NEUP Funded Projects

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Projects by Year

FY 2024 Research and Development Awards

DOE is awarding more than $44 million through NEUP to support 25 university-led nuclear energy research and development projects in 22 states. NEUP seeks to maintain U.S. leadership in nuclear research across the country by providing top science and engineering faculty and their students with opportunities to develop innovative technologies and solutions for civil nuclear capabilities.

A complete list of R&D projects with their associated abstracts is available below.

Title	Institution	Estimated Funding*	Project Description	Abstract	Project Type	Fiscal Year
Neutron Damage and MAX Phase Ternary Compounds	Drexel University			Document	IIR	FY2009
Atomistic Calculations of the Effect of Minor Actinides on Thermodynamic and Kinetic Properties of UO2+x	Georgia Institute of Technology			Document	IIR	FY2009
Maximum Fuel Utilization in Fast Reactors without Chemical Reprocessing	University of California, Berkeley			Document	IIR	FY2009
Developing a High Thermal Conductivity Fuel with Silicon Carbide Additives	University of Florida			Document	IIR	FY2009
Fabrication of Tungsten-Rhenium Cladding Materials via Spark Plasma Sintering for Ultra High Temperature Reactor Applications	University of Idaho			Document	IIR	FY2009
Ionic Liquid and Supercritical Fluid Hyphenated Techniques for Dissolution and Separation of Lanthanides, Actinides, and Fission Products	University of Idaho			Document	IIR	FY2009
Improved Fission Neutron Data Base for Active Interrogation of Actinides	University of Michigan			Document	IIR	FY2009
Utilization of Methacrylates and Polymer Matrices for the Synthesis of Ion Specific Resins	University of Nevada, Las Vegas			Document	IIR	FY2009
Improved LWR Cladding Performance by EPD Surface Modification Technique	University of Wisconsin, Madison			Document	IIR	FY2009
Advanced Models of LWR Pressure Vessel Embrittlement for Low Flux-High Fluence Conditions	University of California, Santa Barbara			Document	LWRS	FY2009
Irradiation Creep in Graphite	Boise State University			Document	NGNP	FY2009
Modeling the Stress Strain Relationships and Predicting Failure Probabilities For Graphite Core Components	Cleveland State University			Document	NGNP	FY2009
TRISO-Coated Fuel Durability Under Extreme Conditions	Colorado School of Mines			Document	NGNP	FY2009
An Innovative and Advanced Coupled Neutron Transport and Thermal Hydraulic Method (Tool) for the Design, Analysis and Optimization of VHTR/NGNP Prismatic Reactors	Georgia Institute of Technology			Document	NGNP	FY2009
Removal of 14C from Irradiated Graphite for Graphite Recycle and Waste Volume Reduction	Idaho State University			Document	NGNP	FY2009
Millimeter-Wave Thermal Analysis Development and Application to Gen IV Reactor Materials	Massachusetts Institute of Technology			Document	NGNP	FY2009
Accurate Development of Thermal Neutron Scattering Cross Section Libraries	North Carolina State University			Document	NGNP	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
Understanding Creep Mechanisms in Graphite with Experiments, Multiscale Simulations, and Modeling	North Carolina State University			Document	NGNP	FY2009
Simulations of the Thermodynamic and Diffusion Properties of Actinide Oxide Fuel Materials	University of Michigan			Document	AFCI	FY2009
Verification & Validation of High-Order Short-Characteristics-Based Deterministic Transport Methodology on Unstructured Grids	North Carolina State University			Document	NGNP	FY2009
Adsorptive Separation and Sequestration of Krypton, I and C14 on Diamond Nanoparticles	University of Missouri, Columbia			Document	AFCI	FY2009
Microscale Heat Conduction Models and Doppler Feedback	North Carolina State University			Document	NGNP	FY2009
Fundamental Understanding of Ambient and High-Temperature Plasticity Phenomena in Structural Materials in Advanced Reactors	Georgia Institute of Technology			Document	AFCI	FY2009
Development of Alternative Technetium Waste Forms	University of Nevada, Las Vegas			Document	AFCI	FY2009
Optimizing Neutron Thermal Scattering Effects in Very High Temperature Reactors	North Carolina State University			Document	NGNP	FY2009
Advanced Elastic/Inelastic Nuclear Data Development Project	Idaho State University			Document	AFCI	FY2009
Heterogeneous Recycling in Fast Reactors	Massachusetts Institute of Technology			Document	AFCI	FY2009
Quantification of UV-Visible and Laser Spectroscopic Techniques for Materials Accountability and Process Control	University of Nevada, Las Vegas			Document	AFCI	FY2009
Multiaxial Creep-Fatigue and CreepRatcheting Failures of Grade 91 and Haynes 230 Alloys Toward Addressing Design Issues of Gen IV Nuclear Power Plants	North Carolina State University			Document	NGNP	FY2009
Thermodynamic Development of Corrosion Rate Modeling in Iron Phosphate Glasses	Missouri University of Science and Technology			Document	AFCI	FY2009
Development of Subspace-Based Hybrid Monte Carlo-Deterministic Algorithms for Reactor Physics Calculations	North Carolina State University			Document	AFCI	FY2009
High-Fidelity Space-Time Adaptive Multiphysics Simulations in Nuclear Engineering	University of Nevada, Reno			Document	AFCI	FY2009
Improvements to Nuclear Data and Its Uncertainties by Theoretical Modeling	Rensselaer Polytechnic Institute			Document	AFCI	FY2009
Investigation of Countercurrent Helium-air Flows in Air-ingress Accidents for VHTRs	Ohio State University			Document	NGNP	FY2009
Sharp Interface Tracking in Rotating Microflows of Solvent Extraction	State University of New York at Stony Brook			Document	AFCI	FY2009
Bulk Nanostructured FCC Steels with Enhanced Radiation Tolerance	Texas A&M University			Document	AFCI	FY2009
Simulations of Failure via Three-Dimensional Cracking in Fuel Cladding for Advanced Nuclear Fuels	University of Texas, Dallas			Document	AFCI	FY2009
Testing of Performance of Optical Fibers Under Irradiation in Intense Radiation Fields, When Subjected to Very High Temperatures	Ohio State University			Document	NGNP	FY2009
Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels	Texas A&M University			Document	AFCI	FY2009
SiC Schottky Diode Detectors for Measurement of Actinide Concentrations from Alpha Activities in Molten Salt Electrolyte	The Ohio State University			Document	AFCI	FY2009
Computational Design of Advanced Nuclear Fuels	University of California, Davis			Document	AFCI	FY2009
Advanced Mesh-Enabled Monte Carlo Capability for Multi-Physics Reactor Analysis	University of Wisconsin, Madison			Document	AFCI	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
A Distributed Fiber Optic Sensor Network for Online 3-D Temperature and Neutron Fluence Mapping in a VHTR Environment	Texas A&M University			Document	NGNP	FY2009
Ab Initio Enhanced Calphad Modeling of Actinide Rich Nuclear Fuels	University of Wisconsin, Madison			Document	AFCI	FY2009
Investigation on the Core Bypass Flow in a Very High Temperature Reactor	Texas A&M University			Document	NGNP	FY2009
Development of Diffusion Barrier Coatings and Deposition Technologies for Mitigating Fuel Cladding Chemical Interactions (FCCI)	University of Wisconsin, Madison			Document	AFCI	FY2009
CFD Model Development and Validation for High Temperature Gas Cooled Reactor Cavity Cooling System (RCCS) Applications	Texas A&M University			Document	NGNP	FY2009
Thermal Properties of LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin, Madison			Document	AFCI	FY2009
Study of Air ingress across the duct during the accident conditions	Texas A&M University			Document	NGNP	FY2009
Verification of the CENTRM Module for Adaptation of the SCALE Code to NGNP Prismatic and PBR Core Designs	University of Arizona			Document	NGNP	FY2009
Integral and Separate Effects Tests for Thermal Hydraulics Code Validation for Liquid-Salt Cooled Nuclear Reactors	University of California, Berkeley			Document	NGNP	FY2009
Mechanisms Governing the Creep Behavior of High Temperature Alloys for Generation IV Nuclear Energy Systems	University of Cincinnati			Document	NGNP	FY2009
ALD Produced B2O3, Al2O3 and TiO2 Coatings on Gd2O3 Burnable Poison Nanoparticles	University of Colorado, Boulder			Document	NGNP	FY2009
Experimental Study and Computational Simulations of Key Pebble Bed Thermomechanics Issues for Design and Safety	University of Idaho			Document	NGNP	FY2009
Prediction and Monitoring Systems of Creep-Fracture Behavior of 9Cr-1Mo Steels for Reactor Pressure Vessels	University of Idaho			Document	NGNP	FY2009
Understanding Fundamental Material Degradation Processes in High Temperature Aggressive Chemomechanical Environments	University of Illinois, Urbana-Champaign			Document	NGNP	FY2009
Multi-Scale Multi-physics Methods Development for the Calculation of Hot-Spots in the NGNP	University of Michigan			Document	NGNP	FY2009
Corrosion and Creep of Candidate Alloys in High Temperature Helium and Steam Environments for the NGNP	University of Michigan			Document	NGNP	FY2009
Creation of a Full-Core HTR Benchmark with the Fort St. Vrain Initial Core and Validation of the DHF Method with Helios for NGNP Configurations	University of Michigan			Document	NGNP	FY2009
Fission Product Sorptivity in Graphite	University of Missouri, Columbia			Document	NGNP	FY2009
Identifying and Understanding Environment-Induced Crack Propagation Behavior in Ni-Based Superalloy INCONEL 617	University of Nevada, Las Vegas			Document	NGNP	FY2009
Graphite Oxidation Simulation in HTR Accident Conditions	University of New Mexico			Document	NGNP	FY2009
Non Destructive Thermal Analysis and In Situ Investigation of Creep Mechanism of Graphite and Ceramic Composites using Phase-sensitive THz Imaging & Nonlinear Resonant Ultrasonic Spectroscopy	University of Rochester			Document	NGNP	FY2009
Tritium Sequestration in Gen IV NGNP Gas Stream via Proton Conducting Ceramic Pumps	University of South Carolina			Document	NGNP	FY2009
Materials, Turbomachinery and Heat Exchangers for Supercritical CO2 Systems	University of Wisconsin, Madison			Document	NGNP	FY2009
Experimental Studies of NGNP Reactor Cavity Cooling System with Water	University of Wisconsin, Madison			Document	NGNP	FY2009
Assessment of Embrittlement of VHTR Structural Alloys in Impure Helium Environments	University of Wisconsin, Madison			Document	NGNP	FY2009
Modeling Fission Product Sorption in Graphite Structures	University of Wisconsin, Madison			Document	NGNP	FY2009
Liquid Salt Heat Exchanger Technology for VHTR Based Applications	University of Wisconsin, Madison			Document	NGNP	FY2009
Effect of Post-Weld Heat Treatment on Creep Rupture Properties of Grade 91 Steel Heavy Section Welds	Utah State University			Document	NGNP	FY2009
Alpha Radiolysis of Nuclear Solvent Extraction Ligands used for An(III) and Ln(III) Separations	California State University, Long Beach	$1,390,252		Document	FCR&D	FY2010
Predictive Maturity of Multi-Scale Simulation Models for Fuel Performance	Clemson University	$614,690		Document	FCR&D	FY2010
Freeze-casting as a Novel Manufacturing Process for Fast Reactor Fuels	Drexel University	$1,149,327		Document	FCR&D	FY2010
Fuel Performance Experiments on the Atomistic Level, Studying Fuel Through Engineered Single Crystal UO2	Idaho State University	$650,000		Document	FCR&D	FY2010
Development of A Self Biased High Efficiency Solid-State Neutron Detector for MPACT Applications	Rensselaer Polytechnic Institute	$810,141		Document	FCR&D	FY2010
Development of a Innovative High Thermal Conductivity UO 2 Ceramic Composites Fuel Pellets with Carbon Nano-Tubes Using Spark Plasma Sintering	University of Florida	$894,042		Document	FCR&D	FY2010
Exploration and Modeling of Structural Changes in Waste Glass under Corrosion	Pennsylvania State University	$1,377,444		Document	FCR&D	FY2010
Evaluation of materials for interim storage of spent fuel for more than 100 years	University of Michigan	$931,603		Document	FCR&D	FY2010
Implementation of On-the-Fly Doppler Broadening in MCNP5 for Multiphysics Simulation of Nuclear Reactors	University of Michigan	$406,712		Document	FCR&D	FY2010
Methods and tools to allow molecular flow simulations to be coupled to higher level continuum descriptions of flows in porous/fractured media and aerosol/dust dynamics	University of Missouri-Columbi	$541,286		Document	FCR&D	FY2010
Characterization and Modeling of Materials for Kr-Xe Separations	University of Nevada-Las Vegas	$989,800		Document	FCR&D	FY2010
Modeling Solute Thermokinetics in LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin-Madison	$616,073		Document	FCR&D	FY2010
Advanced Aqueous Separation Systems for Actinide Partitioning: Develop Fundamental Understanding of An(III)/Ln(III) Separation	Washington State University	$1,451,784		Document	FCR&D	FY2010
Consistent Multigroup Theory Enabling Accurate Coarse-Group Simulation of GenIV Reactors	Georgia Institute of Technology	$1,046,277		Document	GEN IV	FY2010
Studies of Deteriorated Heat Transfer in Prismatic Cores Stemming from Irradiation-Induced Geometry Distortion	Idaho State University	$1,287,921		Document	GEN IV	FY2010
Carbide Coatings for Nickel Alloys, Graphite, and Carbon/Carbon Composites to be Used in Fluoride Salt Valves	Johns Hopkins University	$1,183,239		Document	GEN IV	FY2010
Design, Testing, and Modeling of the Direct Reactor Auxiliary Cooling System for AHTRs	Ohio State University	$1,366,627		Document	GEN IV	FY2010
Monitoring microstructural evolution of Alloy 617 with nonlinear acoustics for remaining useful life prediction; multiaxial creep-fatigue and creep-ratcheting	Pennsylvania State University	$1,000,000		Document	GEN IV	FY2010
Development and Validation of Multidimensional Models of Supercritical CO 2 Energy Conversion Systems for Nuclear Power Reactors	Rensselaer Polytechnic Institute	$475,005		Document	GEN IV	FY2010
Multiscale Concrete Modeling for Aging Degradation	Mississippi State University	$345,941		Document	LWRS	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term and Elevated Temperature Irradiation: Modeling and Experimental Investigation	University of California-Berkeley	$1,320,667		Document	GEN IV	FY2010
Development of an advanced computational fluid dynamics technology for the next-generation nuclear reactor system analysis and safety margin characterization code	North Carolina State University	$418,199		Document	LWRS	FY2010
Development of Barrier Layers for the Protection of Candidate Alloys in the VHTR	University of California-Santa Barbara	$995,232		Document	GEN IV	FY2010
Precursor Derived Nanostructured Si-C-X Materials for Nuclear Applications	University of Washington	$899,518		Document	MRIIR	FY2010
Investigation of a Novel NDE Method for Monitoring Thermo-Mechanical Damage and Microstructure Evolution in Ferritic-Martensitic Steels for Generation IV Nuclear Energy Systems	University of Cincinnati	$833,109		Document	GEN IV	FY2010
Development and Testing of an Open-Loop Oscillator for Small Reactivity Worth Samples	Idaho State University	$597,252		Document	MRIIR	FY2010
Fission Product Transport in TRISO Particle Layers under Operating and Off-Normal Conditions	University of Michigan	$966,581		Document	GEN IV	FY2010
Understanding the Irradiation Behavior of Zirconium Carbide	Pennsylvania State University	$870,613		Document	MRIIR	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term Irradiation at Elevated Temperature: Critical Experiments	University of Michigan	$1,181,379		Document	GEN IV	FY2010
Modeling investigation of the stability and irradiation-induced evolution of nanoscale precipitates in advanced structural materials	University of Tennessee-Knoxville	$380,653		Document	MRIIR	FY2010
Three-dimensional NDE of VHTR Core Components via Simulation-based Testing	University of Minnesota	$1,366,163		Document	GEN IV	FY2010
Investigation of Laser Shock Peening for Enhancing Fatigue and Stress Corrosion Cracking Resistance of Nuclear Energy Materials	University of Cincinnati	$1,242,019		Document	MRIIR	FY2010
Failure Predictions for VHTR Core Components using a Probabilistic Continuum Damage Mechanics Model	University of Minnesota	$854,542		Document	GEN IV	FY2010
Irradiation Accelerated Corrosion of Reactor Core Materials	University of Michigan	$798,943		Document	MRIIR	FY2010
Development of a Scanning Microscale Fast Neutron Irradiation Platform for Examining the Correlation Between Local Neutron Damage and Graphite Microstructure	University of Missouri-Columbia	$703,064		Document	GEN IV	FY2010
Study of Interfacial Interactions using Thin Film Surface Modification: Radiation and Oxidation Effects in Materials	University of Wisconsin-Madison	$538,032		Document	MRIIR	FY2010
Development of Thermal Transient Flow Rate Sensors for High Temperature, Irradiation, Corrosive Environment	University of Nevada-Las Vegas	$451,269		Document	GEN IV	FY2010
Novel Engineered Refractory Materials for Advanced Reactor Applications	North Carolina State University	$1,129,304		Document	MRIIR	FY2010
Novel Methods of Tritium Sequestration: High Temperature Gettering and Separation Membrane Materials Discovery for Nuclear Energy Systems	University of South Carolina	$1,366,626		Document	GEN IV	FY2010
Heat Transfer Salts for Nuclear Reactor Systems - Chemistry Control, Corrosion Mitigation, and Modeling	University of Wisconsin-Madison	$1,352,040		Document	GEN IV	FY2010
Pulsed Magnetic Welding for Advanced Core and Cladding Steels	University of Wisconsin-Madison	$525,206		Document	GEN IV	FY2010
Corrosion in Supercritical Carbon Dioxide: Materials, Environmental Purity, Surface Treatments, and Flow Issues	University of Wisconsin-Madison	$651,447		Document	GEN IV	FY2010
Quantification of Cation Sorption to Engineered Barrier Materials Under Extreme Conditions	Clemson University	$1,171,380		Document	FCR&D	FY2011
In-Pile Instrumentation Multi-Parameter System Utilizing Photonic Fibers and Nanovision	Idaho State University	$1,199,990		Document	FCR&D	FY2011
Development of Plasmonically Cloaked Nanoparticles	Idaho State University	$800,000		Document	FCR&D	FY2011
Fission Product Transmutation in Mixed Radiation Fields	Idaho State University	$800,000		Document	FCR&D	FY2011
Life Prediction of Spent Fuel Storage Canister Material	Massachusetts Institute of Technology	$899,826		Document	FCR&D	FY2011
Active Interrogation using Photofission Technique for Nuclear Materials Control and Accountability	Oregon State University	$900,000		Document	FCR&D	FY2011
Anisotropic Azimuthal Power and Temperature Distribution on Fuel Rod: Impact of Hydride Distribution	Pennsylvania State University	$631,956		Document	FCR&D	FY2011
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$1,000,000		Document	FCR&D	FY2011
Recovery of Uranium from Seawater: Preparation and Development of Polymer-Supported Extractants	City College of New York, Hunter	$363,716		Document	MSTR	FY2011
Microemulsions and Aggregation Formation in Extraction Processes for Used Nuclear Fuel: Thermodynamics and Structural Studies	University of California, Irvine	$1,000,000		Document	FCR&D	FY2011
One-Dimensional Nanostructures for Neutron Detection	North Carolina State University	$455,629		Document	MSTR	FY2011
Optimized Processing Fabrication Paths for Larger Heats of Nanostructured Ferritic Alloys	University of California, Santa Barbara	$1,000,000		Document	FCR&D	FY2011
Feasibility and Safety Assessment for Advanced Reactor Concepts Using Vented Fuel	Oregon State University	$600,000		Document	MSTR	FY2011
Basic Physics Data: Measurement of Neutron Multiplicity from Induced Fission	University of Michigan	$973,364		Document	FCR&D	FY2011
Development of an Efficient Meso-Scale Multi-Phase Flow Solver in Nuclear Applications	City College of New York	$505,858		Document	NEAMS	FY2011
High Temperature Transducers for Online Monitoring of Microstructure Evolution	Pennsylvania State University	$455,628		Document	MSTR	FY2011
Radionuclide Incorporation and Long Term Performance of Apatite Waste Forms	University of Michigan	$862,500		Document	FCR&D	FY2011
Multiscale Modeling and Uncertainty Quantification for Nuclear Fuel Performance	Colorado State University	$1,098,250		Document	NEAMS	FY2011
Laser-Arc Hybrid Welding of Thick Section Ni-base Alloys- Advanced Modeling and Experiments	Pennsylvania State University	$536,117		Document	MSTR	FY2011
Actinide Foil Production for MPACT Research	University of Nevada-Las Vegas	$156,897		Document	FCR&D	FY2011
Fundamental Studies of the Role of Grain Boundaries on Uniform Corrosion of Advanced Nuclear Reactor Materials	Drexel University	$1,098,250		Document	NEAMS	FY2011
Correlates of Sensitive Technologies	Texas A&M University	$509,467		Document	MSTR	FY2011
Enriched Boron-Doped Amorphous Selenium Based Position-Sensitive Solid-State Thermal Neutron Detector for MPACT Applications	University of South Carolina	$1,000,000		Document	FCR&D	FY2011
Phenomena-based Uncertainty Quantification in Predictive Coupled-Physics Reactor Simulations	Texas A&M University	$1,098,250		Document	NEAMS	FY2011
Improved Safety Margin Characterization of Risk from Loss of Offsite Power	Texas A&M University	$600,000		Document	MSTR	FY2011
Development of Advanced High Uranium Density Fuels for Light Water Reactors	University of Wisconsin-Madison	$1,000,000		Document	FCR&D	FY2011
Characterization of Modeling of Grain Boundary Chemistry Evolution in Ferritic Steels Under Irradiation	University of Michigan	$1,098,250		Document	NEAMS	FY2011
Diffusion, Thermal Properties and chemical Compatibilities of Select MAX Phases with Materials for Advanced Nuclear Systems	Drexel University	$535,927		Document	NEET	FY2011
A High Temperature-Tolerant and Radiation-Resistant In-Core Neutron Sensor for Advanced Reactors	The Ohio State University	$455,629		Document	MSTR	FY2011
Developing the User Experience for a Next Generation Nuclear Fuel Cycle Simulator	University of Wisconsin-Madison	$1,200,000		Document	FCR&D	FY2011
Development of Multiscale Materials Modeling Techniques and Coarse-Graining Strategies for Predicting Materials Degradation in Extreme Irradiation Environments	University of Tennessee, Knoxville	$750,000		Document	NEAMS	FY2011
A New Light Weight Structural Material for Nuclear Structures	North Carolina State University	$399,490		Document	NEET	FY2011
Pathway Aggregation in the Risk Assessment of Proliferation Resistance and Physical Protection (PR&PP) of Nuclear Energy Systems	The Ohio State University	$534,471		Document	MSTR	FY2011
Experimental Investigation of Convection and Heat Transfer in the Reactor Core for a VHTR	City College of New York	$1,118,856		Document	RCRD&D	FY2011
Preparation of High Purity, High Molecular-Weight Chitin from Ionic Liquids for Use as an Adsorbate for the Extraction of Uranium from Seawater	University of Alabama	$338,260		Document	MSTR	FY2011
Graphite Microstructural Characterization Using Time-Domain and Correlation-Based Ultrasonics	Johns Hopkins University	$1,199,997		Document	RCRD&D	FY2011
Selectivity in Ligand Binding to Uranyl Compounds: A Synthetic, Structural, Thermodynamic and Computational Study	University of California-Berkeley	$500,000		Document	MSTR	FY2011
Methodology Development for Passive Component Reliability Modeling in a Multi-Physics Simulation Environment	The Ohio State University	$533,457		Document	RCRD&D	FY2011
Development of Seismic Isolation Systems Using Periodic Materials	University of Houston	$538,154		Document	MSTR	FY2011
Pebble Fuel Handling and Reactivity Control for Salt-Cooled High Temperature Reactors	University of California, Berkeley	$612,721		Document	RCRD&D	FY2011
Innovative Elution Processes for Recovering Uranium from Seawater	University of Idaho	$400,000		Document	MSTR	FY2011
Self-Sustaining Thorium Boiling Water Reactors	University of California, Berkeley	$1,145,932		Document	RCRD&D	FY2011
Development of Austenitic ODS Strengthened Alloys for Very High Temperature Applications	University of Illinois-Urbana Champaign	$538,154		Document	MSTR	FY2011
High Fluency Low Flux Embrittlement Models of LWR Reactor Pressure Vessel Embrittlement and a Supporting Database from the UCSB ATR-2 Irradiation Experiment	University of California, Santa Barbara	$1,199,607		Document	RCRD&D	FY2011
Enhancement of the Extraction of the Uranium from Seawater	University of Maryland	$400,000		Document	MSTR	FY2011
A Research Program for Fission Product/Dust Transport in HTGR's	University of Missouri-Columbia	$1,157,367		Document	RCRD&D	FY2011
Transient Safety Analysis of Fast Spectrum TRU Burning LWR with Internal Blankets	University of Michigan	$599,475		Document	MSTR	FY2011
Development and Validation of a Lifecycle-based Prognostics Architecture with Test Bed Validation	University of Tennessee, Knoxville	$846,315		Document	RCRD&D	FY2011
Development of Novel Sorbents for Uranium Extraction from Seawater	University of North Carolina, Chapel Hill	$400,000		Document	MSTR	FY2011
In-situ Condition Monitoring of Components in Small Modular Reactors Using Process and Electrical Signature Analysis	University of Tennessee, Knoxville	$650,000		Document	RCRD&D	FY2011
Radiation Behavior of High-Entropy Alloys for Advanced Reactors	University of Tennessee, Knoxville	$538,159		Document	MSTR	FY2011
Technical Development for S-CO2 Advanced Energy Conversion	University of Wisconsin	$815,000		Document	RCRD&D	FY2011
Rapid Computer Aided Ligand Design and Screening of Precious Metal Extractants from TRUEX Raffinate with Experimental Validation	Washington State University	$500,000		Document	MSTR	FY2011
Ag Transport Through Non-Irradiated and Irradiated SiC	University of Wisconsin-Madison	$1,055,456		Document	RCRD&D	FY2011
Critical Heat Flux Phenomena at High Pressure and Low Mass Fluxes: Tests and Models	University of Wisconsin-Madison	$1,199,781		Document	RCRD&D	FY2011
Modeling and Test Validation of a Reactor Cavity Cooling System with Air	University of Wisconsin-Madison	$1,199,988		Document	RCRD&D	FY2011
Transient Mixed Convection Validation for NGNP	Utah State University	$635,860		Document	RCRD&D	FY2011
Alternative High-Performance Ceramic Waste Forms	Alfred University	$840,000	This project aims to advance fundamental understanding of the kinetics of structural evolution of crystalline ceramic waste forms. The structure/property relationships will be identified and will reveal new formulations, improved processing routes, and strategies for improved performance or ceramic waste forms.	Document	FCR&D	FY2012
Surface Layer Bulk Glass Interface Evolution with Aqueous Corrosion	Alfred University	$880,000	This project will investigate the links between the morphology, structure and chemistry of surface layer-bulk glass interface and the long-term corrosion-reaction kinetics using in-situ and ex-situ experiments. The understanding will result in improved models for long-term predictive behavior of high-level-waste (HLW) glasses under repository conditions.	Document	FCR&D	FY2012
Improved Accident Tolerance of Austenitic Stainless Steel Cladding through Colossal Supersaturation with Interstitial Solutes	Case Western Reserve University	$850,000	This project aims to develop new case-hardened austenitic stainless steels by saturating them with materials that improve their mechanical properties, corrosion resistance and radiation resistance. This project, if successful, will result in safer, longer-lasting, and more accident tolerant fuel claddings.	Document	FCR&D	FY2012
Optimization of Deep Borehole Systems for HLW Disposal	Massachusetts Institute of Technology	$850,000	Researchers aim to carry out a comprehensive evaluation of the deep borehole option for disposal of used nuclear fuel and high livel waste. The models developed will predict potential movement of water through natural and engineered barriers and release of radionuclides to the biosphere which will aide in site selection.	Document	FCR&D	FY2012
Scholarship for Nuclear Communications and Methods for Evaluation of Nuclear Project Acceptability	Massachusetts Institute of Technology	$800,000	Researchers will work to develop a model to characterize the factors affecting social acceptance of nuclear projects with potential stakeholders. The resultant model will strengthen the ability to design and implement large projects more efficiently, leading to higher rates of success of future nuclear projects.	Document	FCR&D	FY2012
Accurate Holdup Calculations with Predictive Modeling and Data Integration	North Carolina State University	$875,000	Researchers will develop and use state-of-the-art radiation transport codes to account accurately for the fissile material in a nuclear materials processing facility. An accurate estimation of the materials will allow for ensured radiological safety, security, waste management and efficient plant operation.	Document	FCR&D	FY2012
Novel Metal Sulfides to Achieve Effective Capture and Durable Consolidation of Radionuclides	Northwestern University	$760,000	Researchers will evaluate the effectiveness of chalcogenide based materials design novel metal sulfides to effectively capture and store of radioisotopes released during reprocessing of used nuclear fuel. This project will focus on understanding structure-property relationships to enable refined and direct synthesis approaches for improved and cost-efficient nuclear waste forms.	Document	FCR&D	FY2012
Nonlinear Ultrasonic Diagnosis and Prognosis of ASR Damage in Dry Cask Storage	Northwestern University	$885,000	Researchers aim to use nondestructive damage characterization methods to detect, manage and mitigate the degradation/damage mechanisms of dry cask storage systems for nuclear fuels. This project, if successful, will provide tools that will allow the prediction of the reliability and the safety of concrete structures in dry cask storage systems.	Document	FCR&D	FY2012
Prototype Demonstration of Gamma-Blind Tensioned Metastable Fluid Neutron/Multiplicity/Alpha Detector- Real Time Methods for Advanced Fuel Cycle Applications	Texas A&M University	$875,000	This project aims to create a prototype demonstration of a novel neutron/alpha detector based on a technology that is blind to gamma field used fuel. The prototype, if successful, will enhance instrumentation for monitoring real-time material balance during various stages of the nuclear cycle.	Document	FCR&D	FY2012
Testing of Sapphire Optical Fiber and Sensors in Intense Radiation Fields, when Subjected to Very High Temperatures	The Ohio State University	$885,000	The researchers on this project will investigate the performance of sapphire optical fibers and sensors in reactor environments. The project, if successful, will result in improved instrumentation to understand the behavior and predict performance of nuclear fuel systems at the microstructural level.	Document	FCR&D	FY2012
Concrete Materials with Ultra-High Damage Resistance and Self-Sensing Capacity for Extended Nuclear Fuel Storage Systems	University of California, Irvine	$800,000	Researchers aim to design a new class of multifunctional concrete materials. This project, if successful, will result in a novel multifunctional concrete material that possesses inherent degradation monitoring capability and is suitable for an extended storage system for the used nuclear fuel.	Document	FCR&D	FY2012
Development of Innovative Accident Tolerant High Thermal Conductivity UO2 Fuel Pellets with a Diamond Dopant	University of Florida	$800,000	Researchers will evaluate the use of diamond nanoparticles composite material in innovative accident tolerant fuel pellets. This could significantly improve both the thermal conductivity of fuel pellets and light water reactors' efficiency safety.	Document	FCR&D	FY2012
Probabilistic Multi-Hazard Assessment of Dry Cask Structures	University of Houston	$865,000	This project aims to investigate the performance of dry cask storage systems under multiple hazard systems (earthquake, tornados, combined with aging effects) using a probabilistic multi-hazard framework. This framework will be validated based on experimental research and will provide improved models for safety and reliability of spent nuclear fuels during storage and transportation.	Document	FCR&D	FY2012
Measurement of Irradiated Pyroprocessing Samples via Laser Induced Breakdown Spectroscopy	University of Idaho	$820,000	This project aims to use advanced characterization techniques to investigate microstructural changes and the micromechanisms related to irradiation induced damage in used nuclear fuels and waste forms. This project, if successful, will result in enhanced models to predict the structural and chemical response of used fuel and waster forms during interim storage and permanent disposal.	Document	FCR&D	FY2012
Elastic/Inelastic Measurement Project	University of Kentucky	$880,523	Researchers will measure nuclear data for elastic/inelastic scattered neutrons on coolants and structural materials. The data generated, will be useful for future R&D programs that will study innovative next generation LWR and future fast systems.	Document	FCR&D	FY2012
Electrochemical Corrosion Studies for Modeling Metallic Waste Form Release Rates	University of Nevada- Las Vegas	$790,000	This project aims to use advanced electrochemical methods to investigate the corrosion related degradation of metal alloys used for housing fission products. The data obtained from this study will allow for the prediction of the long-term behavior of the metallic host phase materials over geological time-scales.	Document	FCR&D	FY2012
Thermodynamic and Microstructural Mechanisms in the Corrosion of Advanced Ceramic Tc-bearing Waste Forms and Thermophysical Properties	University of Nevada- Las Vegas	$795,000	This project team will harvest thermodynamic and microstructural data on the evolution of ceramic based waste forms. The data will be used to advance the current state-of-the-art methodology used for isolation and stabilization of fission products and improve on nuclear fuel recycling processes.	Document	FCR&D	FY2012
Development and Experimental Benchmark of Simulations to Predict Used Nuclear Fuel Cladding Temperatures during Drying and Transfer Operations	University of Nevada- Reno	$745,000	Researchers will conduct experiments to investigate and develop advanced computational models of heat transfer in post-pool-storage drying operations. This project, if successful, will result in tools that can be used to design efficient drying processes to as to ensure suitability for dry-cask systems for long-term storage and transport.	Document	FCR&D	FY2012
Better Radiation Response and Accident Tolerance of Nanostructured Ceramic Fuel Materials?	University of Tennessee	$815,000	Researchers will use novel experimental methods to investigate the links between microstructure, phase stability and damage evolution in nanostructured ceramic fuel materials. The project will study fuel materials at temperatures and irradiation conditions relevant to operation and accidental scenarios.	Document	FCR&D	FY2012
Radiation and Thermal Effects on Used Nuclear Fuel and Nuclear Waste Forms	University of Tennesssee	$770,000	This project aims to investigate the structural and chemical response of used nuclear fuel and waste forms during interim storage and permanent disposal. If successful, this project will generate models that will allow the prediction of structural evolution and hence the radiological safety and security of nuclear fuel and waste forms.	Document	FCR&D	FY2012
Seismic Performance of Dry Casks Storage for Long-Term Exposure	University of Utah	$873,319	Researchers will evaluate the mechanical performance of dry-cask storage under seismic loading for mid-term operational periods. Simulations will include scenarios for freestanding, anchored, and vaulted casks. The experimental tests will also evaluate the dynamic seismic response of freestanding and anchored dry-cask storage prototypes, providing recommendations for optimal Interim Spent Fuel Storage Installations (ISFSIs) design.	Document	FCR&D	FY2012
Validation Experiments for Spent-Fuel Dry-Cask In-Basket Convection	Utah State University	$690,000	Researchers in this project aim to conduct experiments that generate data on natural convection through a fuel assembly. The data will be used to validate the computational models being developed for nuclear safety and design.	Document	FCR&D	FY2012
Re-Branding the Nuclear Fuel Cycle	Virginia Commonwealth University	$850,000	This project will create a comprehensive framework for the evaluation of alternative fuel cycle systems that will be used to identify and analyze key elements related to long-term management of nuclear fuels , with the ultimate goal to develop a communications strategy to reach stakeholders.	Document	FCR&D	FY2012
Advanced Characterization of Molecular Interactions in TALSPEAK-like Separations Systems	Washington State University	$875,000	Researchers will use advanced characterization techniques (experimental and computational) to improve understanding of the molecular level processes/interactions during separation processes for advanced fuel cycles. The understanding of these interactions will be used to develop more robust and streamlined separation processes for advanced fuel cycles.	Document	FCR&D	FY2012
Coupling of Nuclear Waste Form Corrosion and Radionuclide Transport in Presence of Relevant Repository Sediments	Washington State University	$885,000	Researchers will conduct experiments to understand the mechanisms responsible for the corrosion of nuclear waste forms in realistic chemical environments. The data generated from these experiments will enable increased reliability of the models used to predict the waste form performance in repository environments.	Document	FCR&D	FY2012
Stationary Liquid Fuel Fast Reactor (SLFFR) Concept for TRU Burning	Purdue University	$450,000	Reasearchers will investigate a new type of molten metallic fuel reactor concept that will consume hazardous transuranic waste. The liquid fuel alloy has several advantages over solid fuel fast reactors that are used for the same purpose.	Document	MSTR	FY2012
ABR for TRU Transmutation with Breed & Burn Thorium Blanket for Improved Economics and Resource Utilization	University of California- Berkeley	$450,000	The research team will use detailed neutronic analysis for a new Advanced Burner Reactor concept with low conversion ratio. The concept will use a new core shape to improve the utilization of neutrons to perform breed and burn.	Document	MSTR	FY2012
New Materials for High Temperature Thermoelecric Power Generation	University of California, Davis	$450,000	Reasearchers will work to develop nanostructured and other new materials to support the development of higher efficiency thermoelectric devices. These devices convert thermal energy to electricity with no moving parts. The new materials will operate at higher efficiencies and over a wider temperature range than those currently available--an important quality for future nuclear-powered deep space exploration.	Document	MSTR	FY2012
Microscopic Fuel Particles Produced by Self-Assembly of Actinide Nanoclusters on Carbon Nanomaterials	University of Notre Dame	$440,000	Reasearchers will develop the mechanisms, conditions and protocols to prepare uranium-carbon nanocomposite materials to make them more flexible. This could result in the generation of wholesale electricity, providing process heat, and providing power for households.	Document	MSTR	FY2012
High Hydrogen Content Graphene Hydride Compounds & High Cross-Section Cladding Coatings for Fast Neutron Detection	University of South Carolina	$430,000	This project will exploit recent breakthroughs to grow epitaxial graphene on commercial SiC wafers. This will allow researchers to develop a new detection method for fast neutrons. In addition, it will lead to better and more compact neutron detection system.	Document	MSTR	FY2012
Reducing Actinide Production Using Inert Matrix Fuels	University of Texas- Austin	$435,000	Reasearchers will perform a neutronic analysis, a thermal-hydraulic analysis and a simulation of fuel decay heat as a functionof fuel burnup, to determine if inert matrix fuel in coventional reactors will continue to be licensable. If successful, the inert matrix fuel mixtures will reduce harmful transuranic components in the fuel discharge streams at a level comparable to a fast reactcor burner.	Document	MSTR	FY2012
An Integrated Fuel Depletion Calculator for Fuel Cycle Options Analysis	University of Texas- Austin	$395,000	Reasearchers use new analysis techniques to better predict nuclear fuel behavior. The new model will allow improved fuel cycle for a larger number of users.	Document	MSTR	FY2012
Atomic-Scale to Meso-Scale Simulation Studies of Thermal Ageing and Irradiation Effects in Fe-Cr Alloys	Boston University	$874,997	Reasearchers will develop predictive, multi-scale simulation tools for iron-chromium alloys, which are expected to be key components of advanced steels envisioned as fuel cladding and structural components for Generation IV reactors. Such modeling is necessary to avoid resource intensive and costly thermal and neutron irradiation experiments to obtain required performance data.	Document	NEAMS	FY2012
Validation Data and Model Development for Fuel Assembly Response to Seismic Loads	George Washington University	$862,435	Reasearchers will conduct experiments that will provide comprehensive data characterizing the dynamics of the fluid and the structure in Pressurized Water Reactors (PWR) fuel assemblies under seismic loads (earthquakes and loss of coolant accidents). Completion of their project will greatly benefit the safety of existing and future nuclear reactors.	Document	NEAMS	FY2012
Uncertainty Quantification and Management for Multiscale Nuclear Materials Modeling	Georgia Institute of Technology	$743,444	Reasearchers will address the question of uncertainty propogation and error estimates associated with model prediction of material behavior under irradiation. Their work will facilitate a better understanding of the connection of various unit processes to collective responses in a multiscale model chain enabling the development of high strength and high ductility materials.	Document	NEAMS	FY2012
Fuel and Core Design Options to Overcome the Heavy Metal Loading Limit and Improve Performance and Safety of Liquid Salt Cooled Reactors	Georgia Insitute of Technology	$784,689	Reasearchers will examine new options for fuel and core designs in liquid salt cooled reactors where the current standard of TRISO type fuel has limitations due to loading characteristics. The research could enable new, more feasible fuel-core-reload options that will improve safety and performance parameters.	Document	RCRD&D	FY2012
Nonlinear Ultrasonic Techniques to Monitor Radiation Damage in RPV and Internal Components	Georgia Institute of Technology	$877,000	Reasearchers will explore new nondestructive materials evaluation and monitoring techniques utilizing nonlinear ultrasonic measurements . This technique will allow researchers to assess remaining useful life of select reactor components. Breakthroughs in this area will lead to the ability to characterize radiation damage in reactor pressure vessels and other components-leading to a clearer definition of reactor safety margins.	Document	RCRD&D	FY2012
Intergral Reactor Containment Condensation Model and Experimental Validation	Oregon State University	$871,119	Reasearchers will conduct experiments to enhance the safety and efficiency of small modular reactors (SMRs). This project will assess the impact of high-pressure steam condensation on steel containment vessels to be used for SMR deigns.	Document	RCRD&D	FY2012
Investigation of Natural Circulation Instability and Transients in Passively Safe Small Modular Reactors	Purdue University	$871,100	Reasearchers will perform scaled experiments to study the thermal-hydraulic instabilities that can occur in Small Modular Reactors (SMR) which rely on natural circulation cooling during normal operation and accident conditions. Their work will not only improve our understanding of general natural circulation instability but also lead to the development of stability criteria and predictability in the operation of SMRÃs.	Document	RCRD&D	FY2012
Thermoelectric-Driven Sustainable Sensing and Actuation Systems for Fault-Tolerant Nuclear Incidents	State University of New York, Stony Brook	$599,802	Reasearchers will examine the use of solid-state thermoelectric generators to produce electricity to sense and opeate during both normal and abnormal situations. This will provide indefinite monitoring of key components during power outages or station blackouts.	Document	RCRD&D	FY2012
Experimental and CFD Studies of Coolant Flow Mixing within Scaled Models of the Upper and Lower Plenums of NGNP Gas-Cooled Reactors	Texas A&M University	$713,051	Reasearchers will model the internal coolant flow of a prismatic core very high temperature reactor (VHTR) by using large eddy simulation tools. This method will enable more accurate prediction of flow field characteristics and better evaluation of VHTR behavior under operational and accidental conditions.	Document	RCRD&D	FY2012
Demonstrating Hybrid Heat Transport and Energy Conversion System Performance Characterization Using Intelligent Control Systems	University of Idaho	$877,000	Reasearchers will demonstrate an intelligent control systems in a hybrid energy conversion loop for a next generation nuclear power plant. Hybrid energy systems are a method of optimizing the use of natural resources for energy production. Hybrid systems present an opportunity to develop domestic energy sources to improve energy security.	Document	RCRD&D	FY2012
Advanced Reactor-Intermediate Heat Exchanger (IHX) Coupling: Theoretical Modeling and Experimental Validation	University of Idaho	$869,997	Reasearchers will model the behavior of the Advanced Reactor Intermediate Heat Exchanger Chemical Process system and develop advanced control techniques that take into account abnormal scenarios. The data and information obtained will assist in the development of intelligent control systems for next generation nuclear reactor systems.	Document	RCRD&D	FY2012
Irradiation Performance of Fe-Cr Base Alloys	University of Illinois- Urbana Champaign	$876,332	Reasearchers will perform post-radiation analysis and develop tools for future development and application of the Fe-Cr class of alloys. The results of this research will lead to better modeling of performance and development of an alloy designated as the primary choice for reactor fuel cladding and structural applications in advanced systems.	Document	RCRD&D	FY2012
Accelerated Irradiations for High Dose Microstructures in Fast Reactor Alloys	University of Michigan	$831,876	Reasearchers will determine the extent to which high dose rate irradiation can be used as an irradiation damage tool to understand microstructure evolution at high doses and temperatures relevant to advanced fast reactors. The project will provide fundamental understanding of the effectiveness of this process and thus of microstructure development in irradiated materials.	Document	RCRD&D	FY2012
Mitigating IASCC of Reactor Core Internals by Post-Irradiation Annealing Advanced Mitigation Strategies	University of Michigan	$876,985	Reasearchers will determine the optimum Post-irradiation annealing (PIA)-driven mitigation strategy to extend the potential lifetime of light water reactors. Samples that have already been irradiated in a light water reactor will be used to test PIA treatments to understand IASCC initiation and propoagation, annealing kinetics, the role of microstructure features in irradation hardening and localized deformation, and the optimum mitigation strategy based on PIA.	Document	RCRD&D	FY2012
Experimentally Validated Numerical Models for Effects of Non-Isothermal Turbulent Mixing on Wall Stresses in High Temperature Reactors	University of Pittsburgh	$876,422	Reasearchers will develop a comprehensive experimentally validated computational framework for the turbulent mixing in the lower plenum of a very high temperature reactor (VHTR). Through CFD modeling and experimental validation, the results from this project will lay the groundwork for future stress analysis, failure and fatigue studies, and uncertainty quantification for the VHTR system.	Document	RCRD&D	FY2012
Role of Defects in Swelling and Creep of Irradiated SiC	University of Wisconsin- Madison	$875,350	Reasearchers will study mechanisms controlling both radiation swelling and radiation creep in silicon carbide. These two effects are crucial to understanding the issues associated with the brittle silicon carbide composite. Success in this project will ground progress in the adoption of silicon carbide for reactor solutions, particularly as fuel cladding.	Document	RCRD&D	FY2012
Advanced Supercritical Carbon Dioxide Brayton Cycle Development	University of Wisconsin, Madison	$877,000	Reasearchers will investigate the benefits of utilizing advanced Brayton cycles with supercritical carbon dioxide in new reactor systems and components. Benefits of this research include improvement of analysis and performance of components currently utilizing these cycles as well as the potential for a large scale advanced CO2 power system.	Document	RCRD&D	FY2012
Mechanical Behavior of UO2 at Sub-grain Length Scales: Quantification of Elastic, Plastic and Creep Properties via Microscale Testing	Arizona State University	$800,000	Reasearchers will develop techniques to measure properties at sub-grain scales using depleted Uranium Oxide samples. The project will provide a framework to measure sub-grain scale mechanical properties, as well as provide experimental data to improve the understanding of advanced oxide fuels.	Document	FCR&D	FY2013
The Impacts of Pore-Scale Physical and Chemical Heterogeneities on the Transport of Radionuclide-Carrying Colloids	Colorado School of Mines	$800,000	Reasearchers will identify the dominant transport mechanisms to develop models that predict radionuclide distribution in porous materials. Experimental and computational models will be created that couple pore-scale geometric and interfacial structures. Simulators such as these are a necessary step towards fully predictive models for field-scale applications in the future.	Document	FCR&D	FY2013
Recovery of Uranium from Seawater: Polymer-Supported Aminophosphinates as Selective Extractants	Hunter College, CUNY	$399,999	Reasearchers will prepare a polymer-supported extractant for the recovery of uranium from seawater. The project will focus on primary amines that could provide a 3-fold increase in uranium capture capacity than current methods.	Document	FCR&D	FY2013
In-pile Thermal Conductivity Characterization with Single-laser Heating/Time Resolved Raman	Iowa State University	$800,000	Reasearchers will develop a time-resolved Raman-based thermal conductivity measurement system to improve remote in-pile thermal conductivity measurement. These measurements will provide new insights into the behavior of materials exposed to extreme radiation and temperature environments. Understanding the behavior of materials at the microstructural level will support optimized fuel designs.	Document	FCR&D	FY2013
Organic Speciation and Interactions in ALSEP - One Step Partitioning Process of Minor Actinides, Lanthanides, and Fission Products	Oregon State University	$600,000	Reasearchers will investigate the Actinide-Lanthanide Separation (ALSEP) process organic phase prior to aqueous phase separation and after aqueous separation phases of bare and metal-loaded acids. Quantifying these effects can be used to determine how an engineering scale process will perform and generate an accurate chemical model for the system.	Document	FCR&D	FY2013
Glass Composition and Solution Speciation Effects on Stage III Dissolution	Pennsylvania State University	$700,000	Reasearchers will study the chemical and structural triggers of long-term vitrified nuclear waste form behavior. They will study a range of waste glass compositions in corrosive environments. The study will improve understanding of the long-term residual rate and may provide new options for environmental control of glass dissolution rates.	Document	FCR&D	FY2013
Correlating Thermal, Mechanical, and Electrical Coupling Based Multiphysics Behavior of Nuclear Materials Through In-Situ Measurements	Purdue University	$800,000	Reasearchers will use in-situ experimental techniques to monitor the influence of extreme conditions on fuel cladding. The project will establish an in-situ experimental setup that can predict change in thermal properties and their correlation with mechanical properties and correlate such changes to changes in microstructural and chemical features.	Document	FCR&D	FY2013
Creation of a Geant4 Muon Tomography Package for Imaging of Nuclear Fuel in Dry Cask Storage	Purdue University	$440,000	Reasearchers will develop a simulation and analysis package to aid in the non-destructive assessment of sealed used nuclear fuel dry casks using cosmic ray muons. Cosmic ray muon tomography allows for non-destructive assessment that can independently verify and identify weapons grade material sealed within dense dry casks.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Two-stage Fast Reactor Fuel Cycle Options for Optimum Resource Utilization and Waste Management	Purdue University	$400,000	Reasearchers will evaluate the two different two-stage fast reactor fuel cycle options that will offer efficient use of uranium resources and the ability to burn actinides and long-live fission products. Evaluation of these fast fuel cycle options will serve as a useful complement to the options currently being considered in the Fuel Cycle Options Campaign.	Document	FCR&D	FY2013
Mixed Metal Phosphonate-Phosphate Resins for Separation of Lanthanides from Actinides	Texas A&M University	$650,000	Reasearchers will use ion exchangers to cleanly separate lanthanides and curium from reusable actinides. The study will assist in the development of an inexpensive, simple way in which to separate lanthanides from actinides found in used nuclear fuel rods and to recover a large portion of the usable fuel.	Document	FCR&D	FY2013
Safeguards in Pyroprocessing: an Integrated Model Development and Measurement Data Analysis	The Ohio State University	$626,151	Reasearchers will develop a comprehensive and effective safeguards approach for a pyroprocessing facility to support safeguards for future fuel cycles in the United States. The new approach and design will focus directly on the special nuclear materials in the electrorefiner where actinides are separated from fission products through electrochemical process.	Document	FCR&D	FY2013
Using Ionic Liquids for the Development of Renewable Biopolymer-Based Adsorbents for the Extraction of Uranium from Seawater and Testing Under Marine Conditions	University of Alabama	$400,000	Reasearchers will explore the fundamental engineering parameters for a renewable high-performance adsorbent for the extraction of uranium from sweater based on a recently proven ionic liquid (IL)-chitin platform. The project will use the platform to develop a versatile, modifiable adsorbent and characterize its performance and degradation in marine conditions.	Document	FCR&D	FY2013
Developing Ultra-Small Scale Mechanical Testing Methods and Microstructural Investigation Procedures for Irradiated Materials.	University of California, Berkeley	$800,000	Reasearchers will develop new small-scale mechanical testing techniques to allow for the estimation or direct measurement of bulk properties. The combined experiments and modeling will significantly enhance the statistics and information that can be obtained on small radioactive archived samples, as well as new ion beam irradiated specimens.	Document	FCR&D	FY2013
Improved Delayed-Neutron Spectroscopy Using Trapped Ions	University of California, Berkeley	$400,000	Reasearchers will develop innovative spectroscopy techniques to measure the decay of fission fragments. The resulting data from these new techniques will be used to better understand reactor kinetics under accident conditions and failure scenarios.	Document	FCR&D	FY2013
Thermally and Chemically Responsive Nanoporous Materials for Efficient Capture of Fission Product Gases	University of California, Davis	$750,000	Reasearchers will create new nanoporous materials that will be highly effective at capturing fission product gases. These materials would be relevant to both reactor fuels applications and reprocessing operations. Tests will be performed in carbon based and nitride based nanostructures, with the most promising materials from the modeling perspective undergoing further testing.	Document	FCR&D	FY2013
Multiphase Nanocrystalline Ceramic Concept for Nuclear Fuel	University of California, Irvine	$800,000	Researchers will study the use of nanoparticles and nanostructured ceramics to create new materials that can extend the service life and increase efficiency for nuclear fuel. Multiphase nanocrystalline ceramics will be used to design simulated nuclear fuel that can provide added plasticity, better radiation tolerance and improved thermal conductivity.	Document	FCR&D	FY2013
Development of Novel Porous Sorbents for Extraction of Uranium from Seawater	University of Chicago	$400,000	Reasearchers will develop a highly porous sorbent for the extraction of uranium from seawater. Previous research has established sorbent performance. This project will use past foundational studies to design and investigate a new nanocomposites that will be processed into tacks or braids for field tests in seawater tests. The technology may also be used for other metals.	Document	FCR&D	FY2013
Microwave Readout Techniques for Very Large Arrays of Nuclear Sensors	University of Colorado, Boulder	$799,937	Reasearchers will develop a powerful readout technique based on microwave transmission and reflection. The technique will enable very large arrays of diverse sensor types for nuclear materials quantification and tracking. It will provide more accurate data on material composition and quantity.	Document	FCR&D	FY2013
BiI3 Gamma-Ray Spectrometers for Reliable Room-Temperature Nuclear Materials Safeguarding	University of Florida	$799,999	Reasearchers will develop gamma-ray spectrometers based on BiI3 single crystals for MPACT applications such as burnup validation quantification, improved assay of plutonium, determination of uranium enrichment and overall monitoring spent fuel within the fuel cycle. The project will improve energy resolution, efficiency and environmental performance with this new gamma-ray detector.	Document	FCR&D	FY2013
Innovative Coating of Nanostructured Vanadium Carbide on the F/M Cladding Tube Inner Surface for Mitigating the Fuel Cladding Chemical Interactions	University of Florida	$760,276	Researchers will develop barrier coatings on the inner surface of fuel cladding tubes to improve performance of materials at elevated temperatures and high neutron exposures in fast reactors. The project will develop and test a low temperature coating process of nanostructured vanadium carbide that will provide a benchmark for use in future studies.	Document	FCR&D	FY2013
Doubling the Life of Concrete Structures	University of Idaho	$800,000	Reasearchers will use nanoscale techniques to develop methods for doubling the service life of concrete structures. They will study the effect of temperature load and temperature cycling (freezing and thawing) on the durability of concrete with nanoscale viscosity modifiers. The project will benefit from non-destructive evaluation of concrete performance through electrochemical techniques.	Document	FCR&D	FY2013
Off-Gas Treatment: Evaluation of Nano-structured Sorbents for Selective Removal of Contaminants	University of Idaho	$785,910	Reasearchers will evaluate nanostructured sorbent materials for their effectiveness in removing and immobilizing radionuclides for the off-gas treatment from used nuclear fuel recycling operations. The project aims at achieving near-zero emissions of radionuclides by capturing them from the off-gas of recycling operations, allowing for the development of advanced fuel cycles.	Document	FCR&D	FY2013
Innovative Elution Processes for Recovering Uranium and Transition Metals from Amidoxime-Based Sorbents	University of Idaho	$399,864	Reasearchers will develop a new two-step elution process to achieve total recovery of uranium and effective recycling of the sorbent. The extraction process would selectively remove uranium from the sorbent with little or no damage. The process would then remove transition metals and regenerate the sorbent for repeated use, making uranium extraction from seawater economically viable.	Document	FCR&D	FY2013
Performance of a Steel/Oxide Composite Waste Form for Combined Waste Streams from Advanced Electrochemical Processes over Geologic Time Scales	University of Illinois at Chicago	$700,000	Reasearchers will develop and validate a mechanistically-based corrosion model for cermet-type waste forms, creating a testing protocol and modeling approach for predicting long-term performance. The study will apply novel electrochemical testing and modeling methods to the behavior of metal/oxide phase boundaries to evaluate waste form performance.	Document	FCR&D	FY2013
Enhancement of the Extraction of Uranium from Seawater	University of Maryland, College Park	$400,000	Reasearchers will develop and optimize novel adsorbents for uranium recovery from seawater. The team will use radiation-induced grafting of organic phosphates onto polymers. The experiments will use ocean water, with mechanistic analysis, to provide a solid basis for large-scale demonstration of the performance of the new adsorbents in ocean environments.	Document	FCR&D	FY2013
Improving the Understanding of the Coupled Thermal-Mechanical-Hydrologic Behavior of Consolidating Granular Salt	University of New Mexico	$800,000	Reasearchers will increase the understanding of granular salt seal materials for shafts, drifts and boreholes. By coupling thermal, mechanical and hydrological responses, the study will result in greater confidence in granular salt consolidation as a principal strategy for closure and isolation of long-term waste repositories.	Document	FCR&D	FY2013
Fission Fragment Yield Data in Support of Advanced Reactor Technology	University of New Mexico	$399,816	Reasearchers will produce a highly accurate data set for thermal fission. These precision data are necessary for high-accuracy simulations of nuclear criticality, transmutation rates, radiation effects and heating as well as for nuclear fuel, material accounting and identification needs.	Document	FCR&D	FY2013
Molecular dynamics-based simulations of bulk/interfacial structures and diffusion behaviors in nuclear waste glasses	University of North Texas	$700,000	Reasearchers will generate accurate atomic structural models for use in Monte Carlo simulations of the dissolution of nuclear waste glasses. Large-scale molecular dynamics-based computer simulations will be used to investigate self-diffusion behaviors, interfacial structure, and other structures formed during dissolution of these glasses.	Document	FCR&D	FY2013
U3Si2 Fabrication and Testing for Implementation into the BISON Fuel Performance Code	University of South Carolina	$800,000	Reasearchers will fabricate, test and model a high uranium density, advanced nuclear fuel that operates at a much lower temperature and stores less energy. The work will deliver key research data on creep and grain growth, improving economics, through possible power uprates, and advancing accident tolerant fuels research.	Document	FCR&D	FY2013
Structural Health Monitoring of Nuclear Spent Fuel Storage Facilities	University of South Carolina	$738,618	Reasearchers will develop a nuclear structural health monitoring system based on a sensing technology that monitors material degradation and aging for dry cask storage systems. The low-cost, low-profile sensors will perform on-demand monitoring of the structural integrity of individual components as well as the entire system.	Document	FCR&D	FY2013
ORIGEN-based Nuclear Fuel Depletion Module for Fuel Cycle Assessment	University of Tennessee at Knoxville	$755,181	Reasearchers will develop a flexible reactor analysis module for the CYCLUS fuel cycle simulator based on established tools for reactor fuel depletion and decay. They will use ORIGEN, a mature and experimentally validated code, affording greater flexibility and allowing for accurate evaluations of impacts of both present and future fuel cycle options.	Document	FCR&D	FY2013
Cost and System Analysis of Innovative Fuel Resources Concepts	University of Texas at Austin	$295,960	_This project will develop and test braided polymer fiber adsorbents that surpass the sorption capacity, selectivity and durability of the best existing technology to recover uranium from seawater.	Document	FCR&D	FY2013
Risk Assessment of Structural Integrity of Transportation Casks	University of Utah	$789,296	Reasearchers will assess the loss of structural integrity of transportation casks and fuel cladding after extended storage. This risk assessment will conduct experimental tests and simulations to evaluate the structural performance of fuel, fuel assemblies and cask components when subjected to vibration and impact loads during transport.	Document	FCR&D	FY2013
Market-Based and System-Wide Fuel Cycle Optimization	University of Wisconsin, Madison	$612,731	Reasearchers will create market and economic optimizers to improve calculations for the CYCLUS fuel cycle simulator. The team will leverage existing optimization software frameworks within the simulator to resolve top level policy questions. The optimizations will allow CYCLUS to move beyond static material compositions, providing a holistic view of the fuel cycle system.		FCR&D	FY2013
Optical Fiber Based System for Multiple Thermophysical Properties for Glove Box, Hot Cell and In-Pile Applications	Utah State University	$799,975	Reasearchers will use a small pressure vessel to develop a robust technique for the measurement of multiple thermophysical properties at very high temperatures. The technique will lead to a system design moving toward the eventual measurement of irradiated fuels in a glovebox and/or hot cell with all sensors and electronics outside of the glovebox and/or hot cell.	Document	FCR&D	FY2013
Development of a Nano-Modified Concrete for Next Generation of Storage Systems	Vanderbilt University	$796,268	Reasearchers will use nano-sized and nano-structured particles based on enhanced reactivity to develop a superior concrete for the long-term storage of used nuclear fuel. The project will use state-of-the-art experimental chemical and mechanical characterizations and computation analysis to assess the performance of nano-modified concretes.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Thorium Fuel Cycle Options	Vanderbilt University	$797,995	Reasearchers will develop six fuel cycle data packages for multi-stage, thermal fuel cycles which incorporate thorium. These new fuel cycle data packages will provide the opportunity to examine fuel cycle options beyond those which have traditionally been considered. A thorium fuel cycle database will also be assembled as a basis for thorium literature for future evaluations of the thorium fuel cycle.	Document	FCR&D	FY2013
Enhanced Shielding Performance of HLW Storage Packages via Multi-Component Coatings	Virginia Polytechnic Institute and State University	$796,947	Reasearchers will develop a multi-layer composite that will enhance long-term storage and facilitate safe transport of storage packages. This novel multi-layer, multi-component coating would create an outer shield material that is resistant to the corrosion, radiation, diffusion and thermal cycling processes that affect fuel packages during long term storage.	Document	FCR&D	FY2013
Managing Zirconium Chemistry and Phase Compatibility in Combined Process Separations for Minor Actinide Partitioning	Washington State University	$700,000	Reasearchers will address unique challenges for combining TRUEX and TALSPEAK processes for partitioning of lanthanides and minor actinides. The project will develop improved information on the thermodynamics of fission product zirconium and develop a framework for an organic phase solvation model. Combined process development could streamline separations processes.	Document	FCR&D	FY2013
Advances in the Recovery of Uranium from Seawater: Studies Under Real Ocean Conditions	Woods Hole Oceanographic Institution	$398,882	Reasearchers will provide infrastructure and expertise for marine testing of currently available adsorbents in real ocean conditions. The team will move adsorbent research from the lab to field testing in order to quantify sorptive properties and uranium uptake. The project will provide valuable field data that will show the potential of large scale applications of these technologies.	Document	FCR&D	FY2013
NEUP Project 20-19172: Irradiation of Sensors and Adhesive Couplants for Application in LWR Primary Loop Piping and Components		$497,881	Reasearchers paln to attach ultrasonic transducers to substrates using various adhesive couplants that will be irradiated at elevated temperature to simulate LWR primary loop conditions at the PULSTAR reactor at North Carolina State University. Ultrasonic data will be taken in-situ. Subsequently, the sensors and couplant interfaces will be characterized using the LAMDA facility at ORNL. The results will be used to benefit a parallel EPRI project on online monitoring of cracks in LWR primary loop piping._	Document	R&D NSUF	FY2013
NEUP Project 20-19404: Extension of MSTDB to Provide a High-Quality, Validated Thermochemical Database for Predicting/Simulating Corrosion in Molten Salt Reactor SystemsUniversity of South Carolina		$600,000	Reasearchers will generate a validated, consistent database of initial fuel compositions and potential corrossion products of fluoride and chloride salts, allowing for important phenomena predictions in molten salt reactors to guide confident decisions. The database will be integral to the currently being developed Molten Salt Thermochemical Database (MSTDB), structured to allow use by commercial and open source codes._	Document	NEAMS	FY2013
Lower Length Scale Characterization and Validation of Formation and Stability of Helium Bubbles in Nano-structured Ferritic Alloys under Irradiation	Clemson University	$399,870	Reasearchers will provide a fundamental knowledge about the formation and stability of ultra-fine helium bubbles within 14YWT after neutron/ion irradiation for further design of new advanced structural materials with a characteristic high density nanoparticles feature which can increase the mechanical strength, hardness, irradiation resistance and the operational temperature range of materials.	Document	NEAMS	FY2013
Three-Dimensional Fuel Pin Model Validation by Prediction of Hydrogen Distribution in Cladding and Comparison with Experiment	Pennsylvania State University	$800,000	Reasearchers will validate important three-dimensional aspects of the fuel pin modeling by using specialized numerical modeling techniques coupled with laboratory experiments to validate existing models for predicting fuel performance in light water reactors.	Document	NEAMS	FY2013
Collocation-Based Surrogate Models for Uncertainty Quantification and Validation of Coupled, Multiphysics Fuel Performance Simulation Tools	University of Michigan	$596,835	Reasearchers will provide the necessary high fidelity, coupled, multiphysics fuel performance simulator for computational modeling and develop surrogates which will accelerate and focus the validation of the coupled codes. This will be achieved by utilizing the high fidelity coupled fuel performance, thermal-hydraulics and neutronics codes BISON/STAR-CCM+/MPACT and an innovative collocation-based surrogate methodology.	Document	NEAMS	FY2013
Multi-Resolution In-Situ Testing and Mutliscale Simulation for Creep Damage Fatigue Damage Analysis of Alloy 617	Arizona State University	$800,000	This project will develop novel testing and experimentally validated prediction methodologies for micro-structural damage mechanisms of structural materials for advanced reactor systems. The investigations will focus on the characterization and testing of specific metal alloys, but the proposed testing and life-prediction methodologies are applicable to other structural materials as well.	Document	RCRD&D	FY2013
Novel High Temperature and Radiation Resistant Infrared Glasses and Optical Fibers for Sensing in Advanced Small Modular Reactors	Clemson University	$800,000	Clemson University, in partnership with the Iowa State University and the Pacific Northwest National Laboratory, will develop novel optical materials with improved heat and radiation exposure resistance in order to enable in-vessel fiber optic sensing for advanced Small Modular Reactors.	Document	RCRD&D	FY2013
Validation Data Acquisition in HTTF during PCC Events	George Washington University	$800,000	Reasearchers at the George Washington University and Oregon State University will collaborate with NASA Langley Research Center to measure flow velocities in a high temperature test facility. This work supports the development of very-high temperature reactors with passive safety systems.	Document	RCRD&D	FY2013
Advanced High Temperature Inspection Capabilities for Small Modular Reactors	Iowa State University	$790,822	The objective of this project is to develop non-destructive evaluation techniques for advanced small modular reactors. The research will provide key enabling inspection technologies needed to support the design and the reactor component performance validation process for advanced small modular reactors.	Document	RCRD&D	FY2013
Experimental and Computational Investigations of Plenum-to-Plenum Heat Transfer under Natural Circulation in a Prismatic Very High Temperature Reactor	Missouri University of Science and Technology	$799,999	Reasearchers will perform experimental and computational investigations to study heat transfer and natural circulation phenomena in very-high temperature reactors. The study will assist in the ability to predict and analyze passive safety systems.	Document	RCRD&D	FY2013
New Mechanistic Models of Creep-Fatigue Crack Growth Interactions for Advanced High Temperature Reactor Components	Oregon State University	$790,790	Reasearchers will create and validate a robust, multi-scale, numerical model to predict material degradation in nickel-based reactor alloys. If successful, this project will provide better numerical tools for reactor designers and greatly improve their capability to design against material failures for reactor alloys in the long term.	Document	RCRD&D	FY2013
Self-Powered Wireless Dual-mode Langasite Sensor for Pressure/Temperature Monitoring of Nuclear Reactors	State University of New York, Stony Brook	$800,000	This research will develop a novel self-powered wireless hybrid sensor that can accurately monitor both pressure and temperature using a single device without requiring external electricity, even in extreme harsh environments.	Document	RCRD&D	FY2013
Compact Heat Exchanger Design and Testing for Advanced Nuclear Reactors and Advanced Power Cycles	The Ohio State University	$800,000	The goal of this project is to investigate optimal heat exchanger designs for advanced reactors. The research will study the optimization of printed circuit heat exchangers for specific fluids under a variety of conditions as well as perform numerical modeling. Experiments will focus on thermal performance and heat stress during extreme conditions.	Document	RCRD&D	FY2013
Fundamental Understanding of Creep-Fatigue Interactions in 9Cr-1MoV Steel Welds	The Ohio State University	$798,000	This project will advance the state of knowledge and fundamental understanding of deforming materials and welds under loading conditions. Specifically, new integrated testing procedures will be evaluated and applied for conditions that are most detrimental to material stability leading to improved predictions of life expectancy for reactor steels and welds.	Document	RCRD&D	FY2013
Advanced Mechanistic 3D Spatial Modeling and Analysis Methods to Accurately Represent Nuclear Facility External Event Scenarios	The Ohio State University	$800,000	Reasearchers will develop three-dimensional characterization uncertainty analysis for commercial power plants. The project will involve combining experts from the fields of seismic structural modeling and advanced methods of risk assessment. This effort is expected to result in next generation tools that can be used for assessment of seismic risks.	Document	RCRD&D	FY2013
Tritium Mitigation/Control for Advanced Reactor Systems	The Ohio State University	$400,000	Reasearchers will develop a fluoride salt cooled high-temperature reactor featuring a specialized system to control tritium production. If successful, this will result in a significant reduction in size and cost in comparison to other reactor designs.	Document	RCRD&D	FY2013
A Pebble-Bed Breed and Burn Reactor	University of California, Berkeley	$400,000	Reasearchers will assess the feasibility of designing a type of metal cooled reactor able to establish and maintain operation when fueled with depleted uranium. If successful, this reactor will offer at least a 30-fold increase in the uranium ore utilization versus that achieved in contemporary light water reactors without the need for fuel reprocessing and recycling.	Document	RCRD&D	FY2013
Investigation of Thermal Aging Effects on the Evolution of Microstructure and Mechanical Properties of Cast Duplex Stainless Steels	University of Maryland, College Park	$799,966	This research will provide a better understanding of the microstructural evolution and simultaneous change in mechanical response during aging. The results of the research will provide data that can be used to estimate degraded mechanical properties for an 80-year service life of light water reactors.	Document	RCRD&D	FY2013
Model validation using CFD-grade experimental database for NGNP Reactor Cavity Cooling Systems with water and air	University of Michigan	$799,348	Reasearchers will use advanced innovative instrumentation to build a high-resolution experimental database and to use the novel experimental data to assess and further develop the predictive capabilities of computer codes for thermal hydraulics and computational fluid dynamics. The improved models developed by this project will also have the direct benefit of improving the predictive capability of the passive systems of third generation light water reactors and small modular reactor systems.	Document	RCRD&D	FY2013
Long-Term Prediction of Emissivity of Structural Material for High Temperature Reactor Systems	University of Missouri	$799,117	Reasearchers will study specific types of emissivity driven cooling from a variety of materials that are relevant to nuclear reactors. The research will provide a basis for numerical modeling to support reactor development.	Document	RCRD&D	FY2013
Advanced I&C for Fault-Tolerant Supervisory Control of Small Modular Reactors	University of Pittsburgh	$800,000	The purpose of this research is to develop advanced instrumentation and control techniques for supervisory control of advanced small modular reactors. This research supports the operational goals of small modular reactor concepts through the development of improved oversight and surveillance techniques.	Document	RCRD&D	FY2013
Corrosion of Structural Materials for Advanced Supercritical Carbon-Dioxide Brayton Cycle	University of Wisconsin-Madison	$798,672	Reasearchers will study a variety of materials for corrosion resistance under conditions that improve power conversion. In addition to studying the corrosion resistance of the materials, researchers will study the effect of additives to mitigate corrosion. Development of corrosion theories and modeling aimed at prediction of long-term corrosion will be the underlying theme throughout the project.	Document	RCRD&D	FY2013
Component and Technology Development for Advanced Liquid Metal Reactors	University of Wisconsin-Madison	$798,920	In support of liquid metal cooled reactors, the University of Wisconsin, Madison will evaluate advanced alloys and ceramics that come in contact with liquid metals. Additionally, a robust oxygen sensor and for use in liquid metals will be developed in order to better evaluate corrosion profiles in support of diagnostic testing.	Document	RCRD&D	FY2013
A New Paradigm for Understanding Multi-phase Ceramic Waste Form Performance	Clemson University	$800,000	Researchers will use advanced characterization tools to develop 3-D microstructural data that can be incorporated into computer-based simulations in order to predict the performance of waste forms. Materials system modeling will incorporate elemental release and the interconnected microstructural network of phases to better understand performance and degradation, which will accelerate waste form acceptance in repository settings.	Document	FCR&D	FY2014
Controlling Hexavalent Americium: A Centerpiece to a Compact Nuclear Fuel Cycle	Colorado School of Mines	$800,000	Researchers will develop and exploit the fundamental chemistry of Americium to enable an industrially viable means to co-recover the major and minor actinide elements from used nuclear fuel. The results would be a significant step forward in the development of aqueous separations approaches designed to recover the U-Am actinides based on the availability of the hexavalent oxidation state.	Document	FCR&D	FY2014
Zeolite Membranes for Krypton/Xenon Separation from Spent Nuclear Fuel Reprocessing Off-Gas	Georgia Institute of Technology	$400,000	Researchers will develop a high-performance, lower-cost zeolitic membrane process for Kr/Xe separations during spent nuclear fuel processing. Current separation methods are not considered economical and a membrane process would have relatively lower cost, equipment size, and ambient operating temperature. The process would form a sound basis for further development of this transformative separation technology for the nuclear fuel cycle.	Document	FCR&D	FY2014
Optimizing Polymer-Grafted Amidoxime-based Adsorbents for Uranium Uptake from Seawater	Georgia Institute of Technology	$399,999	Researchers will work to increase the adsorbent capacity and selectivity toward uranium by optimizing the adsorbent morphology, synthesis variables, and conditioning parameters and by investigating the rate-limiting variables through transport and reaction modeling. A novel adsorption/partition concept that has the potential to substantially increase the adsorbent capacity will be tested, making uranium from seawater extraction more economically viable.	Document	FCR&D	FY2014
Extraction of Uranium from Seawater: Design and Testing of a Symbiotic System	Massachusetts Institute of Technology	$400,000	Researchers will develop a seawater uranium extraction system that will work symbiotically with an offshore windmill by utilizing the structure, mooring and power of the windmill, while increasing the energy harvested by the installation. Uranium will be extracted by an adsorbent polymer belt, which will be cycled through the seawater and an elution plant located at the base of the windmill tower. Increasing the frequency of harvesting could overcome current economic barriers to seawater uranium extraction.	Document	FCR&D	FY2014
Imaging a Dry Storage Cask with Cosmic Ray Muons	Oregon State University	$799,871	Researchers will develop an imaging system to monitor the content of a dry storage cask with cosmic ray muons. A very large amount of plutonium under nuclear safeguards is contained in used fuel assemblies stored in dry storage casks. Muon imaging will allow a cost effective and reliable way to evaluate dry storage cask content and integrity before transport.	Document	FCR&D	FY2014
Apatite and sodalite based glass-bonded waste forms for immobilization of 129I and mixed halide radioactive wastes	Rutgers University	$800,000	Researchers will develop advanced and chemically durable waste forms for immobilizing 129I (aqueous based reprocessing of fuel) and mixed-halide wastes (molten-salt processing of fuel) by low temperature synthesis. Halide-containing sodalite and calcium phosphate-based apatite minerals will be synthesized, consolidated and tested for chemical durability. The project will provide needed baseline data for the development of advanced waste forms for immobilization of iodine and mixed-halide wastes.	Document	FCR&D	FY2014
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$350,000	Researchers will develop modeling tools supported by experiments for off-gas capture from future nuclear-fuel recycling facilities. Target species include tritium, iodine, krypton, and xenon. The models are intended to provide path forward recommendations to develop off-gas treatment adsorption processes. The project will contribute to the evaluation of options for environmentally acceptable recycle systems.	Document	FCR&D	FY2014
Development of high performance ODS alloys	Texas A&M University	$800,000	Researchers will study swelling, radiation hardening and changes in mechanical properties of ODS alloys to develop two sets of advanced ODS alloys. Two sets of first-round candidate alloys that have already undergone extensive development and testing will evaluate irradiation performance. The study will meet the need for high strength, radiation-tolerant cladding and core components that have enhanced resistance to void swelling.	Document	FCR&D	FY2014
Rare Earth Electrochemical Property Measurements and Phase Diagram Development in a Complex Molten Salt Mixture for Molten Salt Recycle	The Ohio State University	$800,000	Researchers will investigate rare earth (RE) properties in complex molten salt mixtures. In a molten salt recycle approach, the RE drawdown by electrolysis is a key step in which REs are separated from salt containing other fission products. Investigation of RE electrolysis must consider the electrochemical properties of the REs. We propose to conduct studies of detailed experiments and corresponding models to provide the physical properties and phase diagrams required to predict the performance of RE drawdown for processing complex molten salts.	Document	FCR&D	FY2014
Studies of Lanthanide Transport in Metallic Nuclear Fuels	The Ohio State University	$800,000	Researchers will study the redistribution of lanthanides and migration of lanthanides to the fuel surface. The mechanisms of lanthanide transport in metallic fuel based on the novel discovery of a Ôliquid-likeÕ transport mechanism will be studied analytically and experimentally. The project will develop a fundamental understanding of lanthanide fission product migration and redistribution in advanced metallic nuclear fuels, and theory and data to mitigate fuel-cladding chemical interactions.	Document	FCR&D	FY2014
Computational and Experimental Studies of Microstructure-Scale Porosity in Metallic Fuels for Improved Gas Swelling Behavior	University of Arkansas	$796,823	Researchers will study the microstructure of metallic uranium alloy fuels, and their resistance to densification, to minimize in-pile irradiation swelling through bimodal pore size distribution. The project will develop a predictive approach to design metallic fuel microstructures for optimal swelling resistance and fission gas retention.	Document	FCR&D	FY2014
Improved Hybrid Modeling of Spent Fuel Storage Facilities	University of California, Berkeley	$645,393	Researchers will develop a variance reduction method for computational transport that will improve the ability to design and operate monitoring systems for interim used fuel installations through enhanced modeling and simulation. This new tool will demonstrate that modeling calculations can be done more accurately in less time than with current tools and will perform studies characterizing how changes in material, cask configurations, and number of casks could impact monitoring systems.	Document	FCR&D	FY2014
Selective ligands for uranyl via combinatorial peptoid libraries: A synthetic, structural, thermodynamic and computational study	University of California, Berkeley	$400,000	Researchers will study how donor ligands bind to the uranyl ion, UO22+, with the longer-term goal of using this information to tackle selective recognition of uranyl in aqueous solution. The study will impact underlying approaches to controlling the behavior of uranium in these systems. The actinide separation technology could be used in several areas including uranium extraction from seawater, nuclear waste remediation and nuclear materials.	Document	FCR&D	FY2014
Combining Experiments and Simulations of Extraction Kinetics and Thermodynamics in Advanced Separation Processes for Used Nuclear Fuel	University of California, Irvine	$799,938	Researchers will study how the kinetics and thermodynamics of metal ion extraction in advanced separation processes for used nuclear fuel can be described by molecular dynamic (MD) simulations and how the simulations can be validated by experimental data. The project would have broad impacts on several separations processes including advanced TALSPEAK, ALSEP and GANEX by increasing the confidence and accuracy of computer modeling of metal ion extraction._	Document	FCR&D	FY2014
Effect of Metallic Li on the Behavior of Metals in Molten Salts	University of Nevada, Reno	$458,250	Researchers will identify the effect of metallic lithium on materials that are used in molten salt recycling. The study will try to understand how the presence of Li(0) in molten salts affects the degradation of alloys. Studying these changes will help accurately predict container material behavior and longevity.	Document	FCR&D	FY2014
Assessment of Corrosion Resistance of Promising Accident Tolerant Fuel Cladding under Reactor Conditions	University of Notre Dame	$800,000	Researchers will assess the corrosion behavior of accident tolerant fuel candidate iron-based alloys under normal LWR operating conditions consisting of high temperature, relevant water chemistry and irradiation. The assessment will produce data about possible irradiation-accelerated corrosion rates of iron-based alloys, and the mechanisms by which such corrosion rates are accelerated. The project will advance the selection of appropriate replacements for Zircaloy cladding.	Document	FCR&D	FY2014
Functionalized Porous Organic Polymers as Uranium Nano-Traps for Efficient Recovery of Uranium from Seawaterr	University of South Florida	$399,000	Researchers will develop functionalized porous organic polymers, or Ônano-trapsÕ for extraction of uranium from seawater. This technique allows for increased surface area and custom-designed pore size and chemistry to fit specific parameters. The adsorbent materials have high efficiency and effectiveness for uranium recovery from seawater, providing a potential supply for nuclear fuel.	Document	FCR&D	FY2014
Enhanced Accident-Tolerant Fuel Performance and Reliability for Aggressive iPWR/SMR Operation	University of Tennessee	$799,967	To develop a process that evaluates operational and safety performance of reactor-and-fuel combinations by integrating whole-core 3D neutronics with MOOSE/BISON fuel performance assessments via explicit time and space dependent fuel rod operational power histories. The project will be valuable in analyzing and evaluating accident tolerant fuel concepts and furthering the understanding of reactor physics and fuel performance aspects of key accident tolerant fuel concepts.	Document	FCR&D	FY2014
Nuclear Technology R&D Strategies in an Era of Energy Price Uncertainty	University of Texas, Austin	$799,112	Researchers will identify nuclear technology options that are competitive over a wide range of plausible future business environments. No single nuclear technology or business practice will be the best choice across all or even most future conditions. The study will focus on hybrid nuclear-fossil technologies, energy storage and conversion, which will result in an identification of nuclear strategies that can succeed under future market conditions.	Document	FCR&D	FY2014
Development and Optimization of Voltammetric Methods for Real Time Analysis of Electrorefiner Salt with High Concentrations of Actinides and Fission Products	University of Utah	$621,612	Researchers will develop an advanced voltammetry method to pursue the objective of real time monitoring of actinide concentrations in electrorefiner salt. This will include experimental measurement of key parameters such as activity coefficients and exchange current density. It will also involve simulation of voltammetry processes based on first principles. The project will allow for real time measurements that could support the commercialization of pyroprocessing.	Document	FCR&D	FY2014
Development of Self-Healing Zirconium-Silicide Coatings for Improved Performance of Zirconium-Alloy Fuel Cladding	University of Wisconsin, Madison	$798,621	Researchers will study the deposition of self-healing zirconium-silicide coatings on zirconium-alloy fuel cladding material to improve corrosion resistance under normal and accident conditions. Under these conditions, Zr-Si coating evolves into a highly protective functionally-graded multilayered system. The study will lead to improved performance of zirconium-alloy fuels._	Document	FCR&D	FY2014
Thermal Conductivity in Metallic Fuels	Virginia Polytechnic Institute and State University	$799,837	Researchers will calculate the thermal conductivity of metallic uranium and neptunium alloys, including the effects of noble gasses, using density functional theory. The experiments will validate the calculated effective thermal conductivity using the MARMOT code and by helping determine DFT simulation parameters. The study works to improve fuel lifetime by understanding its thermal behavior.	Document	FCR&D	FY2014
SiC-ODS Alloy Gradient Nanocomposites as Novel Cladding Materials	Virginia Polytechnic Institute and State University	$799,998	Researchers will combine nuclear nanomaterial design, processing, testing, and characterization efforts to develop revolutionary materials that can withstand neutron irradiation for long period of time using nanostructured SiC and oxide dispersion strengthened steel. The ultimate objective is to offer new cladding materials with increased corrosion resistance, strength, and creep resistance in both steady state and accident conditions.	Document	FCR&D	FY2014
Experimental Breeder Reactor II Benchmark Evaluation	Idaho State University	$400,000	Researchers will develop a benchmark evaluation of the Experimental Breeder Reactor II (EBR-II). During nearly 30 years of operation numerous experiments were conducted at EBR-II. The most significant of these experiments were conducted in 1986 demonstrating inherent safety features in loss of flow without reactor scram and loss of heat sink without reactor scram. Benchmark evaluation will be valuable for the reactor design efforts in the United States and South Korea.	Document	MSNE	FY2014
Integral full core multi-physics PWR benchmark with measured data	Massachusetts Institute of Technology	$400,000	Researchers will introduce BEAVRS, a new multi-cycle full-core Pressurized Water Reactor (PWR) depletion benchmark based on two operational cycles of a commercial nuclear power plant. This project aims at addressing the uncertainty quantification of the measured data and on making this benchmark a true non-proprietary international benchmark for the validation of high-fidelity multi-physics computational tools.	Document	MSNE	FY2014
Benchmark Evaluation of PROTEUS Gas-Cooled Reactor Experiments	University of Florida	$400,000	Researchers will create International Reactor Physics Experiment Evaluation Project (IRPhEP) benchmarks using data from 1970s experiments of the neutronics of gas-cooled fast reactor (GCFR) designs investigated in the PROTEUS reactor. The GCFR-PROTEUS experiments fill a gap in current integral benchmark data. These experiments can provide validation of computational models and nuclear data for next generation reactors.	Document	MSNE	FY2014
An Investigation To Establish Multiphysical Property Dataset Of Nuclear Materials Based On In-Situ Observations And Measurements	Purdue University	$800,000	Researchers will create an in-situ measurement based experimental approach to develop experimental validation dataset for NEAMS based code validation. Particular emphasis is on supplying data set for multiphysics simulations in extreme conditions as a function of material microstructure.	Document	NEAMS	FY2014
Experimental Validation of UO2 Microstructural Evolutions for NEAMS tool MARMOT	University of Florida	$798,000	Researchers will experimentally validate MARMOT for predicting the microstructural evolutions of UO2 oxide fuel under the driving forces of high temperatures and large temperature gradient in reactors. By performing the experiments and simulations simultaneously using precisely defined initial conditions, the experiment data will provide direct benchmarking of the MARMOT code.	Document	NEAMS	FY2014
High-resolution time-resolved experiments on mixing and entrainment of buoyant jets in stratified environments	University of Michigan	$799,983	Researchers will study high spatial and time-resolution experimental data of the fluid dynamics phenomena of flow jets interacting with a stratified layer. The issue plays an important role in the safety of several reactor designs, including sodium-cooled reactors. The data addresses the NEAMS needs for the validation of high fidelity computational fluid dynamics methodologies.	Document	NEAMS	FY2014
Fundamental study of key issues related to advanced S-CO2 Brayton Cycle: prototypic HX development and Cavitation	Georgia Institute of Technology	$799,000	Researchers will study scientific and operational issues pertinent to compact heat exchanger systems and turbo-machinery. The project will work to resolve issues with the fabrication of diffusion bonded compact heat exchangers, alternate heat exchange technology for recuperators, and resolution of issues with cavitation and fluid instabilities.	Document	RCRD&D	FY2014
Advanced Models for Nondestructive Evaluation of Aging Nuclear Power Plant Cables	Iowa State University	$787,291	Researchers will develop advanced models that relate environmentally induced microstructural and chemical changes in cable insulation polymers to their macroscopic electrical parameters. These parameters will be measured and modeled over a wide range of the electromagnetic spectrum, covering several potential nondestructive evaluation techniques, enabling identification of the most sensitive techniques for future development.	Document	RCRD&D	FY2014
Development of Novel Functionally Graded Transition Joints for Improving the Creep Strength of Dissimilar Metal Welds in Nuclear Applications	Lehigh University	$800,000	Researchers will develop graded transition joints and improved creep life models for increasing the life of dissimilar metal welds (DMWs) in nuclear reactors. The research represents the first application of functionally graded material concepts for solving the problem of DMW failures through an integrated approach of additive manufacturing, modeling, microstructural characterization, and advanced strain-sensing techniques.	Document	RCRD&D	FY2014
Feasibility Assessment of a Micro Modular Reactor (MMR)	North Carolina State University	$400,000	Researchers will develop an innovative compact reactor concept that integrates power production, power conversion and electricity generation in a single unit: the Micro Modular Reactor (MMR). It is designed to be absolutely melt-down proof (MDP) under all circumstances including complete loss of coolant scenarios with no possible release of radioactive material, to have a cycle length of greater than 10 years, and to be highly proliferation resistant.	Document	RCRD&D	FY2014
Scaling Studies for Advanced Gas Reactor Concepts	Oregon State University	$681,834	Researchers will expand the utilization of the Oregon State University High Temperature Test Facility (HTTF) to validate a broader range of advanced high temperature reactors and events. The facility will be revised to add a detailed scaling analysis of additional gas reactor concepts including advanced gas-cooled, molten salt, and sodium cooled reactors.	Document	RCRD&D	FY2014
Fluid Stratification Separate Effects Analysis, Testing and Benchmarking	Oregon State University	$800,000	Researchers will study fluid stratification in high temperature gas reactors. Coolant stratification is the result of incomplete mixing of one or more fluids, leading to a density gradient, which may or may not dissipate under diffusive or convective effects. This combined analytical and experimental project seeks to investigate stratification driven by diffusive and convective mechanisms and is expected to yield insight into this phenomenon.	Document	RCRD&D	FY2014
Probabilistic Economic Valuation of Safety Margin Management Analysis	Oregon State University	$795,364	Researchers will use RAVEN and develop a companion software package to facilitate economic analysis of safety margins. The project is a proof of concept that will use techniques to examine the cost of improving safety margins vs. the risk of accidents from not improving safety margins. This analysis can be used to evaluate the economic viability of various plant upgrades.	Document	RCRD&D	FY2014
Novel Dissimilar Joints Between Alloy 800H and 2.25%Cr and 1%Mo Steel	Pennsylvania State University	$800,000	Researchers will fabricate and test dissimilar metal joints between a nickel base alloy and a steel with gradual variations of chemical composition, microstructure and properties in a manner that reduces abrupt thermal expansion mismatch and the resulting residual stresses. Data on structure and properties will serve as valuable inputs for the initiation of an ASME code case.	Document	RCRD&D	FY2014
Multi-Phase Model Development to Assess RCIC System Capabilities under Severe Accident Conditions	Texas A&M University	$564,246	Researchers will develop physics-based models of the Reactor Core Isolation Cooling (RCIC) System and incorporating them into a multi-phase code for validation. The project will tackle the current major challenges in RCIC System analysis and enable evaluation of two-phase thermodynamic aspects.	Document	RCRD&D	FY2014
Experimental Investigation and CFD Analysis of Steam Ingress Accidents in HTGRs	The Ohio State University	$800,000	Researchers will study the steam ingress scenario for HTGRs. The study will investigate thermal-hydraulic behavior and graphite oxidation of stream ingress phenomena to validate predictive CFD models. This work will resolve concerns about possible steam generator tube ruptures in a HTGR He-Steam Rankine cycle.	Document	RCRD&D	FY2014
Coiled Tube Gas Heaters For Nuclear Gas-Brayton Power Conversion	University of California, Berkeley	$800,000	Researchers will develop heat exchangers for Brayton-cycle power conversion in reactors using sodium, NaK, or salt as intermediate coolants. The proposed coiled tube gas heaters (CTGHs) are expected to have excellent power density, thermal shock/creep, in-service inspection, and reparability characteristics.	Document	RCRD&D	FY2014
Fundamental Studies of Irradiation-Induced Modifications in Microstructural Evolution and Mechanical Properties of Advanced Alloys	University of Illinois, Urbana-Champaign	$800,000	Researchers will develop and test a mechanism for predicting neutron irradiation performance for optimized Grade 92 and Alloy 709 for applications in advanced reactor systems. The work will employ ion irradiations and available information from neutron irradiations of related alloys to develop a basis for predicting the neutron irradiation performance of the optimized alloys.	Document	RCRD&D	FY2014
Integrated Computational and Experimental Study of Radiation Damage Effects in Grade 92 Steel and Alloy 709	University of Tennessee	$800,000	Researchers will develop a mechanistic understanding and predictive models of irradiation-induced microstructural evolution and resulting mechanical properties in optimized ferritic-martensitic Grade 92 steel and austenitic alloy 709 using multiscale simulations coupled with rigorous experimental validation. The project will provide insights into the correlation between ion irradiation and fast neutron damage.	Document	RCRD&D	FY2014
Meta-Level Design Guidance and Operator Performance Measures for Hybrid Control Rooms	Vanderbilt University	$799,869	Researchers will apply human factors engineering methods and relevant expertise from non-nuclear high-risk high-consequence domains toward the measurement of operator performance in analog, digital, and hybrid main control rooms. Performance measures will be developed for evaluating the situation awareness and decision-making proficiencies to support the transition to digital or hybrid control room displays.	Document	RCRD&D	FY2014

FY 2023 Research and Development Awards

DOE is awarding more than $41.2 million through NEUP to support 43 university-led nuclear energy research and development projects in 22 states. NEUP seeks to maintain U.S. leadership in nuclear research across the country by providing top science and engineering faculty and their students with opportunities to develop innovative technologies and solutions for civil nuclear capabilities.

A complete list of R&D projects with their associated abstracts is available below.

Title	Institution	Estimated Funding*	Project Description	Abstract	Project Type	Fiscal Year
Neutron Damage and MAX Phase Ternary Compounds	Drexel University			Document	IIR	FY2009
Atomistic Calculations of the Effect of Minor Actinides on Thermodynamic and Kinetic Properties of UO2+x	Georgia Institute of Technology			Document	IIR	FY2009
Maximum Fuel Utilization in Fast Reactors without Chemical Reprocessing	University of California, Berkeley			Document	IIR	FY2009
Developing a High Thermal Conductivity Fuel with Silicon Carbide Additives	University of Florida			Document	IIR	FY2009
Fabrication of Tungsten-Rhenium Cladding Materials via Spark Plasma Sintering for Ultra High Temperature Reactor Applications	University of Idaho			Document	IIR	FY2009
Ionic Liquid and Supercritical Fluid Hyphenated Techniques for Dissolution and Separation of Lanthanides, Actinides, and Fission Products	University of Idaho			Document	IIR	FY2009
Improved Fission Neutron Data Base for Active Interrogation of Actinides	University of Michigan			Document	IIR	FY2009
Utilization of Methacrylates and Polymer Matrices for the Synthesis of Ion Specific Resins	University of Nevada, Las Vegas			Document	IIR	FY2009
Improved LWR Cladding Performance by EPD Surface Modification Technique	University of Wisconsin, Madison			Document	IIR	FY2009
Advanced Models of LWR Pressure Vessel Embrittlement for Low Flux-High Fluence Conditions	University of California, Santa Barbara			Document	LWRS	FY2009
Irradiation Creep in Graphite	Boise State University			Document	NGNP	FY2009
Modeling the Stress Strain Relationships and Predicting Failure Probabilities For Graphite Core Components	Cleveland State University			Document	NGNP	FY2009
TRISO-Coated Fuel Durability Under Extreme Conditions	Colorado School of Mines			Document	NGNP	FY2009
An Innovative and Advanced Coupled Neutron Transport and Thermal Hydraulic Method (Tool) for the Design, Analysis and Optimization of VHTR/NGNP Prismatic Reactors	Georgia Institute of Technology			Document	NGNP	FY2009
Removal of 14C from Irradiated Graphite for Graphite Recycle and Waste Volume Reduction	Idaho State University			Document	NGNP	FY2009
Millimeter-Wave Thermal Analysis Development and Application to Gen IV Reactor Materials	Massachusetts Institute of Technology			Document	NGNP	FY2009
Accurate Development of Thermal Neutron Scattering Cross Section Libraries	North Carolina State University			Document	NGNP	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
Understanding Creep Mechanisms in Graphite with Experiments, Multiscale Simulations, and Modeling	North Carolina State University			Document	NGNP	FY2009
Simulations of the Thermodynamic and Diffusion Properties of Actinide Oxide Fuel Materials	University of Michigan			Document	AFCI	FY2009
Verification & Validation of High-Order Short-Characteristics-Based Deterministic Transport Methodology on Unstructured Grids	North Carolina State University			Document	NGNP	FY2009
Adsorptive Separation and Sequestration of Krypton, I and C14 on Diamond Nanoparticles	University of Missouri, Columbia			Document	AFCI	FY2009
Microscale Heat Conduction Models and Doppler Feedback	North Carolina State University			Document	NGNP	FY2009
Fundamental Understanding of Ambient and High-Temperature Plasticity Phenomena in Structural Materials in Advanced Reactors	Georgia Institute of Technology			Document	AFCI	FY2009
Development of Alternative Technetium Waste Forms	University of Nevada, Las Vegas			Document	AFCI	FY2009
Optimizing Neutron Thermal Scattering Effects in Very High Temperature Reactors	North Carolina State University			Document	NGNP	FY2009
Advanced Elastic/Inelastic Nuclear Data Development Project	Idaho State University			Document	AFCI	FY2009
Heterogeneous Recycling in Fast Reactors	Massachusetts Institute of Technology			Document	AFCI	FY2009
Quantification of UV-Visible and Laser Spectroscopic Techniques for Materials Accountability and Process Control	University of Nevada, Las Vegas			Document	AFCI	FY2009
Multiaxial Creep-Fatigue and CreepRatcheting Failures of Grade 91 and Haynes 230 Alloys Toward Addressing Design Issues of Gen IV Nuclear Power Plants	North Carolina State University			Document	NGNP	FY2009
Thermodynamic Development of Corrosion Rate Modeling in Iron Phosphate Glasses	Missouri University of Science and Technology			Document	AFCI	FY2009
Development of Subspace-Based Hybrid Monte Carlo-Deterministic Algorithms for Reactor Physics Calculations	North Carolina State University			Document	AFCI	FY2009
High-Fidelity Space-Time Adaptive Multiphysics Simulations in Nuclear Engineering	University of Nevada, Reno			Document	AFCI	FY2009
Improvements to Nuclear Data and Its Uncertainties by Theoretical Modeling	Rensselaer Polytechnic Institute			Document	AFCI	FY2009
Investigation of Countercurrent Helium-air Flows in Air-ingress Accidents for VHTRs	Ohio State University			Document	NGNP	FY2009
Sharp Interface Tracking in Rotating Microflows of Solvent Extraction	State University of New York at Stony Brook			Document	AFCI	FY2009
Bulk Nanostructured FCC Steels with Enhanced Radiation Tolerance	Texas A&M University			Document	AFCI	FY2009
Simulations of Failure via Three-Dimensional Cracking in Fuel Cladding for Advanced Nuclear Fuels	University of Texas, Dallas			Document	AFCI	FY2009
Testing of Performance of Optical Fibers Under Irradiation in Intense Radiation Fields, When Subjected to Very High Temperatures	Ohio State University			Document	NGNP	FY2009
Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels	Texas A&M University			Document	AFCI	FY2009
SiC Schottky Diode Detectors for Measurement of Actinide Concentrations from Alpha Activities in Molten Salt Electrolyte	The Ohio State University			Document	AFCI	FY2009
Computational Design of Advanced Nuclear Fuels	University of California, Davis			Document	AFCI	FY2009
Advanced Mesh-Enabled Monte Carlo Capability for Multi-Physics Reactor Analysis	University of Wisconsin, Madison			Document	AFCI	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
A Distributed Fiber Optic Sensor Network for Online 3-D Temperature and Neutron Fluence Mapping in a VHTR Environment	Texas A&M University			Document	NGNP	FY2009
Ab Initio Enhanced Calphad Modeling of Actinide Rich Nuclear Fuels	University of Wisconsin, Madison			Document	AFCI	FY2009
Investigation on the Core Bypass Flow in a Very High Temperature Reactor	Texas A&M University			Document	NGNP	FY2009
Development of Diffusion Barrier Coatings and Deposition Technologies for Mitigating Fuel Cladding Chemical Interactions (FCCI)	University of Wisconsin, Madison			Document	AFCI	FY2009
CFD Model Development and Validation for High Temperature Gas Cooled Reactor Cavity Cooling System (RCCS) Applications	Texas A&M University			Document	NGNP	FY2009
Thermal Properties of LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin, Madison			Document	AFCI	FY2009
Study of Air ingress across the duct during the accident conditions	Texas A&M University			Document	NGNP	FY2009
Verification of the CENTRM Module for Adaptation of the SCALE Code to NGNP Prismatic and PBR Core Designs	University of Arizona			Document	NGNP	FY2009
Integral and Separate Effects Tests for Thermal Hydraulics Code Validation for Liquid-Salt Cooled Nuclear Reactors	University of California, Berkeley			Document	NGNP	FY2009
Mechanisms Governing the Creep Behavior of High Temperature Alloys for Generation IV Nuclear Energy Systems	University of Cincinnati			Document	NGNP	FY2009
ALD Produced B2O3, Al2O3 and TiO2 Coatings on Gd2O3 Burnable Poison Nanoparticles	University of Colorado, Boulder			Document	NGNP	FY2009
Experimental Study and Computational Simulations of Key Pebble Bed Thermomechanics Issues for Design and Safety	University of Idaho			Document	NGNP	FY2009
Prediction and Monitoring Systems of Creep-Fracture Behavior of 9Cr-1Mo Steels for Reactor Pressure Vessels	University of Idaho			Document	NGNP	FY2009
Understanding Fundamental Material Degradation Processes in High Temperature Aggressive Chemomechanical Environments	University of Illinois, Urbana-Champaign			Document	NGNP	FY2009
Multi-Scale Multi-physics Methods Development for the Calculation of Hot-Spots in the NGNP	University of Michigan			Document	NGNP	FY2009
Corrosion and Creep of Candidate Alloys in High Temperature Helium and Steam Environments for the NGNP	University of Michigan			Document	NGNP	FY2009
Creation of a Full-Core HTR Benchmark with the Fort St. Vrain Initial Core and Validation of the DHF Method with Helios for NGNP Configurations	University of Michigan			Document	NGNP	FY2009
Fission Product Sorptivity in Graphite	University of Missouri, Columbia			Document	NGNP	FY2009
Identifying and Understanding Environment-Induced Crack Propagation Behavior in Ni-Based Superalloy INCONEL 617	University of Nevada, Las Vegas			Document	NGNP	FY2009
Graphite Oxidation Simulation in HTR Accident Conditions	University of New Mexico			Document	NGNP	FY2009
Non Destructive Thermal Analysis and In Situ Investigation of Creep Mechanism of Graphite and Ceramic Composites using Phase-sensitive THz Imaging & Nonlinear Resonant Ultrasonic Spectroscopy	University of Rochester			Document	NGNP	FY2009
Tritium Sequestration in Gen IV NGNP Gas Stream via Proton Conducting Ceramic Pumps	University of South Carolina			Document	NGNP	FY2009
Materials, Turbomachinery and Heat Exchangers for Supercritical CO2 Systems	University of Wisconsin, Madison			Document	NGNP	FY2009
Experimental Studies of NGNP Reactor Cavity Cooling System with Water	University of Wisconsin, Madison			Document	NGNP	FY2009
Assessment of Embrittlement of VHTR Structural Alloys in Impure Helium Environments	University of Wisconsin, Madison			Document	NGNP	FY2009
Modeling Fission Product Sorption in Graphite Structures	University of Wisconsin, Madison			Document	NGNP	FY2009
Liquid Salt Heat Exchanger Technology for VHTR Based Applications	University of Wisconsin, Madison			Document	NGNP	FY2009
Effect of Post-Weld Heat Treatment on Creep Rupture Properties of Grade 91 Steel Heavy Section Welds	Utah State University			Document	NGNP	FY2009
Alpha Radiolysis of Nuclear Solvent Extraction Ligands used for An(III) and Ln(III) Separations	California State University, Long Beach	$1,390,252		Document	FCR&D	FY2010
Predictive Maturity of Multi-Scale Simulation Models for Fuel Performance	Clemson University	$614,690		Document	FCR&D	FY2010
Freeze-casting as a Novel Manufacturing Process for Fast Reactor Fuels	Drexel University	$1,149,327		Document	FCR&D	FY2010
Fuel Performance Experiments on the Atomistic Level, Studying Fuel Through Engineered Single Crystal UO2	Idaho State University	$650,000		Document	FCR&D	FY2010
Development of A Self Biased High Efficiency Solid-State Neutron Detector for MPACT Applications	Rensselaer Polytechnic Institute	$810,141		Document	FCR&D	FY2010
Development of a Innovative High Thermal Conductivity UO 2 Ceramic Composites Fuel Pellets with Carbon Nano-Tubes Using Spark Plasma Sintering	University of Florida	$894,042		Document	FCR&D	FY2010
Exploration and Modeling of Structural Changes in Waste Glass under Corrosion	Pennsylvania State University	$1,377,444		Document	FCR&D	FY2010
Evaluation of materials for interim storage of spent fuel for more than 100 years	University of Michigan	$931,603		Document	FCR&D	FY2010
Implementation of On-the-Fly Doppler Broadening in MCNP5 for Multiphysics Simulation of Nuclear Reactors	University of Michigan	$406,712		Document	FCR&D	FY2010
Methods and tools to allow molecular flow simulations to be coupled to higher level continuum descriptions of flows in porous/fractured media and aerosol/dust dynamics	University of Missouri-Columbi	$541,286		Document	FCR&D	FY2010
Characterization and Modeling of Materials for Kr-Xe Separations	University of Nevada-Las Vegas	$989,800		Document	FCR&D	FY2010
Modeling Solute Thermokinetics in LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin-Madison	$616,073		Document	FCR&D	FY2010
Advanced Aqueous Separation Systems for Actinide Partitioning: Develop Fundamental Understanding of An(III)/Ln(III) Separation	Washington State University	$1,451,784		Document	FCR&D	FY2010
Consistent Multigroup Theory Enabling Accurate Coarse-Group Simulation of GenIV Reactors	Georgia Institute of Technology	$1,046,277		Document	GEN IV	FY2010
Studies of Deteriorated Heat Transfer in Prismatic Cores Stemming from Irradiation-Induced Geometry Distortion	Idaho State University	$1,287,921		Document	GEN IV	FY2010
Carbide Coatings for Nickel Alloys, Graphite, and Carbon/Carbon Composites to be Used in Fluoride Salt Valves	Johns Hopkins University	$1,183,239		Document	GEN IV	FY2010
Design, Testing, and Modeling of the Direct Reactor Auxiliary Cooling System for AHTRs	Ohio State University	$1,366,627		Document	GEN IV	FY2010
Monitoring microstructural evolution of Alloy 617 with nonlinear acoustics for remaining useful life prediction; multiaxial creep-fatigue and creep-ratcheting	Pennsylvania State University	$1,000,000		Document	GEN IV	FY2010
Development and Validation of Multidimensional Models of Supercritical CO 2 Energy Conversion Systems for Nuclear Power Reactors	Rensselaer Polytechnic Institute	$475,005		Document	GEN IV	FY2010
Multiscale Concrete Modeling for Aging Degradation	Mississippi State University	$345,941		Document	LWRS	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term and Elevated Temperature Irradiation: Modeling and Experimental Investigation	University of California-Berkeley	$1,320,667		Document	GEN IV	FY2010
Development of an advanced computational fluid dynamics technology for the next-generation nuclear reactor system analysis and safety margin characterization code	North Carolina State University	$418,199		Document	LWRS	FY2010
Development of Barrier Layers for the Protection of Candidate Alloys in the VHTR	University of California-Santa Barbara	$995,232		Document	GEN IV	FY2010
Precursor Derived Nanostructured Si-C-X Materials for Nuclear Applications	University of Washington	$899,518		Document	MRIIR	FY2010
Investigation of a Novel NDE Method for Monitoring Thermo-Mechanical Damage and Microstructure Evolution in Ferritic-Martensitic Steels for Generation IV Nuclear Energy Systems	University of Cincinnati	$833,109		Document	GEN IV	FY2010
Development and Testing of an Open-Loop Oscillator for Small Reactivity Worth Samples	Idaho State University	$597,252		Document	MRIIR	FY2010
Fission Product Transport in TRISO Particle Layers under Operating and Off-Normal Conditions	University of Michigan	$966,581		Document	GEN IV	FY2010
Understanding the Irradiation Behavior of Zirconium Carbide	Pennsylvania State University	$870,613		Document	MRIIR	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term Irradiation at Elevated Temperature: Critical Experiments	University of Michigan	$1,181,379		Document	GEN IV	FY2010
Modeling investigation of the stability and irradiation-induced evolution of nanoscale precipitates in advanced structural materials	University of Tennessee-Knoxville	$380,653		Document	MRIIR	FY2010
Three-dimensional NDE of VHTR Core Components via Simulation-based Testing	University of Minnesota	$1,366,163		Document	GEN IV	FY2010
Investigation of Laser Shock Peening for Enhancing Fatigue and Stress Corrosion Cracking Resistance of Nuclear Energy Materials	University of Cincinnati	$1,242,019		Document	MRIIR	FY2010
Failure Predictions for VHTR Core Components using a Probabilistic Continuum Damage Mechanics Model	University of Minnesota	$854,542		Document	GEN IV	FY2010
Irradiation Accelerated Corrosion of Reactor Core Materials	University of Michigan	$798,943		Document	MRIIR	FY2010
Development of a Scanning Microscale Fast Neutron Irradiation Platform for Examining the Correlation Between Local Neutron Damage and Graphite Microstructure	University of Missouri-Columbia	$703,064		Document	GEN IV	FY2010
Study of Interfacial Interactions using Thin Film Surface Modification: Radiation and Oxidation Effects in Materials	University of Wisconsin-Madison	$538,032		Document	MRIIR	FY2010
Development of Thermal Transient Flow Rate Sensors for High Temperature, Irradiation, Corrosive Environment	University of Nevada-Las Vegas	$451,269		Document	GEN IV	FY2010
Novel Engineered Refractory Materials for Advanced Reactor Applications	North Carolina State University	$1,129,304		Document	MRIIR	FY2010
Novel Methods of Tritium Sequestration: High Temperature Gettering and Separation Membrane Materials Discovery for Nuclear Energy Systems	University of South Carolina	$1,366,626		Document	GEN IV	FY2010
Heat Transfer Salts for Nuclear Reactor Systems - Chemistry Control, Corrosion Mitigation, and Modeling	University of Wisconsin-Madison	$1,352,040		Document	GEN IV	FY2010
Pulsed Magnetic Welding for Advanced Core and Cladding Steels	University of Wisconsin-Madison	$525,206		Document	GEN IV	FY2010
Corrosion in Supercritical Carbon Dioxide: Materials, Environmental Purity, Surface Treatments, and Flow Issues	University of Wisconsin-Madison	$651,447		Document	GEN IV	FY2010
Quantification of Cation Sorption to Engineered Barrier Materials Under Extreme Conditions	Clemson University	$1,171,380		Document	FCR&D	FY2011
In-Pile Instrumentation Multi-Parameter System Utilizing Photonic Fibers and Nanovision	Idaho State University	$1,199,990		Document	FCR&D	FY2011
Development of Plasmonically Cloaked Nanoparticles	Idaho State University	$800,000		Document	FCR&D	FY2011
Fission Product Transmutation in Mixed Radiation Fields	Idaho State University	$800,000		Document	FCR&D	FY2011
Life Prediction of Spent Fuel Storage Canister Material	Massachusetts Institute of Technology	$899,826		Document	FCR&D	FY2011
Active Interrogation using Photofission Technique for Nuclear Materials Control and Accountability	Oregon State University	$900,000		Document	FCR&D	FY2011
Anisotropic Azimuthal Power and Temperature Distribution on Fuel Rod: Impact of Hydride Distribution	Pennsylvania State University	$631,956		Document	FCR&D	FY2011
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$1,000,000		Document	FCR&D	FY2011
Recovery of Uranium from Seawater: Preparation and Development of Polymer-Supported Extractants	City College of New York, Hunter	$363,716		Document	MSTR	FY2011
Microemulsions and Aggregation Formation in Extraction Processes for Used Nuclear Fuel: Thermodynamics and Structural Studies	University of California, Irvine	$1,000,000		Document	FCR&D	FY2011
One-Dimensional Nanostructures for Neutron Detection	North Carolina State University	$455,629		Document	MSTR	FY2011
Optimized Processing Fabrication Paths for Larger Heats of Nanostructured Ferritic Alloys	University of California, Santa Barbara	$1,000,000		Document	FCR&D	FY2011
Feasibility and Safety Assessment for Advanced Reactor Concepts Using Vented Fuel	Oregon State University	$600,000		Document	MSTR	FY2011
Basic Physics Data: Measurement of Neutron Multiplicity from Induced Fission	University of Michigan	$973,364		Document	FCR&D	FY2011
Development of an Efficient Meso-Scale Multi-Phase Flow Solver in Nuclear Applications	City College of New York	$505,858		Document	NEAMS	FY2011
High Temperature Transducers for Online Monitoring of Microstructure Evolution	Pennsylvania State University	$455,628		Document	MSTR	FY2011
Radionuclide Incorporation and Long Term Performance of Apatite Waste Forms	University of Michigan	$862,500		Document	FCR&D	FY2011
Multiscale Modeling and Uncertainty Quantification for Nuclear Fuel Performance	Colorado State University	$1,098,250		Document	NEAMS	FY2011
Laser-Arc Hybrid Welding of Thick Section Ni-base Alloys- Advanced Modeling and Experiments	Pennsylvania State University	$536,117		Document	MSTR	FY2011
Actinide Foil Production for MPACT Research	University of Nevada-Las Vegas	$156,897		Document	FCR&D	FY2011
Fundamental Studies of the Role of Grain Boundaries on Uniform Corrosion of Advanced Nuclear Reactor Materials	Drexel University	$1,098,250		Document	NEAMS	FY2011
Correlates of Sensitive Technologies	Texas A&M University	$509,467		Document	MSTR	FY2011
Enriched Boron-Doped Amorphous Selenium Based Position-Sensitive Solid-State Thermal Neutron Detector for MPACT Applications	University of South Carolina	$1,000,000		Document	FCR&D	FY2011
Phenomena-based Uncertainty Quantification in Predictive Coupled-Physics Reactor Simulations	Texas A&M University	$1,098,250		Document	NEAMS	FY2011
Improved Safety Margin Characterization of Risk from Loss of Offsite Power	Texas A&M University	$600,000		Document	MSTR	FY2011
Development of Advanced High Uranium Density Fuels for Light Water Reactors	University of Wisconsin-Madison	$1,000,000		Document	FCR&D	FY2011
Characterization of Modeling of Grain Boundary Chemistry Evolution in Ferritic Steels Under Irradiation	University of Michigan	$1,098,250		Document	NEAMS	FY2011
Diffusion, Thermal Properties and chemical Compatibilities of Select MAX Phases with Materials for Advanced Nuclear Systems	Drexel University	$535,927		Document	NEET	FY2011
A High Temperature-Tolerant and Radiation-Resistant In-Core Neutron Sensor for Advanced Reactors	The Ohio State University	$455,629		Document	MSTR	FY2011
Developing the User Experience for a Next Generation Nuclear Fuel Cycle Simulator	University of Wisconsin-Madison	$1,200,000		Document	FCR&D	FY2011
Development of Multiscale Materials Modeling Techniques and Coarse-Graining Strategies for Predicting Materials Degradation in Extreme Irradiation Environments	University of Tennessee, Knoxville	$750,000		Document	NEAMS	FY2011
A New Light Weight Structural Material for Nuclear Structures	North Carolina State University	$399,490		Document	NEET	FY2011
Pathway Aggregation in the Risk Assessment of Proliferation Resistance and Physical Protection (PR&PP) of Nuclear Energy Systems	The Ohio State University	$534,471		Document	MSTR	FY2011
Experimental Investigation of Convection and Heat Transfer in the Reactor Core for a VHTR	City College of New York	$1,118,856		Document	RCRD&D	FY2011
Preparation of High Purity, High Molecular-Weight Chitin from Ionic Liquids for Use as an Adsorbate for the Extraction of Uranium from Seawater	University of Alabama	$338,260		Document	MSTR	FY2011
Graphite Microstructural Characterization Using Time-Domain and Correlation-Based Ultrasonics	Johns Hopkins University	$1,199,997		Document	RCRD&D	FY2011
Selectivity in Ligand Binding to Uranyl Compounds: A Synthetic, Structural, Thermodynamic and Computational Study	University of California-Berkeley	$500,000		Document	MSTR	FY2011
Methodology Development for Passive Component Reliability Modeling in a Multi-Physics Simulation Environment	The Ohio State University	$533,457		Document	RCRD&D	FY2011
Development of Seismic Isolation Systems Using Periodic Materials	University of Houston	$538,154		Document	MSTR	FY2011
Pebble Fuel Handling and Reactivity Control for Salt-Cooled High Temperature Reactors	University of California, Berkeley	$612,721		Document	RCRD&D	FY2011
Innovative Elution Processes for Recovering Uranium from Seawater	University of Idaho	$400,000		Document	MSTR	FY2011
Self-Sustaining Thorium Boiling Water Reactors	University of California, Berkeley	$1,145,932		Document	RCRD&D	FY2011
Development of Austenitic ODS Strengthened Alloys for Very High Temperature Applications	University of Illinois-Urbana Champaign	$538,154		Document	MSTR	FY2011
High Fluency Low Flux Embrittlement Models of LWR Reactor Pressure Vessel Embrittlement and a Supporting Database from the UCSB ATR-2 Irradiation Experiment	University of California, Santa Barbara	$1,199,607		Document	RCRD&D	FY2011
Enhancement of the Extraction of the Uranium from Seawater	University of Maryland	$400,000		Document	MSTR	FY2011
A Research Program for Fission Product/Dust Transport in HTGR's	University of Missouri-Columbia	$1,157,367		Document	RCRD&D	FY2011
Transient Safety Analysis of Fast Spectrum TRU Burning LWR with Internal Blankets	University of Michigan	$599,475		Document	MSTR	FY2011
Development and Validation of a Lifecycle-based Prognostics Architecture with Test Bed Validation	University of Tennessee, Knoxville	$846,315		Document	RCRD&D	FY2011
Development of Novel Sorbents for Uranium Extraction from Seawater	University of North Carolina, Chapel Hill	$400,000		Document	MSTR	FY2011
In-situ Condition Monitoring of Components in Small Modular Reactors Using Process and Electrical Signature Analysis	University of Tennessee, Knoxville	$650,000		Document	RCRD&D	FY2011
Radiation Behavior of High-Entropy Alloys for Advanced Reactors	University of Tennessee, Knoxville	$538,159		Document	MSTR	FY2011
Technical Development for S-CO2 Advanced Energy Conversion	University of Wisconsin	$815,000		Document	RCRD&D	FY2011
Rapid Computer Aided Ligand Design and Screening of Precious Metal Extractants from TRUEX Raffinate with Experimental Validation	Washington State University	$500,000		Document	MSTR	FY2011
Ag Transport Through Non-Irradiated and Irradiated SiC	University of Wisconsin-Madison	$1,055,456		Document	RCRD&D	FY2011
Critical Heat Flux Phenomena at High Pressure and Low Mass Fluxes: Tests and Models	University of Wisconsin-Madison	$1,199,781		Document	RCRD&D	FY2011
Modeling and Test Validation of a Reactor Cavity Cooling System with Air	University of Wisconsin-Madison	$1,199,988		Document	RCRD&D	FY2011
Transient Mixed Convection Validation for NGNP	Utah State University	$635,860		Document	RCRD&D	FY2011
Alternative High-Performance Ceramic Waste Forms	Alfred University	$840,000	This project aims to advance fundamental understanding of the kinetics of structural evolution of crystalline ceramic waste forms. The structure/property relationships will be identified and will reveal new formulations, improved processing routes, and strategies for improved performance or ceramic waste forms.	Document	FCR&D	FY2012
Surface Layer Bulk Glass Interface Evolution with Aqueous Corrosion	Alfred University	$880,000	This project will investigate the links between the morphology, structure and chemistry of surface layer-bulk glass interface and the long-term corrosion-reaction kinetics using in-situ and ex-situ experiments. The understanding will result in improved models for long-term predictive behavior of high-level-waste (HLW) glasses under repository conditions.	Document	FCR&D	FY2012
Improved Accident Tolerance of Austenitic Stainless Steel Cladding through Colossal Supersaturation with Interstitial Solutes	Case Western Reserve University	$850,000	This project aims to develop new case-hardened austenitic stainless steels by saturating them with materials that improve their mechanical properties, corrosion resistance and radiation resistance. This project, if successful, will result in safer, longer-lasting, and more accident tolerant fuel claddings.	Document	FCR&D	FY2012
Optimization of Deep Borehole Systems for HLW Disposal	Massachusetts Institute of Technology	$850,000	Researchers aim to carry out a comprehensive evaluation of the deep borehole option for disposal of used nuclear fuel and high livel waste. The models developed will predict potential movement of water through natural and engineered barriers and release of radionuclides to the biosphere which will aide in site selection.	Document	FCR&D	FY2012
Scholarship for Nuclear Communications and Methods for Evaluation of Nuclear Project Acceptability	Massachusetts Institute of Technology	$800,000	Researchers will work to develop a model to characterize the factors affecting social acceptance of nuclear projects with potential stakeholders. The resultant model will strengthen the ability to design and implement large projects more efficiently, leading to higher rates of success of future nuclear projects.	Document	FCR&D	FY2012
Accurate Holdup Calculations with Predictive Modeling and Data Integration	North Carolina State University	$875,000	Researchers will develop and use state-of-the-art radiation transport codes to account accurately for the fissile material in a nuclear materials processing facility. An accurate estimation of the materials will allow for ensured radiological safety, security, waste management and efficient plant operation.	Document	FCR&D	FY2012
Novel Metal Sulfides to Achieve Effective Capture and Durable Consolidation of Radionuclides	Northwestern University	$760,000	Researchers will evaluate the effectiveness of chalcogenide based materials design novel metal sulfides to effectively capture and store of radioisotopes released during reprocessing of used nuclear fuel. This project will focus on understanding structure-property relationships to enable refined and direct synthesis approaches for improved and cost-efficient nuclear waste forms.	Document	FCR&D	FY2012
Nonlinear Ultrasonic Diagnosis and Prognosis of ASR Damage in Dry Cask Storage	Northwestern University	$885,000	Researchers aim to use nondestructive damage characterization methods to detect, manage and mitigate the degradation/damage mechanisms of dry cask storage systems for nuclear fuels. This project, if successful, will provide tools that will allow the prediction of the reliability and the safety of concrete structures in dry cask storage systems.	Document	FCR&D	FY2012
Prototype Demonstration of Gamma-Blind Tensioned Metastable Fluid Neutron/Multiplicity/Alpha Detector- Real Time Methods for Advanced Fuel Cycle Applications	Texas A&M University	$875,000	This project aims to create a prototype demonstration of a novel neutron/alpha detector based on a technology that is blind to gamma field used fuel. The prototype, if successful, will enhance instrumentation for monitoring real-time material balance during various stages of the nuclear cycle.	Document	FCR&D	FY2012
Testing of Sapphire Optical Fiber and Sensors in Intense Radiation Fields, when Subjected to Very High Temperatures	The Ohio State University	$885,000	The researchers on this project will investigate the performance of sapphire optical fibers and sensors in reactor environments. The project, if successful, will result in improved instrumentation to understand the behavior and predict performance of nuclear fuel systems at the microstructural level.	Document	FCR&D	FY2012
Concrete Materials with Ultra-High Damage Resistance and Self-Sensing Capacity for Extended Nuclear Fuel Storage Systems	University of California, Irvine	$800,000	Researchers aim to design a new class of multifunctional concrete materials. This project, if successful, will result in a novel multifunctional concrete material that possesses inherent degradation monitoring capability and is suitable for an extended storage system for the used nuclear fuel.	Document	FCR&D	FY2012
Development of Innovative Accident Tolerant High Thermal Conductivity UO2 Fuel Pellets with a Diamond Dopant	University of Florida	$800,000	Researchers will evaluate the use of diamond nanoparticles composite material in innovative accident tolerant fuel pellets. This could significantly improve both the thermal conductivity of fuel pellets and light water reactors' efficiency safety.	Document	FCR&D	FY2012
Probabilistic Multi-Hazard Assessment of Dry Cask Structures	University of Houston	$865,000	This project aims to investigate the performance of dry cask storage systems under multiple hazard systems (earthquake, tornados, combined with aging effects) using a probabilistic multi-hazard framework. This framework will be validated based on experimental research and will provide improved models for safety and reliability of spent nuclear fuels during storage and transportation.	Document	FCR&D	FY2012
Measurement of Irradiated Pyroprocessing Samples via Laser Induced Breakdown Spectroscopy	University of Idaho	$820,000	This project aims to use advanced characterization techniques to investigate microstructural changes and the micromechanisms related to irradiation induced damage in used nuclear fuels and waste forms. This project, if successful, will result in enhanced models to predict the structural and chemical response of used fuel and waster forms during interim storage and permanent disposal.	Document	FCR&D	FY2012
Elastic/Inelastic Measurement Project	University of Kentucky	$880,523	Researchers will measure nuclear data for elastic/inelastic scattered neutrons on coolants and structural materials. The data generated, will be useful for future R&D programs that will study innovative next generation LWR and future fast systems.	Document	FCR&D	FY2012
Electrochemical Corrosion Studies for Modeling Metallic Waste Form Release Rates	University of Nevada- Las Vegas	$790,000	This project aims to use advanced electrochemical methods to investigate the corrosion related degradation of metal alloys used for housing fission products. The data obtained from this study will allow for the prediction of the long-term behavior of the metallic host phase materials over geological time-scales.	Document	FCR&D	FY2012
Thermodynamic and Microstructural Mechanisms in the Corrosion of Advanced Ceramic Tc-bearing Waste Forms and Thermophysical Properties	University of Nevada- Las Vegas	$795,000	This project team will harvest thermodynamic and microstructural data on the evolution of ceramic based waste forms. The data will be used to advance the current state-of-the-art methodology used for isolation and stabilization of fission products and improve on nuclear fuel recycling processes.	Document	FCR&D	FY2012
Development and Experimental Benchmark of Simulations to Predict Used Nuclear Fuel Cladding Temperatures during Drying and Transfer Operations	University of Nevada- Reno	$745,000	Researchers will conduct experiments to investigate and develop advanced computational models of heat transfer in post-pool-storage drying operations. This project, if successful, will result in tools that can be used to design efficient drying processes to as to ensure suitability for dry-cask systems for long-term storage and transport.	Document	FCR&D	FY2012
Better Radiation Response and Accident Tolerance of Nanostructured Ceramic Fuel Materials?	University of Tennessee	$815,000	Researchers will use novel experimental methods to investigate the links between microstructure, phase stability and damage evolution in nanostructured ceramic fuel materials. The project will study fuel materials at temperatures and irradiation conditions relevant to operation and accidental scenarios.	Document	FCR&D	FY2012
Radiation and Thermal Effects on Used Nuclear Fuel and Nuclear Waste Forms	University of Tennesssee	$770,000	This project aims to investigate the structural and chemical response of used nuclear fuel and waste forms during interim storage and permanent disposal. If successful, this project will generate models that will allow the prediction of structural evolution and hence the radiological safety and security of nuclear fuel and waste forms.	Document	FCR&D	FY2012
Seismic Performance of Dry Casks Storage for Long-Term Exposure	University of Utah	$873,319	Researchers will evaluate the mechanical performance of dry-cask storage under seismic loading for mid-term operational periods. Simulations will include scenarios for freestanding, anchored, and vaulted casks. The experimental tests will also evaluate the dynamic seismic response of freestanding and anchored dry-cask storage prototypes, providing recommendations for optimal Interim Spent Fuel Storage Installations (ISFSIs) design.	Document	FCR&D	FY2012
Validation Experiments for Spent-Fuel Dry-Cask In-Basket Convection	Utah State University	$690,000	Researchers in this project aim to conduct experiments that generate data on natural convection through a fuel assembly. The data will be used to validate the computational models being developed for nuclear safety and design.	Document	FCR&D	FY2012
Re-Branding the Nuclear Fuel Cycle	Virginia Commonwealth University	$850,000	This project will create a comprehensive framework for the evaluation of alternative fuel cycle systems that will be used to identify and analyze key elements related to long-term management of nuclear fuels , with the ultimate goal to develop a communications strategy to reach stakeholders.	Document	FCR&D	FY2012
Advanced Characterization of Molecular Interactions in TALSPEAK-like Separations Systems	Washington State University	$875,000	Researchers will use advanced characterization techniques (experimental and computational) to improve understanding of the molecular level processes/interactions during separation processes for advanced fuel cycles. The understanding of these interactions will be used to develop more robust and streamlined separation processes for advanced fuel cycles.	Document	FCR&D	FY2012
Coupling of Nuclear Waste Form Corrosion and Radionuclide Transport in Presence of Relevant Repository Sediments	Washington State University	$885,000	Researchers will conduct experiments to understand the mechanisms responsible for the corrosion of nuclear waste forms in realistic chemical environments. The data generated from these experiments will enable increased reliability of the models used to predict the waste form performance in repository environments.	Document	FCR&D	FY2012
Stationary Liquid Fuel Fast Reactor (SLFFR) Concept for TRU Burning	Purdue University	$450,000	Reasearchers will investigate a new type of molten metallic fuel reactor concept that will consume hazardous transuranic waste. The liquid fuel alloy has several advantages over solid fuel fast reactors that are used for the same purpose.	Document	MSTR	FY2012
ABR for TRU Transmutation with Breed & Burn Thorium Blanket for Improved Economics and Resource Utilization	University of California- Berkeley	$450,000	The research team will use detailed neutronic analysis for a new Advanced Burner Reactor concept with low conversion ratio. The concept will use a new core shape to improve the utilization of neutrons to perform breed and burn.	Document	MSTR	FY2012
New Materials for High Temperature Thermoelecric Power Generation	University of California, Davis	$450,000	Reasearchers will work to develop nanostructured and other new materials to support the development of higher efficiency thermoelectric devices. These devices convert thermal energy to electricity with no moving parts. The new materials will operate at higher efficiencies and over a wider temperature range than those currently available--an important quality for future nuclear-powered deep space exploration.	Document	MSTR	FY2012
Microscopic Fuel Particles Produced by Self-Assembly of Actinide Nanoclusters on Carbon Nanomaterials	University of Notre Dame	$440,000	Reasearchers will develop the mechanisms, conditions and protocols to prepare uranium-carbon nanocomposite materials to make them more flexible. This could result in the generation of wholesale electricity, providing process heat, and providing power for households.	Document	MSTR	FY2012
High Hydrogen Content Graphene Hydride Compounds & High Cross-Section Cladding Coatings for Fast Neutron Detection	University of South Carolina	$430,000	This project will exploit recent breakthroughs to grow epitaxial graphene on commercial SiC wafers. This will allow researchers to develop a new detection method for fast neutrons. In addition, it will lead to better and more compact neutron detection system.	Document	MSTR	FY2012
Reducing Actinide Production Using Inert Matrix Fuels	University of Texas- Austin	$435,000	Reasearchers will perform a neutronic analysis, a thermal-hydraulic analysis and a simulation of fuel decay heat as a functionof fuel burnup, to determine if inert matrix fuel in coventional reactors will continue to be licensable. If successful, the inert matrix fuel mixtures will reduce harmful transuranic components in the fuel discharge streams at a level comparable to a fast reactcor burner.	Document	MSTR	FY2012
An Integrated Fuel Depletion Calculator for Fuel Cycle Options Analysis	University of Texas- Austin	$395,000	Reasearchers use new analysis techniques to better predict nuclear fuel behavior. The new model will allow improved fuel cycle for a larger number of users.	Document	MSTR	FY2012
Atomic-Scale to Meso-Scale Simulation Studies of Thermal Ageing and Irradiation Effects in Fe-Cr Alloys	Boston University	$874,997	Reasearchers will develop predictive, multi-scale simulation tools for iron-chromium alloys, which are expected to be key components of advanced steels envisioned as fuel cladding and structural components for Generation IV reactors. Such modeling is necessary to avoid resource intensive and costly thermal and neutron irradiation experiments to obtain required performance data.	Document	NEAMS	FY2012
Validation Data and Model Development for Fuel Assembly Response to Seismic Loads	George Washington University	$862,435	Reasearchers will conduct experiments that will provide comprehensive data characterizing the dynamics of the fluid and the structure in Pressurized Water Reactors (PWR) fuel assemblies under seismic loads (earthquakes and loss of coolant accidents). Completion of their project will greatly benefit the safety of existing and future nuclear reactors.	Document	NEAMS	FY2012
Uncertainty Quantification and Management for Multiscale Nuclear Materials Modeling	Georgia Institute of Technology	$743,444	Reasearchers will address the question of uncertainty propogation and error estimates associated with model prediction of material behavior under irradiation. Their work will facilitate a better understanding of the connection of various unit processes to collective responses in a multiscale model chain enabling the development of high strength and high ductility materials.	Document	NEAMS	FY2012
Fuel and Core Design Options to Overcome the Heavy Metal Loading Limit and Improve Performance and Safety of Liquid Salt Cooled Reactors	Georgia Insitute of Technology	$784,689	Reasearchers will examine new options for fuel and core designs in liquid salt cooled reactors where the current standard of TRISO type fuel has limitations due to loading characteristics. The research could enable new, more feasible fuel-core-reload options that will improve safety and performance parameters.	Document	RCRD&D	FY2012
Nonlinear Ultrasonic Techniques to Monitor Radiation Damage in RPV and Internal Components	Georgia Institute of Technology	$877,000	Reasearchers will explore new nondestructive materials evaluation and monitoring techniques utilizing nonlinear ultrasonic measurements . This technique will allow researchers to assess remaining useful life of select reactor components. Breakthroughs in this area will lead to the ability to characterize radiation damage in reactor pressure vessels and other components-leading to a clearer definition of reactor safety margins.	Document	RCRD&D	FY2012
Intergral Reactor Containment Condensation Model and Experimental Validation	Oregon State University	$871,119	Reasearchers will conduct experiments to enhance the safety and efficiency of small modular reactors (SMRs). This project will assess the impact of high-pressure steam condensation on steel containment vessels to be used for SMR deigns.	Document	RCRD&D	FY2012
Investigation of Natural Circulation Instability and Transients in Passively Safe Small Modular Reactors	Purdue University	$871,100	Reasearchers will perform scaled experiments to study the thermal-hydraulic instabilities that can occur in Small Modular Reactors (SMR) which rely on natural circulation cooling during normal operation and accident conditions. Their work will not only improve our understanding of general natural circulation instability but also lead to the development of stability criteria and predictability in the operation of SMRÃs.	Document	RCRD&D	FY2012
Thermoelectric-Driven Sustainable Sensing and Actuation Systems for Fault-Tolerant Nuclear Incidents	State University of New York, Stony Brook	$599,802	Reasearchers will examine the use of solid-state thermoelectric generators to produce electricity to sense and opeate during both normal and abnormal situations. This will provide indefinite monitoring of key components during power outages or station blackouts.	Document	RCRD&D	FY2012
Experimental and CFD Studies of Coolant Flow Mixing within Scaled Models of the Upper and Lower Plenums of NGNP Gas-Cooled Reactors	Texas A&M University	$713,051	Reasearchers will model the internal coolant flow of a prismatic core very high temperature reactor (VHTR) by using large eddy simulation tools. This method will enable more accurate prediction of flow field characteristics and better evaluation of VHTR behavior under operational and accidental conditions.	Document	RCRD&D	FY2012
Demonstrating Hybrid Heat Transport and Energy Conversion System Performance Characterization Using Intelligent Control Systems	University of Idaho	$877,000	Reasearchers will demonstrate an intelligent control systems in a hybrid energy conversion loop for a next generation nuclear power plant. Hybrid energy systems are a method of optimizing the use of natural resources for energy production. Hybrid systems present an opportunity to develop domestic energy sources to improve energy security.	Document	RCRD&D	FY2012
Advanced Reactor-Intermediate Heat Exchanger (IHX) Coupling: Theoretical Modeling and Experimental Validation	University of Idaho	$869,997	Reasearchers will model the behavior of the Advanced Reactor Intermediate Heat Exchanger Chemical Process system and develop advanced control techniques that take into account abnormal scenarios. The data and information obtained will assist in the development of intelligent control systems for next generation nuclear reactor systems.	Document	RCRD&D	FY2012
Irradiation Performance of Fe-Cr Base Alloys	University of Illinois- Urbana Champaign	$876,332	Reasearchers will perform post-radiation analysis and develop tools for future development and application of the Fe-Cr class of alloys. The results of this research will lead to better modeling of performance and development of an alloy designated as the primary choice for reactor fuel cladding and structural applications in advanced systems.	Document	RCRD&D	FY2012
Accelerated Irradiations for High Dose Microstructures in Fast Reactor Alloys	University of Michigan	$831,876	Reasearchers will determine the extent to which high dose rate irradiation can be used as an irradiation damage tool to understand microstructure evolution at high doses and temperatures relevant to advanced fast reactors. The project will provide fundamental understanding of the effectiveness of this process and thus of microstructure development in irradiated materials.	Document	RCRD&D	FY2012
Mitigating IASCC of Reactor Core Internals by Post-Irradiation Annealing Advanced Mitigation Strategies	University of Michigan	$876,985	Reasearchers will determine the optimum Post-irradiation annealing (PIA)-driven mitigation strategy to extend the potential lifetime of light water reactors. Samples that have already been irradiated in a light water reactor will be used to test PIA treatments to understand IASCC initiation and propoagation, annealing kinetics, the role of microstructure features in irradation hardening and localized deformation, and the optimum mitigation strategy based on PIA.	Document	RCRD&D	FY2012
Experimentally Validated Numerical Models for Effects of Non-Isothermal Turbulent Mixing on Wall Stresses in High Temperature Reactors	University of Pittsburgh	$876,422	Reasearchers will develop a comprehensive experimentally validated computational framework for the turbulent mixing in the lower plenum of a very high temperature reactor (VHTR). Through CFD modeling and experimental validation, the results from this project will lay the groundwork for future stress analysis, failure and fatigue studies, and uncertainty quantification for the VHTR system.	Document	RCRD&D	FY2012
Role of Defects in Swelling and Creep of Irradiated SiC	University of Wisconsin- Madison	$875,350	Reasearchers will study mechanisms controlling both radiation swelling and radiation creep in silicon carbide. These two effects are crucial to understanding the issues associated with the brittle silicon carbide composite. Success in this project will ground progress in the adoption of silicon carbide for reactor solutions, particularly as fuel cladding.	Document	RCRD&D	FY2012
Advanced Supercritical Carbon Dioxide Brayton Cycle Development	University of Wisconsin, Madison	$877,000	Reasearchers will investigate the benefits of utilizing advanced Brayton cycles with supercritical carbon dioxide in new reactor systems and components. Benefits of this research include improvement of analysis and performance of components currently utilizing these cycles as well as the potential for a large scale advanced CO2 power system.	Document	RCRD&D	FY2012
Mechanical Behavior of UO2 at Sub-grain Length Scales: Quantification of Elastic, Plastic and Creep Properties via Microscale Testing	Arizona State University	$800,000	Reasearchers will develop techniques to measure properties at sub-grain scales using depleted Uranium Oxide samples. The project will provide a framework to measure sub-grain scale mechanical properties, as well as provide experimental data to improve the understanding of advanced oxide fuels.	Document	FCR&D	FY2013
The Impacts of Pore-Scale Physical and Chemical Heterogeneities on the Transport of Radionuclide-Carrying Colloids	Colorado School of Mines	$800,000	Reasearchers will identify the dominant transport mechanisms to develop models that predict radionuclide distribution in porous materials. Experimental and computational models will be created that couple pore-scale geometric and interfacial structures. Simulators such as these are a necessary step towards fully predictive models for field-scale applications in the future.	Document	FCR&D	FY2013
Recovery of Uranium from Seawater: Polymer-Supported Aminophosphinates as Selective Extractants	Hunter College, CUNY	$399,999	Reasearchers will prepare a polymer-supported extractant for the recovery of uranium from seawater. The project will focus on primary amines that could provide a 3-fold increase in uranium capture capacity than current methods.	Document	FCR&D	FY2013
In-pile Thermal Conductivity Characterization with Single-laser Heating/Time Resolved Raman	Iowa State University	$800,000	Reasearchers will develop a time-resolved Raman-based thermal conductivity measurement system to improve remote in-pile thermal conductivity measurement. These measurements will provide new insights into the behavior of materials exposed to extreme radiation and temperature environments. Understanding the behavior of materials at the microstructural level will support optimized fuel designs.	Document	FCR&D	FY2013
Organic Speciation and Interactions in ALSEP - One Step Partitioning Process of Minor Actinides, Lanthanides, and Fission Products	Oregon State University	$600,000	Reasearchers will investigate the Actinide-Lanthanide Separation (ALSEP) process organic phase prior to aqueous phase separation and after aqueous separation phases of bare and metal-loaded acids. Quantifying these effects can be used to determine how an engineering scale process will perform and generate an accurate chemical model for the system.	Document	FCR&D	FY2013
Glass Composition and Solution Speciation Effects on Stage III Dissolution	Pennsylvania State University	$700,000	Reasearchers will study the chemical and structural triggers of long-term vitrified nuclear waste form behavior. They will study a range of waste glass compositions in corrosive environments. The study will improve understanding of the long-term residual rate and may provide new options for environmental control of glass dissolution rates.	Document	FCR&D	FY2013
Correlating Thermal, Mechanical, and Electrical Coupling Based Multiphysics Behavior of Nuclear Materials Through In-Situ Measurements	Purdue University	$800,000	Reasearchers will use in-situ experimental techniques to monitor the influence of extreme conditions on fuel cladding. The project will establish an in-situ experimental setup that can predict change in thermal properties and their correlation with mechanical properties and correlate such changes to changes in microstructural and chemical features.	Document	FCR&D	FY2013
Creation of a Geant4 Muon Tomography Package for Imaging of Nuclear Fuel in Dry Cask Storage	Purdue University	$440,000	Reasearchers will develop a simulation and analysis package to aid in the non-destructive assessment of sealed used nuclear fuel dry casks using cosmic ray muons. Cosmic ray muon tomography allows for non-destructive assessment that can independently verify and identify weapons grade material sealed within dense dry casks.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Two-stage Fast Reactor Fuel Cycle Options for Optimum Resource Utilization and Waste Management	Purdue University	$400,000	Reasearchers will evaluate the two different two-stage fast reactor fuel cycle options that will offer efficient use of uranium resources and the ability to burn actinides and long-live fission products. Evaluation of these fast fuel cycle options will serve as a useful complement to the options currently being considered in the Fuel Cycle Options Campaign.	Document	FCR&D	FY2013
Mixed Metal Phosphonate-Phosphate Resins for Separation of Lanthanides from Actinides	Texas A&M University	$650,000	Reasearchers will use ion exchangers to cleanly separate lanthanides and curium from reusable actinides. The study will assist in the development of an inexpensive, simple way in which to separate lanthanides from actinides found in used nuclear fuel rods and to recover a large portion of the usable fuel.	Document	FCR&D	FY2013
Safeguards in Pyroprocessing: an Integrated Model Development and Measurement Data Analysis	The Ohio State University	$626,151	Reasearchers will develop a comprehensive and effective safeguards approach for a pyroprocessing facility to support safeguards for future fuel cycles in the United States. The new approach and design will focus directly on the special nuclear materials in the electrorefiner where actinides are separated from fission products through electrochemical process.	Document	FCR&D	FY2013
Using Ionic Liquids for the Development of Renewable Biopolymer-Based Adsorbents for the Extraction of Uranium from Seawater and Testing Under Marine Conditions	University of Alabama	$400,000	Reasearchers will explore the fundamental engineering parameters for a renewable high-performance adsorbent for the extraction of uranium from sweater based on a recently proven ionic liquid (IL)-chitin platform. The project will use the platform to develop a versatile, modifiable adsorbent and characterize its performance and degradation in marine conditions.	Document	FCR&D	FY2013
Developing Ultra-Small Scale Mechanical Testing Methods and Microstructural Investigation Procedures for Irradiated Materials.	University of California, Berkeley	$800,000	Reasearchers will develop new small-scale mechanical testing techniques to allow for the estimation or direct measurement of bulk properties. The combined experiments and modeling will significantly enhance the statistics and information that can be obtained on small radioactive archived samples, as well as new ion beam irradiated specimens.	Document	FCR&D	FY2013
Improved Delayed-Neutron Spectroscopy Using Trapped Ions	University of California, Berkeley	$400,000	Reasearchers will develop innovative spectroscopy techniques to measure the decay of fission fragments. The resulting data from these new techniques will be used to better understand reactor kinetics under accident conditions and failure scenarios.	Document	FCR&D	FY2013
Thermally and Chemically Responsive Nanoporous Materials for Efficient Capture of Fission Product Gases	University of California, Davis	$750,000	Reasearchers will create new nanoporous materials that will be highly effective at capturing fission product gases. These materials would be relevant to both reactor fuels applications and reprocessing operations. Tests will be performed in carbon based and nitride based nanostructures, with the most promising materials from the modeling perspective undergoing further testing.	Document	FCR&D	FY2013
Multiphase Nanocrystalline Ceramic Concept for Nuclear Fuel	University of California, Irvine	$800,000	Researchers will study the use of nanoparticles and nanostructured ceramics to create new materials that can extend the service life and increase efficiency for nuclear fuel. Multiphase nanocrystalline ceramics will be used to design simulated nuclear fuel that can provide added plasticity, better radiation tolerance and improved thermal conductivity.	Document	FCR&D	FY2013
Development of Novel Porous Sorbents for Extraction of Uranium from Seawater	University of Chicago	$400,000	Reasearchers will develop a highly porous sorbent for the extraction of uranium from seawater. Previous research has established sorbent performance. This project will use past foundational studies to design and investigate a new nanocomposites that will be processed into tacks or braids for field tests in seawater tests. The technology may also be used for other metals.	Document	FCR&D	FY2013
Microwave Readout Techniques for Very Large Arrays of Nuclear Sensors	University of Colorado, Boulder	$799,937	Reasearchers will develop a powerful readout technique based on microwave transmission and reflection. The technique will enable very large arrays of diverse sensor types for nuclear materials quantification and tracking. It will provide more accurate data on material composition and quantity.	Document	FCR&D	FY2013
BiI3 Gamma-Ray Spectrometers for Reliable Room-Temperature Nuclear Materials Safeguarding	University of Florida	$799,999	Reasearchers will develop gamma-ray spectrometers based on BiI3 single crystals for MPACT applications such as burnup validation quantification, improved assay of plutonium, determination of uranium enrichment and overall monitoring spent fuel within the fuel cycle. The project will improve energy resolution, efficiency and environmental performance with this new gamma-ray detector.	Document	FCR&D	FY2013
Innovative Coating of Nanostructured Vanadium Carbide on the F/M Cladding Tube Inner Surface for Mitigating the Fuel Cladding Chemical Interactions	University of Florida	$760,276	Researchers will develop barrier coatings on the inner surface of fuel cladding tubes to improve performance of materials at elevated temperatures and high neutron exposures in fast reactors. The project will develop and test a low temperature coating process of nanostructured vanadium carbide that will provide a benchmark for use in future studies.	Document	FCR&D	FY2013
Doubling the Life of Concrete Structures	University of Idaho	$800,000	Reasearchers will use nanoscale techniques to develop methods for doubling the service life of concrete structures. They will study the effect of temperature load and temperature cycling (freezing and thawing) on the durability of concrete with nanoscale viscosity modifiers. The project will benefit from non-destructive evaluation of concrete performance through electrochemical techniques.	Document	FCR&D	FY2013
Off-Gas Treatment: Evaluation of Nano-structured Sorbents for Selective Removal of Contaminants	University of Idaho	$785,910	Reasearchers will evaluate nanostructured sorbent materials for their effectiveness in removing and immobilizing radionuclides for the off-gas treatment from used nuclear fuel recycling operations. The project aims at achieving near-zero emissions of radionuclides by capturing them from the off-gas of recycling operations, allowing for the development of advanced fuel cycles.	Document	FCR&D	FY2013
Innovative Elution Processes for Recovering Uranium and Transition Metals from Amidoxime-Based Sorbents	University of Idaho	$399,864	Reasearchers will develop a new two-step elution process to achieve total recovery of uranium and effective recycling of the sorbent. The extraction process would selectively remove uranium from the sorbent with little or no damage. The process would then remove transition metals and regenerate the sorbent for repeated use, making uranium extraction from seawater economically viable.	Document	FCR&D	FY2013
Performance of a Steel/Oxide Composite Waste Form for Combined Waste Streams from Advanced Electrochemical Processes over Geologic Time Scales	University of Illinois at Chicago	$700,000	Reasearchers will develop and validate a mechanistically-based corrosion model for cermet-type waste forms, creating a testing protocol and modeling approach for predicting long-term performance. The study will apply novel electrochemical testing and modeling methods to the behavior of metal/oxide phase boundaries to evaluate waste form performance.	Document	FCR&D	FY2013
Enhancement of the Extraction of Uranium from Seawater	University of Maryland, College Park	$400,000	Reasearchers will develop and optimize novel adsorbents for uranium recovery from seawater. The team will use radiation-induced grafting of organic phosphates onto polymers. The experiments will use ocean water, with mechanistic analysis, to provide a solid basis for large-scale demonstration of the performance of the new adsorbents in ocean environments.	Document	FCR&D	FY2013
Improving the Understanding of the Coupled Thermal-Mechanical-Hydrologic Behavior of Consolidating Granular Salt	University of New Mexico	$800,000	Reasearchers will increase the understanding of granular salt seal materials for shafts, drifts and boreholes. By coupling thermal, mechanical and hydrological responses, the study will result in greater confidence in granular salt consolidation as a principal strategy for closure and isolation of long-term waste repositories.	Document	FCR&D	FY2013
Fission Fragment Yield Data in Support of Advanced Reactor Technology	University of New Mexico	$399,816	Reasearchers will produce a highly accurate data set for thermal fission. These precision data are necessary for high-accuracy simulations of nuclear criticality, transmutation rates, radiation effects and heating as well as for nuclear fuel, material accounting and identification needs.	Document	FCR&D	FY2013
Molecular dynamics-based simulations of bulk/interfacial structures and diffusion behaviors in nuclear waste glasses	University of North Texas	$700,000	Reasearchers will generate accurate atomic structural models for use in Monte Carlo simulations of the dissolution of nuclear waste glasses. Large-scale molecular dynamics-based computer simulations will be used to investigate self-diffusion behaviors, interfacial structure, and other structures formed during dissolution of these glasses.	Document	FCR&D	FY2013
U3Si2 Fabrication and Testing for Implementation into the BISON Fuel Performance Code	University of South Carolina	$800,000	Reasearchers will fabricate, test and model a high uranium density, advanced nuclear fuel that operates at a much lower temperature and stores less energy. The work will deliver key research data on creep and grain growth, improving economics, through possible power uprates, and advancing accident tolerant fuels research.	Document	FCR&D	FY2013
Structural Health Monitoring of Nuclear Spent Fuel Storage Facilities	University of South Carolina	$738,618	Reasearchers will develop a nuclear structural health monitoring system based on a sensing technology that monitors material degradation and aging for dry cask storage systems. The low-cost, low-profile sensors will perform on-demand monitoring of the structural integrity of individual components as well as the entire system.	Document	FCR&D	FY2013
ORIGEN-based Nuclear Fuel Depletion Module for Fuel Cycle Assessment	University of Tennessee at Knoxville	$755,181	Reasearchers will develop a flexible reactor analysis module for the CYCLUS fuel cycle simulator based on established tools for reactor fuel depletion and decay. They will use ORIGEN, a mature and experimentally validated code, affording greater flexibility and allowing for accurate evaluations of impacts of both present and future fuel cycle options.	Document	FCR&D	FY2013
Cost and System Analysis of Innovative Fuel Resources Concepts	University of Texas at Austin	$295,960	_This project will develop and test braided polymer fiber adsorbents that surpass the sorption capacity, selectivity and durability of the best existing technology to recover uranium from seawater.	Document	FCR&D	FY2013
Risk Assessment of Structural Integrity of Transportation Casks	University of Utah	$789,296	Reasearchers will assess the loss of structural integrity of transportation casks and fuel cladding after extended storage. This risk assessment will conduct experimental tests and simulations to evaluate the structural performance of fuel, fuel assemblies and cask components when subjected to vibration and impact loads during transport.	Document	FCR&D	FY2013
Market-Based and System-Wide Fuel Cycle Optimization	University of Wisconsin, Madison	$612,731	Reasearchers will create market and economic optimizers to improve calculations for the CYCLUS fuel cycle simulator. The team will leverage existing optimization software frameworks within the simulator to resolve top level policy questions. The optimizations will allow CYCLUS to move beyond static material compositions, providing a holistic view of the fuel cycle system.		FCR&D	FY2013
Optical Fiber Based System for Multiple Thermophysical Properties for Glove Box, Hot Cell and In-Pile Applications	Utah State University	$799,975	Reasearchers will use a small pressure vessel to develop a robust technique for the measurement of multiple thermophysical properties at very high temperatures. The technique will lead to a system design moving toward the eventual measurement of irradiated fuels in a glovebox and/or hot cell with all sensors and electronics outside of the glovebox and/or hot cell.	Document	FCR&D	FY2013
Development of a Nano-Modified Concrete for Next Generation of Storage Systems	Vanderbilt University	$796,268	Reasearchers will use nano-sized and nano-structured particles based on enhanced reactivity to develop a superior concrete for the long-term storage of used nuclear fuel. The project will use state-of-the-art experimental chemical and mechanical characterizations and computation analysis to assess the performance of nano-modified concretes.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Thorium Fuel Cycle Options	Vanderbilt University	$797,995	Reasearchers will develop six fuel cycle data packages for multi-stage, thermal fuel cycles which incorporate thorium. These new fuel cycle data packages will provide the opportunity to examine fuel cycle options beyond those which have traditionally been considered. A thorium fuel cycle database will also be assembled as a basis for thorium literature for future evaluations of the thorium fuel cycle.	Document	FCR&D	FY2013
Enhanced Shielding Performance of HLW Storage Packages via Multi-Component Coatings	Virginia Polytechnic Institute and State University	$796,947	Reasearchers will develop a multi-layer composite that will enhance long-term storage and facilitate safe transport of storage packages. This novel multi-layer, multi-component coating would create an outer shield material that is resistant to the corrosion, radiation, diffusion and thermal cycling processes that affect fuel packages during long term storage.	Document	FCR&D	FY2013
Managing Zirconium Chemistry and Phase Compatibility in Combined Process Separations for Minor Actinide Partitioning	Washington State University	$700,000	Reasearchers will address unique challenges for combining TRUEX and TALSPEAK processes for partitioning of lanthanides and minor actinides. The project will develop improved information on the thermodynamics of fission product zirconium and develop a framework for an organic phase solvation model. Combined process development could streamline separations processes.	Document	FCR&D	FY2013
Advances in the Recovery of Uranium from Seawater: Studies Under Real Ocean Conditions	Woods Hole Oceanographic Institution	$398,882	Reasearchers will provide infrastructure and expertise for marine testing of currently available adsorbents in real ocean conditions. The team will move adsorbent research from the lab to field testing in order to quantify sorptive properties and uranium uptake. The project will provide valuable field data that will show the potential of large scale applications of these technologies.	Document	FCR&D	FY2013
NEUP Project 20-19172: Irradiation of Sensors and Adhesive Couplants for Application in LWR Primary Loop Piping and Components		$497,881	Reasearchers paln to attach ultrasonic transducers to substrates using various adhesive couplants that will be irradiated at elevated temperature to simulate LWR primary loop conditions at the PULSTAR reactor at North Carolina State University. Ultrasonic data will be taken in-situ. Subsequently, the sensors and couplant interfaces will be characterized using the LAMDA facility at ORNL. The results will be used to benefit a parallel EPRI project on online monitoring of cracks in LWR primary loop piping._	Document	R&D NSUF	FY2013
NEUP Project 20-19404: Extension of MSTDB to Provide a High-Quality, Validated Thermochemical Database for Predicting/Simulating Corrosion in Molten Salt Reactor SystemsUniversity of South Carolina		$600,000	Reasearchers will generate a validated, consistent database of initial fuel compositions and potential corrossion products of fluoride and chloride salts, allowing for important phenomena predictions in molten salt reactors to guide confident decisions. The database will be integral to the currently being developed Molten Salt Thermochemical Database (MSTDB), structured to allow use by commercial and open source codes._	Document	NEAMS	FY2013
Lower Length Scale Characterization and Validation of Formation and Stability of Helium Bubbles in Nano-structured Ferritic Alloys under Irradiation	Clemson University	$399,870	Reasearchers will provide a fundamental knowledge about the formation and stability of ultra-fine helium bubbles within 14YWT after neutron/ion irradiation for further design of new advanced structural materials with a characteristic high density nanoparticles feature which can increase the mechanical strength, hardness, irradiation resistance and the operational temperature range of materials.	Document	NEAMS	FY2013
Three-Dimensional Fuel Pin Model Validation by Prediction of Hydrogen Distribution in Cladding and Comparison with Experiment	Pennsylvania State University	$800,000	Reasearchers will validate important three-dimensional aspects of the fuel pin modeling by using specialized numerical modeling techniques coupled with laboratory experiments to validate existing models for predicting fuel performance in light water reactors.	Document	NEAMS	FY2013
Collocation-Based Surrogate Models for Uncertainty Quantification and Validation of Coupled, Multiphysics Fuel Performance Simulation Tools	University of Michigan	$596,835	Reasearchers will provide the necessary high fidelity, coupled, multiphysics fuel performance simulator for computational modeling and develop surrogates which will accelerate and focus the validation of the coupled codes. This will be achieved by utilizing the high fidelity coupled fuel performance, thermal-hydraulics and neutronics codes BISON/STAR-CCM+/MPACT and an innovative collocation-based surrogate methodology.	Document	NEAMS	FY2013
Multi-Resolution In-Situ Testing and Mutliscale Simulation for Creep Damage Fatigue Damage Analysis of Alloy 617	Arizona State University	$800,000	This project will develop novel testing and experimentally validated prediction methodologies for micro-structural damage mechanisms of structural materials for advanced reactor systems. The investigations will focus on the characterization and testing of specific metal alloys, but the proposed testing and life-prediction methodologies are applicable to other structural materials as well.	Document	RCRD&D	FY2013
Novel High Temperature and Radiation Resistant Infrared Glasses and Optical Fibers for Sensing in Advanced Small Modular Reactors	Clemson University	$800,000	Clemson University, in partnership with the Iowa State University and the Pacific Northwest National Laboratory, will develop novel optical materials with improved heat and radiation exposure resistance in order to enable in-vessel fiber optic sensing for advanced Small Modular Reactors.	Document	RCRD&D	FY2013
Validation Data Acquisition in HTTF during PCC Events	George Washington University	$800,000	Reasearchers at the George Washington University and Oregon State University will collaborate with NASA Langley Research Center to measure flow velocities in a high temperature test facility. This work supports the development of very-high temperature reactors with passive safety systems.	Document	RCRD&D	FY2013
Advanced High Temperature Inspection Capabilities for Small Modular Reactors	Iowa State University	$790,822	The objective of this project is to develop non-destructive evaluation techniques for advanced small modular reactors. The research will provide key enabling inspection technologies needed to support the design and the reactor component performance validation process for advanced small modular reactors.	Document	RCRD&D	FY2013
Experimental and Computational Investigations of Plenum-to-Plenum Heat Transfer under Natural Circulation in a Prismatic Very High Temperature Reactor	Missouri University of Science and Technology	$799,999	Reasearchers will perform experimental and computational investigations to study heat transfer and natural circulation phenomena in very-high temperature reactors. The study will assist in the ability to predict and analyze passive safety systems.	Document	RCRD&D	FY2013
New Mechanistic Models of Creep-Fatigue Crack Growth Interactions for Advanced High Temperature Reactor Components	Oregon State University	$790,790	Reasearchers will create and validate a robust, multi-scale, numerical model to predict material degradation in nickel-based reactor alloys. If successful, this project will provide better numerical tools for reactor designers and greatly improve their capability to design against material failures for reactor alloys in the long term.	Document	RCRD&D	FY2013
Self-Powered Wireless Dual-mode Langasite Sensor for Pressure/Temperature Monitoring of Nuclear Reactors	State University of New York, Stony Brook	$800,000	This research will develop a novel self-powered wireless hybrid sensor that can accurately monitor both pressure and temperature using a single device without requiring external electricity, even in extreme harsh environments.	Document	RCRD&D	FY2013
Compact Heat Exchanger Design and Testing for Advanced Nuclear Reactors and Advanced Power Cycles	The Ohio State University	$800,000	The goal of this project is to investigate optimal heat exchanger designs for advanced reactors. The research will study the optimization of printed circuit heat exchangers for specific fluids under a variety of conditions as well as perform numerical modeling. Experiments will focus on thermal performance and heat stress during extreme conditions.	Document	RCRD&D	FY2013
Fundamental Understanding of Creep-Fatigue Interactions in 9Cr-1MoV Steel Welds	The Ohio State University	$798,000	This project will advance the state of knowledge and fundamental understanding of deforming materials and welds under loading conditions. Specifically, new integrated testing procedures will be evaluated and applied for conditions that are most detrimental to material stability leading to improved predictions of life expectancy for reactor steels and welds.	Document	RCRD&D	FY2013
Advanced Mechanistic 3D Spatial Modeling and Analysis Methods to Accurately Represent Nuclear Facility External Event Scenarios	The Ohio State University	$800,000	Reasearchers will develop three-dimensional characterization uncertainty analysis for commercial power plants. The project will involve combining experts from the fields of seismic structural modeling and advanced methods of risk assessment. This effort is expected to result in next generation tools that can be used for assessment of seismic risks.	Document	RCRD&D	FY2013
Tritium Mitigation/Control for Advanced Reactor Systems	The Ohio State University	$400,000	Reasearchers will develop a fluoride salt cooled high-temperature reactor featuring a specialized system to control tritium production. If successful, this will result in a significant reduction in size and cost in comparison to other reactor designs.	Document	RCRD&D	FY2013
A Pebble-Bed Breed and Burn Reactor	University of California, Berkeley	$400,000	Reasearchers will assess the feasibility of designing a type of metal cooled reactor able to establish and maintain operation when fueled with depleted uranium. If successful, this reactor will offer at least a 30-fold increase in the uranium ore utilization versus that achieved in contemporary light water reactors without the need for fuel reprocessing and recycling.	Document	RCRD&D	FY2013
Investigation of Thermal Aging Effects on the Evolution of Microstructure and Mechanical Properties of Cast Duplex Stainless Steels	University of Maryland, College Park	$799,966	This research will provide a better understanding of the microstructural evolution and simultaneous change in mechanical response during aging. The results of the research will provide data that can be used to estimate degraded mechanical properties for an 80-year service life of light water reactors.	Document	RCRD&D	FY2013
Model validation using CFD-grade experimental database for NGNP Reactor Cavity Cooling Systems with water and air	University of Michigan	$799,348	Reasearchers will use advanced innovative instrumentation to build a high-resolution experimental database and to use the novel experimental data to assess and further develop the predictive capabilities of computer codes for thermal hydraulics and computational fluid dynamics. The improved models developed by this project will also have the direct benefit of improving the predictive capability of the passive systems of third generation light water reactors and small modular reactor systems.	Document	RCRD&D	FY2013
Long-Term Prediction of Emissivity of Structural Material for High Temperature Reactor Systems	University of Missouri	$799,117	Reasearchers will study specific types of emissivity driven cooling from a variety of materials that are relevant to nuclear reactors. The research will provide a basis for numerical modeling to support reactor development.	Document	RCRD&D	FY2013
Advanced I&C for Fault-Tolerant Supervisory Control of Small Modular Reactors	University of Pittsburgh	$800,000	The purpose of this research is to develop advanced instrumentation and control techniques for supervisory control of advanced small modular reactors. This research supports the operational goals of small modular reactor concepts through the development of improved oversight and surveillance techniques.	Document	RCRD&D	FY2013
Corrosion of Structural Materials for Advanced Supercritical Carbon-Dioxide Brayton Cycle	University of Wisconsin-Madison	$798,672	Reasearchers will study a variety of materials for corrosion resistance under conditions that improve power conversion. In addition to studying the corrosion resistance of the materials, researchers will study the effect of additives to mitigate corrosion. Development of corrosion theories and modeling aimed at prediction of long-term corrosion will be the underlying theme throughout the project.	Document	RCRD&D	FY2013
Component and Technology Development for Advanced Liquid Metal Reactors	University of Wisconsin-Madison	$798,920	In support of liquid metal cooled reactors, the University of Wisconsin, Madison will evaluate advanced alloys and ceramics that come in contact with liquid metals. Additionally, a robust oxygen sensor and for use in liquid metals will be developed in order to better evaluate corrosion profiles in support of diagnostic testing.	Document	RCRD&D	FY2013
A New Paradigm for Understanding Multi-phase Ceramic Waste Form Performance	Clemson University	$800,000	Researchers will use advanced characterization tools to develop 3-D microstructural data that can be incorporated into computer-based simulations in order to predict the performance of waste forms. Materials system modeling will incorporate elemental release and the interconnected microstructural network of phases to better understand performance and degradation, which will accelerate waste form acceptance in repository settings.	Document	FCR&D	FY2014
Controlling Hexavalent Americium: A Centerpiece to a Compact Nuclear Fuel Cycle	Colorado School of Mines	$800,000	Researchers will develop and exploit the fundamental chemistry of Americium to enable an industrially viable means to co-recover the major and minor actinide elements from used nuclear fuel. The results would be a significant step forward in the development of aqueous separations approaches designed to recover the U-Am actinides based on the availability of the hexavalent oxidation state.	Document	FCR&D	FY2014
Zeolite Membranes for Krypton/Xenon Separation from Spent Nuclear Fuel Reprocessing Off-Gas	Georgia Institute of Technology	$400,000	Researchers will develop a high-performance, lower-cost zeolitic membrane process for Kr/Xe separations during spent nuclear fuel processing. Current separation methods are not considered economical and a membrane process would have relatively lower cost, equipment size, and ambient operating temperature. The process would form a sound basis for further development of this transformative separation technology for the nuclear fuel cycle.	Document	FCR&D	FY2014
Optimizing Polymer-Grafted Amidoxime-based Adsorbents for Uranium Uptake from Seawater	Georgia Institute of Technology	$399,999	Researchers will work to increase the adsorbent capacity and selectivity toward uranium by optimizing the adsorbent morphology, synthesis variables, and conditioning parameters and by investigating the rate-limiting variables through transport and reaction modeling. A novel adsorption/partition concept that has the potential to substantially increase the adsorbent capacity will be tested, making uranium from seawater extraction more economically viable.	Document	FCR&D	FY2014
Extraction of Uranium from Seawater: Design and Testing of a Symbiotic System	Massachusetts Institute of Technology	$400,000	Researchers will develop a seawater uranium extraction system that will work symbiotically with an offshore windmill by utilizing the structure, mooring and power of the windmill, while increasing the energy harvested by the installation. Uranium will be extracted by an adsorbent polymer belt, which will be cycled through the seawater and an elution plant located at the base of the windmill tower. Increasing the frequency of harvesting could overcome current economic barriers to seawater uranium extraction.	Document	FCR&D	FY2014
Imaging a Dry Storage Cask with Cosmic Ray Muons	Oregon State University	$799,871	Researchers will develop an imaging system to monitor the content of a dry storage cask with cosmic ray muons. A very large amount of plutonium under nuclear safeguards is contained in used fuel assemblies stored in dry storage casks. Muon imaging will allow a cost effective and reliable way to evaluate dry storage cask content and integrity before transport.	Document	FCR&D	FY2014
Apatite and sodalite based glass-bonded waste forms for immobilization of 129I and mixed halide radioactive wastes	Rutgers University	$800,000	Researchers will develop advanced and chemically durable waste forms for immobilizing 129I (aqueous based reprocessing of fuel) and mixed-halide wastes (molten-salt processing of fuel) by low temperature synthesis. Halide-containing sodalite and calcium phosphate-based apatite minerals will be synthesized, consolidated and tested for chemical durability. The project will provide needed baseline data for the development of advanced waste forms for immobilization of iodine and mixed-halide wastes.	Document	FCR&D	FY2014
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$350,000	Researchers will develop modeling tools supported by experiments for off-gas capture from future nuclear-fuel recycling facilities. Target species include tritium, iodine, krypton, and xenon. The models are intended to provide path forward recommendations to develop off-gas treatment adsorption processes. The project will contribute to the evaluation of options for environmentally acceptable recycle systems.	Document	FCR&D	FY2014
Development of high performance ODS alloys	Texas A&M University	$800,000	Researchers will study swelling, radiation hardening and changes in mechanical properties of ODS alloys to develop two sets of advanced ODS alloys. Two sets of first-round candidate alloys that have already undergone extensive development and testing will evaluate irradiation performance. The study will meet the need for high strength, radiation-tolerant cladding and core components that have enhanced resistance to void swelling.	Document	FCR&D	FY2014
Rare Earth Electrochemical Property Measurements and Phase Diagram Development in a Complex Molten Salt Mixture for Molten Salt Recycle	The Ohio State University	$800,000	Researchers will investigate rare earth (RE) properties in complex molten salt mixtures. In a molten salt recycle approach, the RE drawdown by electrolysis is a key step in which REs are separated from salt containing other fission products. Investigation of RE electrolysis must consider the electrochemical properties of the REs. We propose to conduct studies of detailed experiments and corresponding models to provide the physical properties and phase diagrams required to predict the performance of RE drawdown for processing complex molten salts.	Document	FCR&D	FY2014
Studies of Lanthanide Transport in Metallic Nuclear Fuels	The Ohio State University	$800,000	Researchers will study the redistribution of lanthanides and migration of lanthanides to the fuel surface. The mechanisms of lanthanide transport in metallic fuel based on the novel discovery of a Ôliquid-likeÕ transport mechanism will be studied analytically and experimentally. The project will develop a fundamental understanding of lanthanide fission product migration and redistribution in advanced metallic nuclear fuels, and theory and data to mitigate fuel-cladding chemical interactions.	Document	FCR&D	FY2014
Computational and Experimental Studies of Microstructure-Scale Porosity in Metallic Fuels for Improved Gas Swelling Behavior	University of Arkansas	$796,823	Researchers will study the microstructure of metallic uranium alloy fuels, and their resistance to densification, to minimize in-pile irradiation swelling through bimodal pore size distribution. The project will develop a predictive approach to design metallic fuel microstructures for optimal swelling resistance and fission gas retention.	Document	FCR&D	FY2014
Improved Hybrid Modeling of Spent Fuel Storage Facilities	University of California, Berkeley	$645,393	Researchers will develop a variance reduction method for computational transport that will improve the ability to design and operate monitoring systems for interim used fuel installations through enhanced modeling and simulation. This new tool will demonstrate that modeling calculations can be done more accurately in less time than with current tools and will perform studies characterizing how changes in material, cask configurations, and number of casks could impact monitoring systems.	Document	FCR&D	FY2014
Selective ligands for uranyl via combinatorial peptoid libraries: A synthetic, structural, thermodynamic and computational study	University of California, Berkeley	$400,000	Researchers will study how donor ligands bind to the uranyl ion, UO22+, with the longer-term goal of using this information to tackle selective recognition of uranyl in aqueous solution. The study will impact underlying approaches to controlling the behavior of uranium in these systems. The actinide separation technology could be used in several areas including uranium extraction from seawater, nuclear waste remediation and nuclear materials.	Document	FCR&D	FY2014
Combining Experiments and Simulations of Extraction Kinetics and Thermodynamics in Advanced Separation Processes for Used Nuclear Fuel	University of California, Irvine	$799,938	Researchers will study how the kinetics and thermodynamics of metal ion extraction in advanced separation processes for used nuclear fuel can be described by molecular dynamic (MD) simulations and how the simulations can be validated by experimental data. The project would have broad impacts on several separations processes including advanced TALSPEAK, ALSEP and GANEX by increasing the confidence and accuracy of computer modeling of metal ion extraction._	Document	FCR&D	FY2014
Effect of Metallic Li on the Behavior of Metals in Molten Salts	University of Nevada, Reno	$458,250	Researchers will identify the effect of metallic lithium on materials that are used in molten salt recycling. The study will try to understand how the presence of Li(0) in molten salts affects the degradation of alloys. Studying these changes will help accurately predict container material behavior and longevity.	Document	FCR&D	FY2014
Assessment of Corrosion Resistance of Promising Accident Tolerant Fuel Cladding under Reactor Conditions	University of Notre Dame	$800,000	Researchers will assess the corrosion behavior of accident tolerant fuel candidate iron-based alloys under normal LWR operating conditions consisting of high temperature, relevant water chemistry and irradiation. The assessment will produce data about possible irradiation-accelerated corrosion rates of iron-based alloys, and the mechanisms by which such corrosion rates are accelerated. The project will advance the selection of appropriate replacements for Zircaloy cladding.	Document	FCR&D	FY2014
Functionalized Porous Organic Polymers as Uranium Nano-Traps for Efficient Recovery of Uranium from Seawaterr	University of South Florida	$399,000	Researchers will develop functionalized porous organic polymers, or Ônano-trapsÕ for extraction of uranium from seawater. This technique allows for increased surface area and custom-designed pore size and chemistry to fit specific parameters. The adsorbent materials have high efficiency and effectiveness for uranium recovery from seawater, providing a potential supply for nuclear fuel.	Document	FCR&D	FY2014
Enhanced Accident-Tolerant Fuel Performance and Reliability for Aggressive iPWR/SMR Operation	University of Tennessee	$799,967	To develop a process that evaluates operational and safety performance of reactor-and-fuel combinations by integrating whole-core 3D neutronics with MOOSE/BISON fuel performance assessments via explicit time and space dependent fuel rod operational power histories. The project will be valuable in analyzing and evaluating accident tolerant fuel concepts and furthering the understanding of reactor physics and fuel performance aspects of key accident tolerant fuel concepts.	Document	FCR&D	FY2014
Nuclear Technology R&D Strategies in an Era of Energy Price Uncertainty	University of Texas, Austin	$799,112	Researchers will identify nuclear technology options that are competitive over a wide range of plausible future business environments. No single nuclear technology or business practice will be the best choice across all or even most future conditions. The study will focus on hybrid nuclear-fossil technologies, energy storage and conversion, which will result in an identification of nuclear strategies that can succeed under future market conditions.	Document	FCR&D	FY2014
Development and Optimization of Voltammetric Methods for Real Time Analysis of Electrorefiner Salt with High Concentrations of Actinides and Fission Products	University of Utah	$621,612	Researchers will develop an advanced voltammetry method to pursue the objective of real time monitoring of actinide concentrations in electrorefiner salt. This will include experimental measurement of key parameters such as activity coefficients and exchange current density. It will also involve simulation of voltammetry processes based on first principles. The project will allow for real time measurements that could support the commercialization of pyroprocessing.	Document	FCR&D	FY2014
Development of Self-Healing Zirconium-Silicide Coatings for Improved Performance of Zirconium-Alloy Fuel Cladding	University of Wisconsin, Madison	$798,621	Researchers will study the deposition of self-healing zirconium-silicide coatings on zirconium-alloy fuel cladding material to improve corrosion resistance under normal and accident conditions. Under these conditions, Zr-Si coating evolves into a highly protective functionally-graded multilayered system. The study will lead to improved performance of zirconium-alloy fuels._	Document	FCR&D	FY2014
Thermal Conductivity in Metallic Fuels	Virginia Polytechnic Institute and State University	$799,837	Researchers will calculate the thermal conductivity of metallic uranium and neptunium alloys, including the effects of noble gasses, using density functional theory. The experiments will validate the calculated effective thermal conductivity using the MARMOT code and by helping determine DFT simulation parameters. The study works to improve fuel lifetime by understanding its thermal behavior.	Document	FCR&D	FY2014
SiC-ODS Alloy Gradient Nanocomposites as Novel Cladding Materials	Virginia Polytechnic Institute and State University	$799,998	Researchers will combine nuclear nanomaterial design, processing, testing, and characterization efforts to develop revolutionary materials that can withstand neutron irradiation for long period of time using nanostructured SiC and oxide dispersion strengthened steel. The ultimate objective is to offer new cladding materials with increased corrosion resistance, strength, and creep resistance in both steady state and accident conditions.	Document	FCR&D	FY2014
Experimental Breeder Reactor II Benchmark Evaluation	Idaho State University	$400,000	Researchers will develop a benchmark evaluation of the Experimental Breeder Reactor II (EBR-II). During nearly 30 years of operation numerous experiments were conducted at EBR-II. The most significant of these experiments were conducted in 1986 demonstrating inherent safety features in loss of flow without reactor scram and loss of heat sink without reactor scram. Benchmark evaluation will be valuable for the reactor design efforts in the United States and South Korea.	Document	MSNE	FY2014
Integral full core multi-physics PWR benchmark with measured data	Massachusetts Institute of Technology	$400,000	Researchers will introduce BEAVRS, a new multi-cycle full-core Pressurized Water Reactor (PWR) depletion benchmark based on two operational cycles of a commercial nuclear power plant. This project aims at addressing the uncertainty quantification of the measured data and on making this benchmark a true non-proprietary international benchmark for the validation of high-fidelity multi-physics computational tools.	Document	MSNE	FY2014
Benchmark Evaluation of PROTEUS Gas-Cooled Reactor Experiments	University of Florida	$400,000	Researchers will create International Reactor Physics Experiment Evaluation Project (IRPhEP) benchmarks using data from 1970s experiments of the neutronics of gas-cooled fast reactor (GCFR) designs investigated in the PROTEUS reactor. The GCFR-PROTEUS experiments fill a gap in current integral benchmark data. These experiments can provide validation of computational models and nuclear data for next generation reactors.	Document	MSNE	FY2014
An Investigation To Establish Multiphysical Property Dataset Of Nuclear Materials Based On In-Situ Observations And Measurements	Purdue University	$800,000	Researchers will create an in-situ measurement based experimental approach to develop experimental validation dataset for NEAMS based code validation. Particular emphasis is on supplying data set for multiphysics simulations in extreme conditions as a function of material microstructure.	Document	NEAMS	FY2014
Experimental Validation of UO2 Microstructural Evolutions for NEAMS tool MARMOT	University of Florida	$798,000	Researchers will experimentally validate MARMOT for predicting the microstructural evolutions of UO2 oxide fuel under the driving forces of high temperatures and large temperature gradient in reactors. By performing the experiments and simulations simultaneously using precisely defined initial conditions, the experiment data will provide direct benchmarking of the MARMOT code.	Document	NEAMS	FY2014
High-resolution time-resolved experiments on mixing and entrainment of buoyant jets in stratified environments	University of Michigan	$799,983	Researchers will study high spatial and time-resolution experimental data of the fluid dynamics phenomena of flow jets interacting with a stratified layer. The issue plays an important role in the safety of several reactor designs, including sodium-cooled reactors. The data addresses the NEAMS needs for the validation of high fidelity computational fluid dynamics methodologies.	Document	NEAMS	FY2014
Fundamental study of key issues related to advanced S-CO2 Brayton Cycle: prototypic HX development and Cavitation	Georgia Institute of Technology	$799,000	Researchers will study scientific and operational issues pertinent to compact heat exchanger systems and turbo-machinery. The project will work to resolve issues with the fabrication of diffusion bonded compact heat exchangers, alternate heat exchange technology for recuperators, and resolution of issues with cavitation and fluid instabilities.	Document	RCRD&D	FY2014
Advanced Models for Nondestructive Evaluation of Aging Nuclear Power Plant Cables	Iowa State University	$787,291	Researchers will develop advanced models that relate environmentally induced microstructural and chemical changes in cable insulation polymers to their macroscopic electrical parameters. These parameters will be measured and modeled over a wide range of the electromagnetic spectrum, covering several potential nondestructive evaluation techniques, enabling identification of the most sensitive techniques for future development.	Document	RCRD&D	FY2014
Development of Novel Functionally Graded Transition Joints for Improving the Creep Strength of Dissimilar Metal Welds in Nuclear Applications	Lehigh University	$800,000	Researchers will develop graded transition joints and improved creep life models for increasing the life of dissimilar metal welds (DMWs) in nuclear reactors. The research represents the first application of functionally graded material concepts for solving the problem of DMW failures through an integrated approach of additive manufacturing, modeling, microstructural characterization, and advanced strain-sensing techniques.	Document	RCRD&D	FY2014
Feasibility Assessment of a Micro Modular Reactor (MMR)	North Carolina State University	$400,000	Researchers will develop an innovative compact reactor concept that integrates power production, power conversion and electricity generation in a single unit: the Micro Modular Reactor (MMR). It is designed to be absolutely melt-down proof (MDP) under all circumstances including complete loss of coolant scenarios with no possible release of radioactive material, to have a cycle length of greater than 10 years, and to be highly proliferation resistant.	Document	RCRD&D	FY2014
Scaling Studies for Advanced Gas Reactor Concepts	Oregon State University	$681,834	Researchers will expand the utilization of the Oregon State University High Temperature Test Facility (HTTF) to validate a broader range of advanced high temperature reactors and events. The facility will be revised to add a detailed scaling analysis of additional gas reactor concepts including advanced gas-cooled, molten salt, and sodium cooled reactors.	Document	RCRD&D	FY2014
Fluid Stratification Separate Effects Analysis, Testing and Benchmarking	Oregon State University	$800,000	Researchers will study fluid stratification in high temperature gas reactors. Coolant stratification is the result of incomplete mixing of one or more fluids, leading to a density gradient, which may or may not dissipate under diffusive or convective effects. This combined analytical and experimental project seeks to investigate stratification driven by diffusive and convective mechanisms and is expected to yield insight into this phenomenon.	Document	RCRD&D	FY2014
Probabilistic Economic Valuation of Safety Margin Management Analysis	Oregon State University	$795,364	Researchers will use RAVEN and develop a companion software package to facilitate economic analysis of safety margins. The project is a proof of concept that will use techniques to examine the cost of improving safety margins vs. the risk of accidents from not improving safety margins. This analysis can be used to evaluate the economic viability of various plant upgrades.	Document	RCRD&D	FY2014
Novel Dissimilar Joints Between Alloy 800H and 2.25%Cr and 1%Mo Steel	Pennsylvania State University	$800,000	Researchers will fabricate and test dissimilar metal joints between a nickel base alloy and a steel with gradual variations of chemical composition, microstructure and properties in a manner that reduces abrupt thermal expansion mismatch and the resulting residual stresses. Data on structure and properties will serve as valuable inputs for the initiation of an ASME code case.	Document	RCRD&D	FY2014
Multi-Phase Model Development to Assess RCIC System Capabilities under Severe Accident Conditions	Texas A&M University	$564,246	Researchers will develop physics-based models of the Reactor Core Isolation Cooling (RCIC) System and incorporating them into a multi-phase code for validation. The project will tackle the current major challenges in RCIC System analysis and enable evaluation of two-phase thermodynamic aspects.	Document	RCRD&D	FY2014
Experimental Investigation and CFD Analysis of Steam Ingress Accidents in HTGRs	The Ohio State University	$800,000	Researchers will study the steam ingress scenario for HTGRs. The study will investigate thermal-hydraulic behavior and graphite oxidation of stream ingress phenomena to validate predictive CFD models. This work will resolve concerns about possible steam generator tube ruptures in a HTGR He-Steam Rankine cycle.	Document	RCRD&D	FY2014
Coiled Tube Gas Heaters For Nuclear Gas-Brayton Power Conversion	University of California, Berkeley	$800,000	Researchers will develop heat exchangers for Brayton-cycle power conversion in reactors using sodium, NaK, or salt as intermediate coolants. The proposed coiled tube gas heaters (CTGHs) are expected to have excellent power density, thermal shock/creep, in-service inspection, and reparability characteristics.	Document	RCRD&D	FY2014
Fundamental Studies of Irradiation-Induced Modifications in Microstructural Evolution and Mechanical Properties of Advanced Alloys	University of Illinois, Urbana-Champaign	$800,000	Researchers will develop and test a mechanism for predicting neutron irradiation performance for optimized Grade 92 and Alloy 709 for applications in advanced reactor systems. The work will employ ion irradiations and available information from neutron irradiations of related alloys to develop a basis for predicting the neutron irradiation performance of the optimized alloys.	Document	RCRD&D	FY2014
Integrated Computational and Experimental Study of Radiation Damage Effects in Grade 92 Steel and Alloy 709	University of Tennessee	$800,000	Researchers will develop a mechanistic understanding and predictive models of irradiation-induced microstructural evolution and resulting mechanical properties in optimized ferritic-martensitic Grade 92 steel and austenitic alloy 709 using multiscale simulations coupled with rigorous experimental validation. The project will provide insights into the correlation between ion irradiation and fast neutron damage.	Document	RCRD&D	FY2014
Meta-Level Design Guidance and Operator Performance Measures for Hybrid Control Rooms	Vanderbilt University	$799,869	Researchers will apply human factors engineering methods and relevant expertise from non-nuclear high-risk high-consequence domains toward the measurement of operator performance in analog, digital, and hybrid main control rooms. Performance measures will be developed for evaluating the situation awareness and decision-making proficiencies to support the transition to digital or hybrid control room displays.	Document	RCRD&D	FY2014

FY 2022 Research and Development Awards

DOE is awarding more than $24.3 million through NEUP to support thirty-eight university-led nuclear energy research and development projects in twenty-one states. NEUP seeks to maintain U.S. leadership in nuclear research across the country by providing top science and engineering faculty and their students with opportunities to develop innovative technologies and solutions for civil nuclear capabilities.

A complete list of R&D projects with their associated abstracts is available below.

Title	Institution	Estimated Funding*	Project Description	Abstract	Project Type	Fiscal Year
Neutron Damage and MAX Phase Ternary Compounds	Drexel University			Document	IIR	FY2009
Atomistic Calculations of the Effect of Minor Actinides on Thermodynamic and Kinetic Properties of UO2+x	Georgia Institute of Technology			Document	IIR	FY2009
Maximum Fuel Utilization in Fast Reactors without Chemical Reprocessing	University of California, Berkeley			Document	IIR	FY2009
Developing a High Thermal Conductivity Fuel with Silicon Carbide Additives	University of Florida			Document	IIR	FY2009
Fabrication of Tungsten-Rhenium Cladding Materials via Spark Plasma Sintering for Ultra High Temperature Reactor Applications	University of Idaho			Document	IIR	FY2009
Ionic Liquid and Supercritical Fluid Hyphenated Techniques for Dissolution and Separation of Lanthanides, Actinides, and Fission Products	University of Idaho			Document	IIR	FY2009
Improved Fission Neutron Data Base for Active Interrogation of Actinides	University of Michigan			Document	IIR	FY2009
Utilization of Methacrylates and Polymer Matrices for the Synthesis of Ion Specific Resins	University of Nevada, Las Vegas			Document	IIR	FY2009
Improved LWR Cladding Performance by EPD Surface Modification Technique	University of Wisconsin, Madison			Document	IIR	FY2009
Advanced Models of LWR Pressure Vessel Embrittlement for Low Flux-High Fluence Conditions	University of California, Santa Barbara			Document	LWRS	FY2009
Irradiation Creep in Graphite	Boise State University			Document	NGNP	FY2009
Modeling the Stress Strain Relationships and Predicting Failure Probabilities For Graphite Core Components	Cleveland State University			Document	NGNP	FY2009
TRISO-Coated Fuel Durability Under Extreme Conditions	Colorado School of Mines			Document	NGNP	FY2009
An Innovative and Advanced Coupled Neutron Transport and Thermal Hydraulic Method (Tool) for the Design, Analysis and Optimization of VHTR/NGNP Prismatic Reactors	Georgia Institute of Technology			Document	NGNP	FY2009
Removal of 14C from Irradiated Graphite for Graphite Recycle and Waste Volume Reduction	Idaho State University			Document	NGNP	FY2009
Millimeter-Wave Thermal Analysis Development and Application to Gen IV Reactor Materials	Massachusetts Institute of Technology			Document	NGNP	FY2009
Accurate Development of Thermal Neutron Scattering Cross Section Libraries	North Carolina State University			Document	NGNP	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
Understanding Creep Mechanisms in Graphite with Experiments, Multiscale Simulations, and Modeling	North Carolina State University			Document	NGNP	FY2009
Simulations of the Thermodynamic and Diffusion Properties of Actinide Oxide Fuel Materials	University of Michigan			Document	AFCI	FY2009
Verification & Validation of High-Order Short-Characteristics-Based Deterministic Transport Methodology on Unstructured Grids	North Carolina State University			Document	NGNP	FY2009
Adsorptive Separation and Sequestration of Krypton, I and C14 on Diamond Nanoparticles	University of Missouri, Columbia			Document	AFCI	FY2009
Microscale Heat Conduction Models and Doppler Feedback	North Carolina State University			Document	NGNP	FY2009
Fundamental Understanding of Ambient and High-Temperature Plasticity Phenomena in Structural Materials in Advanced Reactors	Georgia Institute of Technology			Document	AFCI	FY2009
Development of Alternative Technetium Waste Forms	University of Nevada, Las Vegas			Document	AFCI	FY2009
Optimizing Neutron Thermal Scattering Effects in Very High Temperature Reactors	North Carolina State University			Document	NGNP	FY2009
Advanced Elastic/Inelastic Nuclear Data Development Project	Idaho State University			Document	AFCI	FY2009
Heterogeneous Recycling in Fast Reactors	Massachusetts Institute of Technology			Document	AFCI	FY2009
Quantification of UV-Visible and Laser Spectroscopic Techniques for Materials Accountability and Process Control	University of Nevada, Las Vegas			Document	AFCI	FY2009
Multiaxial Creep-Fatigue and CreepRatcheting Failures of Grade 91 and Haynes 230 Alloys Toward Addressing Design Issues of Gen IV Nuclear Power Plants	North Carolina State University			Document	NGNP	FY2009
Thermodynamic Development of Corrosion Rate Modeling in Iron Phosphate Glasses	Missouri University of Science and Technology			Document	AFCI	FY2009
Development of Subspace-Based Hybrid Monte Carlo-Deterministic Algorithms for Reactor Physics Calculations	North Carolina State University			Document	AFCI	FY2009
High-Fidelity Space-Time Adaptive Multiphysics Simulations in Nuclear Engineering	University of Nevada, Reno			Document	AFCI	FY2009
Improvements to Nuclear Data and Its Uncertainties by Theoretical Modeling	Rensselaer Polytechnic Institute			Document	AFCI	FY2009
Investigation of Countercurrent Helium-air Flows in Air-ingress Accidents for VHTRs	Ohio State University			Document	NGNP	FY2009
Sharp Interface Tracking in Rotating Microflows of Solvent Extraction	State University of New York at Stony Brook			Document	AFCI	FY2009
Bulk Nanostructured FCC Steels with Enhanced Radiation Tolerance	Texas A&M University			Document	AFCI	FY2009
Simulations of Failure via Three-Dimensional Cracking in Fuel Cladding for Advanced Nuclear Fuels	University of Texas, Dallas			Document	AFCI	FY2009
Testing of Performance of Optical Fibers Under Irradiation in Intense Radiation Fields, When Subjected to Very High Temperatures	Ohio State University			Document	NGNP	FY2009
Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels	Texas A&M University			Document	AFCI	FY2009
SiC Schottky Diode Detectors for Measurement of Actinide Concentrations from Alpha Activities in Molten Salt Electrolyte	The Ohio State University			Document	AFCI	FY2009
Computational Design of Advanced Nuclear Fuels	University of California, Davis			Document	AFCI	FY2009
Advanced Mesh-Enabled Monte Carlo Capability for Multi-Physics Reactor Analysis	University of Wisconsin, Madison			Document	AFCI	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
A Distributed Fiber Optic Sensor Network for Online 3-D Temperature and Neutron Fluence Mapping in a VHTR Environment	Texas A&M University			Document	NGNP	FY2009
Ab Initio Enhanced Calphad Modeling of Actinide Rich Nuclear Fuels	University of Wisconsin, Madison			Document	AFCI	FY2009
Investigation on the Core Bypass Flow in a Very High Temperature Reactor	Texas A&M University			Document	NGNP	FY2009
Development of Diffusion Barrier Coatings and Deposition Technologies for Mitigating Fuel Cladding Chemical Interactions (FCCI)	University of Wisconsin, Madison			Document	AFCI	FY2009
CFD Model Development and Validation for High Temperature Gas Cooled Reactor Cavity Cooling System (RCCS) Applications	Texas A&M University			Document	NGNP	FY2009
Thermal Properties of LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin, Madison			Document	AFCI	FY2009
Study of Air ingress across the duct during the accident conditions	Texas A&M University			Document	NGNP	FY2009
Verification of the CENTRM Module for Adaptation of the SCALE Code to NGNP Prismatic and PBR Core Designs	University of Arizona			Document	NGNP	FY2009
Integral and Separate Effects Tests for Thermal Hydraulics Code Validation for Liquid-Salt Cooled Nuclear Reactors	University of California, Berkeley			Document	NGNP	FY2009
Mechanisms Governing the Creep Behavior of High Temperature Alloys for Generation IV Nuclear Energy Systems	University of Cincinnati			Document	NGNP	FY2009
ALD Produced B2O3, Al2O3 and TiO2 Coatings on Gd2O3 Burnable Poison Nanoparticles	University of Colorado, Boulder			Document	NGNP	FY2009
Experimental Study and Computational Simulations of Key Pebble Bed Thermomechanics Issues for Design and Safety	University of Idaho			Document	NGNP	FY2009
Prediction and Monitoring Systems of Creep-Fracture Behavior of 9Cr-1Mo Steels for Reactor Pressure Vessels	University of Idaho			Document	NGNP	FY2009
Understanding Fundamental Material Degradation Processes in High Temperature Aggressive Chemomechanical Environments	University of Illinois, Urbana-Champaign			Document	NGNP	FY2009
Multi-Scale Multi-physics Methods Development for the Calculation of Hot-Spots in the NGNP	University of Michigan			Document	NGNP	FY2009
Corrosion and Creep of Candidate Alloys in High Temperature Helium and Steam Environments for the NGNP	University of Michigan			Document	NGNP	FY2009
Creation of a Full-Core HTR Benchmark with the Fort St. Vrain Initial Core and Validation of the DHF Method with Helios for NGNP Configurations	University of Michigan			Document	NGNP	FY2009
Fission Product Sorptivity in Graphite	University of Missouri, Columbia			Document	NGNP	FY2009
Identifying and Understanding Environment-Induced Crack Propagation Behavior in Ni-Based Superalloy INCONEL 617	University of Nevada, Las Vegas			Document	NGNP	FY2009
Graphite Oxidation Simulation in HTR Accident Conditions	University of New Mexico			Document	NGNP	FY2009
Non Destructive Thermal Analysis and In Situ Investigation of Creep Mechanism of Graphite and Ceramic Composites using Phase-sensitive THz Imaging & Nonlinear Resonant Ultrasonic Spectroscopy	University of Rochester			Document	NGNP	FY2009
Tritium Sequestration in Gen IV NGNP Gas Stream via Proton Conducting Ceramic Pumps	University of South Carolina			Document	NGNP	FY2009
Materials, Turbomachinery and Heat Exchangers for Supercritical CO2 Systems	University of Wisconsin, Madison			Document	NGNP	FY2009
Experimental Studies of NGNP Reactor Cavity Cooling System with Water	University of Wisconsin, Madison			Document	NGNP	FY2009
Assessment of Embrittlement of VHTR Structural Alloys in Impure Helium Environments	University of Wisconsin, Madison			Document	NGNP	FY2009
Modeling Fission Product Sorption in Graphite Structures	University of Wisconsin, Madison			Document	NGNP	FY2009
Liquid Salt Heat Exchanger Technology for VHTR Based Applications	University of Wisconsin, Madison			Document	NGNP	FY2009
Effect of Post-Weld Heat Treatment on Creep Rupture Properties of Grade 91 Steel Heavy Section Welds	Utah State University			Document	NGNP	FY2009
Alpha Radiolysis of Nuclear Solvent Extraction Ligands used for An(III) and Ln(III) Separations	California State University, Long Beach	$1,390,252		Document	FCR&D	FY2010
Predictive Maturity of Multi-Scale Simulation Models for Fuel Performance	Clemson University	$614,690		Document	FCR&D	FY2010
Freeze-casting as a Novel Manufacturing Process for Fast Reactor Fuels	Drexel University	$1,149,327		Document	FCR&D	FY2010
Fuel Performance Experiments on the Atomistic Level, Studying Fuel Through Engineered Single Crystal UO2	Idaho State University	$650,000		Document	FCR&D	FY2010
Development of A Self Biased High Efficiency Solid-State Neutron Detector for MPACT Applications	Rensselaer Polytechnic Institute	$810,141		Document	FCR&D	FY2010
Development of a Innovative High Thermal Conductivity UO 2 Ceramic Composites Fuel Pellets with Carbon Nano-Tubes Using Spark Plasma Sintering	University of Florida	$894,042		Document	FCR&D	FY2010
Exploration and Modeling of Structural Changes in Waste Glass under Corrosion	Pennsylvania State University	$1,377,444		Document	FCR&D	FY2010
Evaluation of materials for interim storage of spent fuel for more than 100 years	University of Michigan	$931,603		Document	FCR&D	FY2010
Implementation of On-the-Fly Doppler Broadening in MCNP5 for Multiphysics Simulation of Nuclear Reactors	University of Michigan	$406,712		Document	FCR&D	FY2010
Methods and tools to allow molecular flow simulations to be coupled to higher level continuum descriptions of flows in porous/fractured media and aerosol/dust dynamics	University of Missouri-Columbi	$541,286		Document	FCR&D	FY2010
Characterization and Modeling of Materials for Kr-Xe Separations	University of Nevada-Las Vegas	$989,800		Document	FCR&D	FY2010
Modeling Solute Thermokinetics in LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin-Madison	$616,073		Document	FCR&D	FY2010
Advanced Aqueous Separation Systems for Actinide Partitioning: Develop Fundamental Understanding of An(III)/Ln(III) Separation	Washington State University	$1,451,784		Document	FCR&D	FY2010
Consistent Multigroup Theory Enabling Accurate Coarse-Group Simulation of GenIV Reactors	Georgia Institute of Technology	$1,046,277		Document	GEN IV	FY2010
Studies of Deteriorated Heat Transfer in Prismatic Cores Stemming from Irradiation-Induced Geometry Distortion	Idaho State University	$1,287,921		Document	GEN IV	FY2010
Carbide Coatings for Nickel Alloys, Graphite, and Carbon/Carbon Composites to be Used in Fluoride Salt Valves	Johns Hopkins University	$1,183,239		Document	GEN IV	FY2010
Design, Testing, and Modeling of the Direct Reactor Auxiliary Cooling System for AHTRs	Ohio State University	$1,366,627		Document	GEN IV	FY2010
Monitoring microstructural evolution of Alloy 617 with nonlinear acoustics for remaining useful life prediction; multiaxial creep-fatigue and creep-ratcheting	Pennsylvania State University	$1,000,000		Document	GEN IV	FY2010
Development and Validation of Multidimensional Models of Supercritical CO 2 Energy Conversion Systems for Nuclear Power Reactors	Rensselaer Polytechnic Institute	$475,005		Document	GEN IV	FY2010
Multiscale Concrete Modeling for Aging Degradation	Mississippi State University	$345,941		Document	LWRS	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term and Elevated Temperature Irradiation: Modeling and Experimental Investigation	University of California-Berkeley	$1,320,667		Document	GEN IV	FY2010
Development of an advanced computational fluid dynamics technology for the next-generation nuclear reactor system analysis and safety margin characterization code	North Carolina State University	$418,199		Document	LWRS	FY2010
Development of Barrier Layers for the Protection of Candidate Alloys in the VHTR	University of California-Santa Barbara	$995,232		Document	GEN IV	FY2010
Precursor Derived Nanostructured Si-C-X Materials for Nuclear Applications	University of Washington	$899,518		Document	MRIIR	FY2010
Investigation of a Novel NDE Method for Monitoring Thermo-Mechanical Damage and Microstructure Evolution in Ferritic-Martensitic Steels for Generation IV Nuclear Energy Systems	University of Cincinnati	$833,109		Document	GEN IV	FY2010
Development and Testing of an Open-Loop Oscillator for Small Reactivity Worth Samples	Idaho State University	$597,252		Document	MRIIR	FY2010
Fission Product Transport in TRISO Particle Layers under Operating and Off-Normal Conditions	University of Michigan	$966,581		Document	GEN IV	FY2010
Understanding the Irradiation Behavior of Zirconium Carbide	Pennsylvania State University	$870,613		Document	MRIIR	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term Irradiation at Elevated Temperature: Critical Experiments	University of Michigan	$1,181,379		Document	GEN IV	FY2010
Modeling investigation of the stability and irradiation-induced evolution of nanoscale precipitates in advanced structural materials	University of Tennessee-Knoxville	$380,653		Document	MRIIR	FY2010
Three-dimensional NDE of VHTR Core Components via Simulation-based Testing	University of Minnesota	$1,366,163		Document	GEN IV	FY2010
Investigation of Laser Shock Peening for Enhancing Fatigue and Stress Corrosion Cracking Resistance of Nuclear Energy Materials	University of Cincinnati	$1,242,019		Document	MRIIR	FY2010
Failure Predictions for VHTR Core Components using a Probabilistic Continuum Damage Mechanics Model	University of Minnesota	$854,542		Document	GEN IV	FY2010
Irradiation Accelerated Corrosion of Reactor Core Materials	University of Michigan	$798,943		Document	MRIIR	FY2010
Development of a Scanning Microscale Fast Neutron Irradiation Platform for Examining the Correlation Between Local Neutron Damage and Graphite Microstructure	University of Missouri-Columbia	$703,064		Document	GEN IV	FY2010
Study of Interfacial Interactions using Thin Film Surface Modification: Radiation and Oxidation Effects in Materials	University of Wisconsin-Madison	$538,032		Document	MRIIR	FY2010
Development of Thermal Transient Flow Rate Sensors for High Temperature, Irradiation, Corrosive Environment	University of Nevada-Las Vegas	$451,269		Document	GEN IV	FY2010
Novel Engineered Refractory Materials for Advanced Reactor Applications	North Carolina State University	$1,129,304		Document	MRIIR	FY2010
Novel Methods of Tritium Sequestration: High Temperature Gettering and Separation Membrane Materials Discovery for Nuclear Energy Systems	University of South Carolina	$1,366,626		Document	GEN IV	FY2010
Heat Transfer Salts for Nuclear Reactor Systems - Chemistry Control, Corrosion Mitigation, and Modeling	University of Wisconsin-Madison	$1,352,040		Document	GEN IV	FY2010
Pulsed Magnetic Welding for Advanced Core and Cladding Steels	University of Wisconsin-Madison	$525,206		Document	GEN IV	FY2010
Corrosion in Supercritical Carbon Dioxide: Materials, Environmental Purity, Surface Treatments, and Flow Issues	University of Wisconsin-Madison	$651,447		Document	GEN IV	FY2010
Quantification of Cation Sorption to Engineered Barrier Materials Under Extreme Conditions	Clemson University	$1,171,380		Document	FCR&D	FY2011
In-Pile Instrumentation Multi-Parameter System Utilizing Photonic Fibers and Nanovision	Idaho State University	$1,199,990		Document	FCR&D	FY2011
Development of Plasmonically Cloaked Nanoparticles	Idaho State University	$800,000		Document	FCR&D	FY2011
Fission Product Transmutation in Mixed Radiation Fields	Idaho State University	$800,000		Document	FCR&D	FY2011
Life Prediction of Spent Fuel Storage Canister Material	Massachusetts Institute of Technology	$899,826		Document	FCR&D	FY2011
Active Interrogation using Photofission Technique for Nuclear Materials Control and Accountability	Oregon State University	$900,000		Document	FCR&D	FY2011
Anisotropic Azimuthal Power and Temperature Distribution on Fuel Rod: Impact of Hydride Distribution	Pennsylvania State University	$631,956		Document	FCR&D	FY2011
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$1,000,000		Document	FCR&D	FY2011
Recovery of Uranium from Seawater: Preparation and Development of Polymer-Supported Extractants	City College of New York, Hunter	$363,716		Document	MSTR	FY2011
Microemulsions and Aggregation Formation in Extraction Processes for Used Nuclear Fuel: Thermodynamics and Structural Studies	University of California, Irvine	$1,000,000		Document	FCR&D	FY2011
One-Dimensional Nanostructures for Neutron Detection	North Carolina State University	$455,629		Document	MSTR	FY2011
Optimized Processing Fabrication Paths for Larger Heats of Nanostructured Ferritic Alloys	University of California, Santa Barbara	$1,000,000		Document	FCR&D	FY2011
Feasibility and Safety Assessment for Advanced Reactor Concepts Using Vented Fuel	Oregon State University	$600,000		Document	MSTR	FY2011
Basic Physics Data: Measurement of Neutron Multiplicity from Induced Fission	University of Michigan	$973,364		Document	FCR&D	FY2011
Development of an Efficient Meso-Scale Multi-Phase Flow Solver in Nuclear Applications	City College of New York	$505,858		Document	NEAMS	FY2011
High Temperature Transducers for Online Monitoring of Microstructure Evolution	Pennsylvania State University	$455,628		Document	MSTR	FY2011
Radionuclide Incorporation and Long Term Performance of Apatite Waste Forms	University of Michigan	$862,500		Document	FCR&D	FY2011
Multiscale Modeling and Uncertainty Quantification for Nuclear Fuel Performance	Colorado State University	$1,098,250		Document	NEAMS	FY2011
Laser-Arc Hybrid Welding of Thick Section Ni-base Alloys- Advanced Modeling and Experiments	Pennsylvania State University	$536,117		Document	MSTR	FY2011
Actinide Foil Production for MPACT Research	University of Nevada-Las Vegas	$156,897		Document	FCR&D	FY2011
Fundamental Studies of the Role of Grain Boundaries on Uniform Corrosion of Advanced Nuclear Reactor Materials	Drexel University	$1,098,250		Document	NEAMS	FY2011
Correlates of Sensitive Technologies	Texas A&M University	$509,467		Document	MSTR	FY2011
Enriched Boron-Doped Amorphous Selenium Based Position-Sensitive Solid-State Thermal Neutron Detector for MPACT Applications	University of South Carolina	$1,000,000		Document	FCR&D	FY2011
Phenomena-based Uncertainty Quantification in Predictive Coupled-Physics Reactor Simulations	Texas A&M University	$1,098,250		Document	NEAMS	FY2011
Improved Safety Margin Characterization of Risk from Loss of Offsite Power	Texas A&M University	$600,000		Document	MSTR	FY2011
Development of Advanced High Uranium Density Fuels for Light Water Reactors	University of Wisconsin-Madison	$1,000,000		Document	FCR&D	FY2011
Characterization of Modeling of Grain Boundary Chemistry Evolution in Ferritic Steels Under Irradiation	University of Michigan	$1,098,250		Document	NEAMS	FY2011
Diffusion, Thermal Properties and chemical Compatibilities of Select MAX Phases with Materials for Advanced Nuclear Systems	Drexel University	$535,927		Document	NEET	FY2011
A High Temperature-Tolerant and Radiation-Resistant In-Core Neutron Sensor for Advanced Reactors	The Ohio State University	$455,629		Document	MSTR	FY2011
Developing the User Experience for a Next Generation Nuclear Fuel Cycle Simulator	University of Wisconsin-Madison	$1,200,000		Document	FCR&D	FY2011
Development of Multiscale Materials Modeling Techniques and Coarse-Graining Strategies for Predicting Materials Degradation in Extreme Irradiation Environments	University of Tennessee, Knoxville	$750,000		Document	NEAMS	FY2011
A New Light Weight Structural Material for Nuclear Structures	North Carolina State University	$399,490		Document	NEET	FY2011
Pathway Aggregation in the Risk Assessment of Proliferation Resistance and Physical Protection (PR&PP) of Nuclear Energy Systems	The Ohio State University	$534,471		Document	MSTR	FY2011
Experimental Investigation of Convection and Heat Transfer in the Reactor Core for a VHTR	City College of New York	$1,118,856		Document	RCRD&D	FY2011
Preparation of High Purity, High Molecular-Weight Chitin from Ionic Liquids for Use as an Adsorbate for the Extraction of Uranium from Seawater	University of Alabama	$338,260		Document	MSTR	FY2011
Graphite Microstructural Characterization Using Time-Domain and Correlation-Based Ultrasonics	Johns Hopkins University	$1,199,997		Document	RCRD&D	FY2011
Selectivity in Ligand Binding to Uranyl Compounds: A Synthetic, Structural, Thermodynamic and Computational Study	University of California-Berkeley	$500,000		Document	MSTR	FY2011
Methodology Development for Passive Component Reliability Modeling in a Multi-Physics Simulation Environment	The Ohio State University	$533,457		Document	RCRD&D	FY2011
Development of Seismic Isolation Systems Using Periodic Materials	University of Houston	$538,154		Document	MSTR	FY2011
Pebble Fuel Handling and Reactivity Control for Salt-Cooled High Temperature Reactors	University of California, Berkeley	$612,721		Document	RCRD&D	FY2011
Innovative Elution Processes for Recovering Uranium from Seawater	University of Idaho	$400,000		Document	MSTR	FY2011
Self-Sustaining Thorium Boiling Water Reactors	University of California, Berkeley	$1,145,932		Document	RCRD&D	FY2011
Development of Austenitic ODS Strengthened Alloys for Very High Temperature Applications	University of Illinois-Urbana Champaign	$538,154		Document	MSTR	FY2011
High Fluency Low Flux Embrittlement Models of LWR Reactor Pressure Vessel Embrittlement and a Supporting Database from the UCSB ATR-2 Irradiation Experiment	University of California, Santa Barbara	$1,199,607		Document	RCRD&D	FY2011
Enhancement of the Extraction of the Uranium from Seawater	University of Maryland	$400,000		Document	MSTR	FY2011
A Research Program for Fission Product/Dust Transport in HTGR's	University of Missouri-Columbia	$1,157,367		Document	RCRD&D	FY2011
Transient Safety Analysis of Fast Spectrum TRU Burning LWR with Internal Blankets	University of Michigan	$599,475		Document	MSTR	FY2011
Development and Validation of a Lifecycle-based Prognostics Architecture with Test Bed Validation	University of Tennessee, Knoxville	$846,315		Document	RCRD&D	FY2011
Development of Novel Sorbents for Uranium Extraction from Seawater	University of North Carolina, Chapel Hill	$400,000		Document	MSTR	FY2011
In-situ Condition Monitoring of Components in Small Modular Reactors Using Process and Electrical Signature Analysis	University of Tennessee, Knoxville	$650,000		Document	RCRD&D	FY2011
Radiation Behavior of High-Entropy Alloys for Advanced Reactors	University of Tennessee, Knoxville	$538,159		Document	MSTR	FY2011
Technical Development for S-CO2 Advanced Energy Conversion	University of Wisconsin	$815,000		Document	RCRD&D	FY2011
Rapid Computer Aided Ligand Design and Screening of Precious Metal Extractants from TRUEX Raffinate with Experimental Validation	Washington State University	$500,000		Document	MSTR	FY2011
Ag Transport Through Non-Irradiated and Irradiated SiC	University of Wisconsin-Madison	$1,055,456		Document	RCRD&D	FY2011
Critical Heat Flux Phenomena at High Pressure and Low Mass Fluxes: Tests and Models	University of Wisconsin-Madison	$1,199,781		Document	RCRD&D	FY2011
Modeling and Test Validation of a Reactor Cavity Cooling System with Air	University of Wisconsin-Madison	$1,199,988		Document	RCRD&D	FY2011
Transient Mixed Convection Validation for NGNP	Utah State University	$635,860		Document	RCRD&D	FY2011
Alternative High-Performance Ceramic Waste Forms	Alfred University	$840,000	This project aims to advance fundamental understanding of the kinetics of structural evolution of crystalline ceramic waste forms. The structure/property relationships will be identified and will reveal new formulations, improved processing routes, and strategies for improved performance or ceramic waste forms.	Document	FCR&D	FY2012
Surface Layer Bulk Glass Interface Evolution with Aqueous Corrosion	Alfred University	$880,000	This project will investigate the links between the morphology, structure and chemistry of surface layer-bulk glass interface and the long-term corrosion-reaction kinetics using in-situ and ex-situ experiments. The understanding will result in improved models for long-term predictive behavior of high-level-waste (HLW) glasses under repository conditions.	Document	FCR&D	FY2012
Improved Accident Tolerance of Austenitic Stainless Steel Cladding through Colossal Supersaturation with Interstitial Solutes	Case Western Reserve University	$850,000	This project aims to develop new case-hardened austenitic stainless steels by saturating them with materials that improve their mechanical properties, corrosion resistance and radiation resistance. This project, if successful, will result in safer, longer-lasting, and more accident tolerant fuel claddings.	Document	FCR&D	FY2012
Optimization of Deep Borehole Systems for HLW Disposal	Massachusetts Institute of Technology	$850,000	Researchers aim to carry out a comprehensive evaluation of the deep borehole option for disposal of used nuclear fuel and high livel waste. The models developed will predict potential movement of water through natural and engineered barriers and release of radionuclides to the biosphere which will aide in site selection.	Document	FCR&D	FY2012
Scholarship for Nuclear Communications and Methods for Evaluation of Nuclear Project Acceptability	Massachusetts Institute of Technology	$800,000	Researchers will work to develop a model to characterize the factors affecting social acceptance of nuclear projects with potential stakeholders. The resultant model will strengthen the ability to design and implement large projects more efficiently, leading to higher rates of success of future nuclear projects.	Document	FCR&D	FY2012
Accurate Holdup Calculations with Predictive Modeling and Data Integration	North Carolina State University	$875,000	Researchers will develop and use state-of-the-art radiation transport codes to account accurately for the fissile material in a nuclear materials processing facility. An accurate estimation of the materials will allow for ensured radiological safety, security, waste management and efficient plant operation.	Document	FCR&D	FY2012
Novel Metal Sulfides to Achieve Effective Capture and Durable Consolidation of Radionuclides	Northwestern University	$760,000	Researchers will evaluate the effectiveness of chalcogenide based materials design novel metal sulfides to effectively capture and store of radioisotopes released during reprocessing of used nuclear fuel. This project will focus on understanding structure-property relationships to enable refined and direct synthesis approaches for improved and cost-efficient nuclear waste forms.	Document	FCR&D	FY2012
Nonlinear Ultrasonic Diagnosis and Prognosis of ASR Damage in Dry Cask Storage	Northwestern University	$885,000	Researchers aim to use nondestructive damage characterization methods to detect, manage and mitigate the degradation/damage mechanisms of dry cask storage systems for nuclear fuels. This project, if successful, will provide tools that will allow the prediction of the reliability and the safety of concrete structures in dry cask storage systems.	Document	FCR&D	FY2012
Prototype Demonstration of Gamma-Blind Tensioned Metastable Fluid Neutron/Multiplicity/Alpha Detector- Real Time Methods for Advanced Fuel Cycle Applications	Texas A&M University	$875,000	This project aims to create a prototype demonstration of a novel neutron/alpha detector based on a technology that is blind to gamma field used fuel. The prototype, if successful, will enhance instrumentation for monitoring real-time material balance during various stages of the nuclear cycle.	Document	FCR&D	FY2012
Testing of Sapphire Optical Fiber and Sensors in Intense Radiation Fields, when Subjected to Very High Temperatures	The Ohio State University	$885,000	The researchers on this project will investigate the performance of sapphire optical fibers and sensors in reactor environments. The project, if successful, will result in improved instrumentation to understand the behavior and predict performance of nuclear fuel systems at the microstructural level.	Document	FCR&D	FY2012
Concrete Materials with Ultra-High Damage Resistance and Self-Sensing Capacity for Extended Nuclear Fuel Storage Systems	University of California, Irvine	$800,000	Researchers aim to design a new class of multifunctional concrete materials. This project, if successful, will result in a novel multifunctional concrete material that possesses inherent degradation monitoring capability and is suitable for an extended storage system for the used nuclear fuel.	Document	FCR&D	FY2012
Development of Innovative Accident Tolerant High Thermal Conductivity UO2 Fuel Pellets with a Diamond Dopant	University of Florida	$800,000	Researchers will evaluate the use of diamond nanoparticles composite material in innovative accident tolerant fuel pellets. This could significantly improve both the thermal conductivity of fuel pellets and light water reactors' efficiency safety.	Document	FCR&D	FY2012
Probabilistic Multi-Hazard Assessment of Dry Cask Structures	University of Houston	$865,000	This project aims to investigate the performance of dry cask storage systems under multiple hazard systems (earthquake, tornados, combined with aging effects) using a probabilistic multi-hazard framework. This framework will be validated based on experimental research and will provide improved models for safety and reliability of spent nuclear fuels during storage and transportation.	Document	FCR&D	FY2012
Measurement of Irradiated Pyroprocessing Samples via Laser Induced Breakdown Spectroscopy	University of Idaho	$820,000	This project aims to use advanced characterization techniques to investigate microstructural changes and the micromechanisms related to irradiation induced damage in used nuclear fuels and waste forms. This project, if successful, will result in enhanced models to predict the structural and chemical response of used fuel and waster forms during interim storage and permanent disposal.	Document	FCR&D	FY2012
Elastic/Inelastic Measurement Project	University of Kentucky	$880,523	Researchers will measure nuclear data for elastic/inelastic scattered neutrons on coolants and structural materials. The data generated, will be useful for future R&D programs that will study innovative next generation LWR and future fast systems.	Document	FCR&D	FY2012
Electrochemical Corrosion Studies for Modeling Metallic Waste Form Release Rates	University of Nevada- Las Vegas	$790,000	This project aims to use advanced electrochemical methods to investigate the corrosion related degradation of metal alloys used for housing fission products. The data obtained from this study will allow for the prediction of the long-term behavior of the metallic host phase materials over geological time-scales.	Document	FCR&D	FY2012
Thermodynamic and Microstructural Mechanisms in the Corrosion of Advanced Ceramic Tc-bearing Waste Forms and Thermophysical Properties	University of Nevada- Las Vegas	$795,000	This project team will harvest thermodynamic and microstructural data on the evolution of ceramic based waste forms. The data will be used to advance the current state-of-the-art methodology used for isolation and stabilization of fission products and improve on nuclear fuel recycling processes.	Document	FCR&D	FY2012
Development and Experimental Benchmark of Simulations to Predict Used Nuclear Fuel Cladding Temperatures during Drying and Transfer Operations	University of Nevada- Reno	$745,000	Researchers will conduct experiments to investigate and develop advanced computational models of heat transfer in post-pool-storage drying operations. This project, if successful, will result in tools that can be used to design efficient drying processes to as to ensure suitability for dry-cask systems for long-term storage and transport.	Document	FCR&D	FY2012
Better Radiation Response and Accident Tolerance of Nanostructured Ceramic Fuel Materials?	University of Tennessee	$815,000	Researchers will use novel experimental methods to investigate the links between microstructure, phase stability and damage evolution in nanostructured ceramic fuel materials. The project will study fuel materials at temperatures and irradiation conditions relevant to operation and accidental scenarios.	Document	FCR&D	FY2012
Radiation and Thermal Effects on Used Nuclear Fuel and Nuclear Waste Forms	University of Tennesssee	$770,000	This project aims to investigate the structural and chemical response of used nuclear fuel and waste forms during interim storage and permanent disposal. If successful, this project will generate models that will allow the prediction of structural evolution and hence the radiological safety and security of nuclear fuel and waste forms.	Document	FCR&D	FY2012
Seismic Performance of Dry Casks Storage for Long-Term Exposure	University of Utah	$873,319	Researchers will evaluate the mechanical performance of dry-cask storage under seismic loading for mid-term operational periods. Simulations will include scenarios for freestanding, anchored, and vaulted casks. The experimental tests will also evaluate the dynamic seismic response of freestanding and anchored dry-cask storage prototypes, providing recommendations for optimal Interim Spent Fuel Storage Installations (ISFSIs) design.	Document	FCR&D	FY2012
Validation Experiments for Spent-Fuel Dry-Cask In-Basket Convection	Utah State University	$690,000	Researchers in this project aim to conduct experiments that generate data on natural convection through a fuel assembly. The data will be used to validate the computational models being developed for nuclear safety and design.	Document	FCR&D	FY2012
Re-Branding the Nuclear Fuel Cycle	Virginia Commonwealth University	$850,000	This project will create a comprehensive framework for the evaluation of alternative fuel cycle systems that will be used to identify and analyze key elements related to long-term management of nuclear fuels , with the ultimate goal to develop a communications strategy to reach stakeholders.	Document	FCR&D	FY2012
Advanced Characterization of Molecular Interactions in TALSPEAK-like Separations Systems	Washington State University	$875,000	Researchers will use advanced characterization techniques (experimental and computational) to improve understanding of the molecular level processes/interactions during separation processes for advanced fuel cycles. The understanding of these interactions will be used to develop more robust and streamlined separation processes for advanced fuel cycles.	Document	FCR&D	FY2012
Coupling of Nuclear Waste Form Corrosion and Radionuclide Transport in Presence of Relevant Repository Sediments	Washington State University	$885,000	Researchers will conduct experiments to understand the mechanisms responsible for the corrosion of nuclear waste forms in realistic chemical environments. The data generated from these experiments will enable increased reliability of the models used to predict the waste form performance in repository environments.	Document	FCR&D	FY2012
Stationary Liquid Fuel Fast Reactor (SLFFR) Concept for TRU Burning	Purdue University	$450,000	Reasearchers will investigate a new type of molten metallic fuel reactor concept that will consume hazardous transuranic waste. The liquid fuel alloy has several advantages over solid fuel fast reactors that are used for the same purpose.	Document	MSTR	FY2012
ABR for TRU Transmutation with Breed & Burn Thorium Blanket for Improved Economics and Resource Utilization	University of California- Berkeley	$450,000	The research team will use detailed neutronic analysis for a new Advanced Burner Reactor concept with low conversion ratio. The concept will use a new core shape to improve the utilization of neutrons to perform breed and burn.	Document	MSTR	FY2012
New Materials for High Temperature Thermoelecric Power Generation	University of California, Davis	$450,000	Reasearchers will work to develop nanostructured and other new materials to support the development of higher efficiency thermoelectric devices. These devices convert thermal energy to electricity with no moving parts. The new materials will operate at higher efficiencies and over a wider temperature range than those currently available--an important quality for future nuclear-powered deep space exploration.	Document	MSTR	FY2012
Microscopic Fuel Particles Produced by Self-Assembly of Actinide Nanoclusters on Carbon Nanomaterials	University of Notre Dame	$440,000	Reasearchers will develop the mechanisms, conditions and protocols to prepare uranium-carbon nanocomposite materials to make them more flexible. This could result in the generation of wholesale electricity, providing process heat, and providing power for households.	Document	MSTR	FY2012
High Hydrogen Content Graphene Hydride Compounds & High Cross-Section Cladding Coatings for Fast Neutron Detection	University of South Carolina	$430,000	This project will exploit recent breakthroughs to grow epitaxial graphene on commercial SiC wafers. This will allow researchers to develop a new detection method for fast neutrons. In addition, it will lead to better and more compact neutron detection system.	Document	MSTR	FY2012
Reducing Actinide Production Using Inert Matrix Fuels	University of Texas- Austin	$435,000	Reasearchers will perform a neutronic analysis, a thermal-hydraulic analysis and a simulation of fuel decay heat as a functionof fuel burnup, to determine if inert matrix fuel in coventional reactors will continue to be licensable. If successful, the inert matrix fuel mixtures will reduce harmful transuranic components in the fuel discharge streams at a level comparable to a fast reactcor burner.	Document	MSTR	FY2012
An Integrated Fuel Depletion Calculator for Fuel Cycle Options Analysis	University of Texas- Austin	$395,000	Reasearchers use new analysis techniques to better predict nuclear fuel behavior. The new model will allow improved fuel cycle for a larger number of users.	Document	MSTR	FY2012
Atomic-Scale to Meso-Scale Simulation Studies of Thermal Ageing and Irradiation Effects in Fe-Cr Alloys	Boston University	$874,997	Reasearchers will develop predictive, multi-scale simulation tools for iron-chromium alloys, which are expected to be key components of advanced steels envisioned as fuel cladding and structural components for Generation IV reactors. Such modeling is necessary to avoid resource intensive and costly thermal and neutron irradiation experiments to obtain required performance data.	Document	NEAMS	FY2012
Validation Data and Model Development for Fuel Assembly Response to Seismic Loads	George Washington University	$862,435	Reasearchers will conduct experiments that will provide comprehensive data characterizing the dynamics of the fluid and the structure in Pressurized Water Reactors (PWR) fuel assemblies under seismic loads (earthquakes and loss of coolant accidents). Completion of their project will greatly benefit the safety of existing and future nuclear reactors.	Document	NEAMS	FY2012
Uncertainty Quantification and Management for Multiscale Nuclear Materials Modeling	Georgia Institute of Technology	$743,444	Reasearchers will address the question of uncertainty propogation and error estimates associated with model prediction of material behavior under irradiation. Their work will facilitate a better understanding of the connection of various unit processes to collective responses in a multiscale model chain enabling the development of high strength and high ductility materials.	Document	NEAMS	FY2012
Fuel and Core Design Options to Overcome the Heavy Metal Loading Limit and Improve Performance and Safety of Liquid Salt Cooled Reactors	Georgia Insitute of Technology	$784,689	Reasearchers will examine new options for fuel and core designs in liquid salt cooled reactors where the current standard of TRISO type fuel has limitations due to loading characteristics. The research could enable new, more feasible fuel-core-reload options that will improve safety and performance parameters.	Document	RCRD&D	FY2012
Nonlinear Ultrasonic Techniques to Monitor Radiation Damage in RPV and Internal Components	Georgia Institute of Technology	$877,000	Reasearchers will explore new nondestructive materials evaluation and monitoring techniques utilizing nonlinear ultrasonic measurements . This technique will allow researchers to assess remaining useful life of select reactor components. Breakthroughs in this area will lead to the ability to characterize radiation damage in reactor pressure vessels and other components-leading to a clearer definition of reactor safety margins.	Document	RCRD&D	FY2012
Intergral Reactor Containment Condensation Model and Experimental Validation	Oregon State University	$871,119	Reasearchers will conduct experiments to enhance the safety and efficiency of small modular reactors (SMRs). This project will assess the impact of high-pressure steam condensation on steel containment vessels to be used for SMR deigns.	Document	RCRD&D	FY2012
Investigation of Natural Circulation Instability and Transients in Passively Safe Small Modular Reactors	Purdue University	$871,100	Reasearchers will perform scaled experiments to study the thermal-hydraulic instabilities that can occur in Small Modular Reactors (SMR) which rely on natural circulation cooling during normal operation and accident conditions. Their work will not only improve our understanding of general natural circulation instability but also lead to the development of stability criteria and predictability in the operation of SMRÃs.	Document	RCRD&D	FY2012
Thermoelectric-Driven Sustainable Sensing and Actuation Systems for Fault-Tolerant Nuclear Incidents	State University of New York, Stony Brook	$599,802	Reasearchers will examine the use of solid-state thermoelectric generators to produce electricity to sense and opeate during both normal and abnormal situations. This will provide indefinite monitoring of key components during power outages or station blackouts.	Document	RCRD&D	FY2012
Experimental and CFD Studies of Coolant Flow Mixing within Scaled Models of the Upper and Lower Plenums of NGNP Gas-Cooled Reactors	Texas A&M University	$713,051	Reasearchers will model the internal coolant flow of a prismatic core very high temperature reactor (VHTR) by using large eddy simulation tools. This method will enable more accurate prediction of flow field characteristics and better evaluation of VHTR behavior under operational and accidental conditions.	Document	RCRD&D	FY2012
Demonstrating Hybrid Heat Transport and Energy Conversion System Performance Characterization Using Intelligent Control Systems	University of Idaho	$877,000	Reasearchers will demonstrate an intelligent control systems in a hybrid energy conversion loop for a next generation nuclear power plant. Hybrid energy systems are a method of optimizing the use of natural resources for energy production. Hybrid systems present an opportunity to develop domestic energy sources to improve energy security.	Document	RCRD&D	FY2012
Advanced Reactor-Intermediate Heat Exchanger (IHX) Coupling: Theoretical Modeling and Experimental Validation	University of Idaho	$869,997	Reasearchers will model the behavior of the Advanced Reactor Intermediate Heat Exchanger Chemical Process system and develop advanced control techniques that take into account abnormal scenarios. The data and information obtained will assist in the development of intelligent control systems for next generation nuclear reactor systems.	Document	RCRD&D	FY2012
Irradiation Performance of Fe-Cr Base Alloys	University of Illinois- Urbana Champaign	$876,332	Reasearchers will perform post-radiation analysis and develop tools for future development and application of the Fe-Cr class of alloys. The results of this research will lead to better modeling of performance and development of an alloy designated as the primary choice for reactor fuel cladding and structural applications in advanced systems.	Document	RCRD&D	FY2012
Accelerated Irradiations for High Dose Microstructures in Fast Reactor Alloys	University of Michigan	$831,876	Reasearchers will determine the extent to which high dose rate irradiation can be used as an irradiation damage tool to understand microstructure evolution at high doses and temperatures relevant to advanced fast reactors. The project will provide fundamental understanding of the effectiveness of this process and thus of microstructure development in irradiated materials.	Document	RCRD&D	FY2012
Mitigating IASCC of Reactor Core Internals by Post-Irradiation Annealing Advanced Mitigation Strategies	University of Michigan	$876,985	Reasearchers will determine the optimum Post-irradiation annealing (PIA)-driven mitigation strategy to extend the potential lifetime of light water reactors. Samples that have already been irradiated in a light water reactor will be used to test PIA treatments to understand IASCC initiation and propoagation, annealing kinetics, the role of microstructure features in irradation hardening and localized deformation, and the optimum mitigation strategy based on PIA.	Document	RCRD&D	FY2012
Experimentally Validated Numerical Models for Effects of Non-Isothermal Turbulent Mixing on Wall Stresses in High Temperature Reactors	University of Pittsburgh	$876,422	Reasearchers will develop a comprehensive experimentally validated computational framework for the turbulent mixing in the lower plenum of a very high temperature reactor (VHTR). Through CFD modeling and experimental validation, the results from this project will lay the groundwork for future stress analysis, failure and fatigue studies, and uncertainty quantification for the VHTR system.	Document	RCRD&D	FY2012
Role of Defects in Swelling and Creep of Irradiated SiC	University of Wisconsin- Madison	$875,350	Reasearchers will study mechanisms controlling both radiation swelling and radiation creep in silicon carbide. These two effects are crucial to understanding the issues associated with the brittle silicon carbide composite. Success in this project will ground progress in the adoption of silicon carbide for reactor solutions, particularly as fuel cladding.	Document	RCRD&D	FY2012
Advanced Supercritical Carbon Dioxide Brayton Cycle Development	University of Wisconsin, Madison	$877,000	Reasearchers will investigate the benefits of utilizing advanced Brayton cycles with supercritical carbon dioxide in new reactor systems and components. Benefits of this research include improvement of analysis and performance of components currently utilizing these cycles as well as the potential for a large scale advanced CO2 power system.	Document	RCRD&D	FY2012
Mechanical Behavior of UO2 at Sub-grain Length Scales: Quantification of Elastic, Plastic and Creep Properties via Microscale Testing	Arizona State University	$800,000	Reasearchers will develop techniques to measure properties at sub-grain scales using depleted Uranium Oxide samples. The project will provide a framework to measure sub-grain scale mechanical properties, as well as provide experimental data to improve the understanding of advanced oxide fuels.	Document	FCR&D	FY2013
The Impacts of Pore-Scale Physical and Chemical Heterogeneities on the Transport of Radionuclide-Carrying Colloids	Colorado School of Mines	$800,000	Reasearchers will identify the dominant transport mechanisms to develop models that predict radionuclide distribution in porous materials. Experimental and computational models will be created that couple pore-scale geometric and interfacial structures. Simulators such as these are a necessary step towards fully predictive models for field-scale applications in the future.	Document	FCR&D	FY2013
Recovery of Uranium from Seawater: Polymer-Supported Aminophosphinates as Selective Extractants	Hunter College, CUNY	$399,999	Reasearchers will prepare a polymer-supported extractant for the recovery of uranium from seawater. The project will focus on primary amines that could provide a 3-fold increase in uranium capture capacity than current methods.	Document	FCR&D	FY2013
In-pile Thermal Conductivity Characterization with Single-laser Heating/Time Resolved Raman	Iowa State University	$800,000	Reasearchers will develop a time-resolved Raman-based thermal conductivity measurement system to improve remote in-pile thermal conductivity measurement. These measurements will provide new insights into the behavior of materials exposed to extreme radiation and temperature environments. Understanding the behavior of materials at the microstructural level will support optimized fuel designs.	Document	FCR&D	FY2013
Organic Speciation and Interactions in ALSEP - One Step Partitioning Process of Minor Actinides, Lanthanides, and Fission Products	Oregon State University	$600,000	Reasearchers will investigate the Actinide-Lanthanide Separation (ALSEP) process organic phase prior to aqueous phase separation and after aqueous separation phases of bare and metal-loaded acids. Quantifying these effects can be used to determine how an engineering scale process will perform and generate an accurate chemical model for the system.	Document	FCR&D	FY2013
Glass Composition and Solution Speciation Effects on Stage III Dissolution	Pennsylvania State University	$700,000	Reasearchers will study the chemical and structural triggers of long-term vitrified nuclear waste form behavior. They will study a range of waste glass compositions in corrosive environments. The study will improve understanding of the long-term residual rate and may provide new options for environmental control of glass dissolution rates.	Document	FCR&D	FY2013
Correlating Thermal, Mechanical, and Electrical Coupling Based Multiphysics Behavior of Nuclear Materials Through In-Situ Measurements	Purdue University	$800,000	Reasearchers will use in-situ experimental techniques to monitor the influence of extreme conditions on fuel cladding. The project will establish an in-situ experimental setup that can predict change in thermal properties and their correlation with mechanical properties and correlate such changes to changes in microstructural and chemical features.	Document	FCR&D	FY2013
Creation of a Geant4 Muon Tomography Package for Imaging of Nuclear Fuel in Dry Cask Storage	Purdue University	$440,000	Reasearchers will develop a simulation and analysis package to aid in the non-destructive assessment of sealed used nuclear fuel dry casks using cosmic ray muons. Cosmic ray muon tomography allows for non-destructive assessment that can independently verify and identify weapons grade material sealed within dense dry casks.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Two-stage Fast Reactor Fuel Cycle Options for Optimum Resource Utilization and Waste Management	Purdue University	$400,000	Reasearchers will evaluate the two different two-stage fast reactor fuel cycle options that will offer efficient use of uranium resources and the ability to burn actinides and long-live fission products. Evaluation of these fast fuel cycle options will serve as a useful complement to the options currently being considered in the Fuel Cycle Options Campaign.	Document	FCR&D	FY2013
Mixed Metal Phosphonate-Phosphate Resins for Separation of Lanthanides from Actinides	Texas A&M University	$650,000	Reasearchers will use ion exchangers to cleanly separate lanthanides and curium from reusable actinides. The study will assist in the development of an inexpensive, simple way in which to separate lanthanides from actinides found in used nuclear fuel rods and to recover a large portion of the usable fuel.	Document	FCR&D	FY2013
Safeguards in Pyroprocessing: an Integrated Model Development and Measurement Data Analysis	The Ohio State University	$626,151	Reasearchers will develop a comprehensive and effective safeguards approach for a pyroprocessing facility to support safeguards for future fuel cycles in the United States. The new approach and design will focus directly on the special nuclear materials in the electrorefiner where actinides are separated from fission products through electrochemical process.	Document	FCR&D	FY2013
Using Ionic Liquids for the Development of Renewable Biopolymer-Based Adsorbents for the Extraction of Uranium from Seawater and Testing Under Marine Conditions	University of Alabama	$400,000	Reasearchers will explore the fundamental engineering parameters for a renewable high-performance adsorbent for the extraction of uranium from sweater based on a recently proven ionic liquid (IL)-chitin platform. The project will use the platform to develop a versatile, modifiable adsorbent and characterize its performance and degradation in marine conditions.	Document	FCR&D	FY2013
Developing Ultra-Small Scale Mechanical Testing Methods and Microstructural Investigation Procedures for Irradiated Materials.	University of California, Berkeley	$800,000	Reasearchers will develop new small-scale mechanical testing techniques to allow for the estimation or direct measurement of bulk properties. The combined experiments and modeling will significantly enhance the statistics and information that can be obtained on small radioactive archived samples, as well as new ion beam irradiated specimens.	Document	FCR&D	FY2013
Improved Delayed-Neutron Spectroscopy Using Trapped Ions	University of California, Berkeley	$400,000	Reasearchers will develop innovative spectroscopy techniques to measure the decay of fission fragments. The resulting data from these new techniques will be used to better understand reactor kinetics under accident conditions and failure scenarios.	Document	FCR&D	FY2013
Thermally and Chemically Responsive Nanoporous Materials for Efficient Capture of Fission Product Gases	University of California, Davis	$750,000	Reasearchers will create new nanoporous materials that will be highly effective at capturing fission product gases. These materials would be relevant to both reactor fuels applications and reprocessing operations. Tests will be performed in carbon based and nitride based nanostructures, with the most promising materials from the modeling perspective undergoing further testing.	Document	FCR&D	FY2013
Multiphase Nanocrystalline Ceramic Concept for Nuclear Fuel	University of California, Irvine	$800,000	Researchers will study the use of nanoparticles and nanostructured ceramics to create new materials that can extend the service life and increase efficiency for nuclear fuel. Multiphase nanocrystalline ceramics will be used to design simulated nuclear fuel that can provide added plasticity, better radiation tolerance and improved thermal conductivity.	Document	FCR&D	FY2013
Development of Novel Porous Sorbents for Extraction of Uranium from Seawater	University of Chicago	$400,000	Reasearchers will develop a highly porous sorbent for the extraction of uranium from seawater. Previous research has established sorbent performance. This project will use past foundational studies to design and investigate a new nanocomposites that will be processed into tacks or braids for field tests in seawater tests. The technology may also be used for other metals.	Document	FCR&D	FY2013
Microwave Readout Techniques for Very Large Arrays of Nuclear Sensors	University of Colorado, Boulder	$799,937	Reasearchers will develop a powerful readout technique based on microwave transmission and reflection. The technique will enable very large arrays of diverse sensor types for nuclear materials quantification and tracking. It will provide more accurate data on material composition and quantity.	Document	FCR&D	FY2013
BiI3 Gamma-Ray Spectrometers for Reliable Room-Temperature Nuclear Materials Safeguarding	University of Florida	$799,999	Reasearchers will develop gamma-ray spectrometers based on BiI3 single crystals for MPACT applications such as burnup validation quantification, improved assay of plutonium, determination of uranium enrichment and overall monitoring spent fuel within the fuel cycle. The project will improve energy resolution, efficiency and environmental performance with this new gamma-ray detector.	Document	FCR&D	FY2013
Innovative Coating of Nanostructured Vanadium Carbide on the F/M Cladding Tube Inner Surface for Mitigating the Fuel Cladding Chemical Interactions	University of Florida	$760,276	Researchers will develop barrier coatings on the inner surface of fuel cladding tubes to improve performance of materials at elevated temperatures and high neutron exposures in fast reactors. The project will develop and test a low temperature coating process of nanostructured vanadium carbide that will provide a benchmark for use in future studies.	Document	FCR&D	FY2013
Doubling the Life of Concrete Structures	University of Idaho	$800,000	Reasearchers will use nanoscale techniques to develop methods for doubling the service life of concrete structures. They will study the effect of temperature load and temperature cycling (freezing and thawing) on the durability of concrete with nanoscale viscosity modifiers. The project will benefit from non-destructive evaluation of concrete performance through electrochemical techniques.	Document	FCR&D	FY2013
Off-Gas Treatment: Evaluation of Nano-structured Sorbents for Selective Removal of Contaminants	University of Idaho	$785,910	Reasearchers will evaluate nanostructured sorbent materials for their effectiveness in removing and immobilizing radionuclides for the off-gas treatment from used nuclear fuel recycling operations. The project aims at achieving near-zero emissions of radionuclides by capturing them from the off-gas of recycling operations, allowing for the development of advanced fuel cycles.	Document	FCR&D	FY2013
Innovative Elution Processes for Recovering Uranium and Transition Metals from Amidoxime-Based Sorbents	University of Idaho	$399,864	Reasearchers will develop a new two-step elution process to achieve total recovery of uranium and effective recycling of the sorbent. The extraction process would selectively remove uranium from the sorbent with little or no damage. The process would then remove transition metals and regenerate the sorbent for repeated use, making uranium extraction from seawater economically viable.	Document	FCR&D	FY2013
Performance of a Steel/Oxide Composite Waste Form for Combined Waste Streams from Advanced Electrochemical Processes over Geologic Time Scales	University of Illinois at Chicago	$700,000	Reasearchers will develop and validate a mechanistically-based corrosion model for cermet-type waste forms, creating a testing protocol and modeling approach for predicting long-term performance. The study will apply novel electrochemical testing and modeling methods to the behavior of metal/oxide phase boundaries to evaluate waste form performance.	Document	FCR&D	FY2013
Enhancement of the Extraction of Uranium from Seawater	University of Maryland, College Park	$400,000	Reasearchers will develop and optimize novel adsorbents for uranium recovery from seawater. The team will use radiation-induced grafting of organic phosphates onto polymers. The experiments will use ocean water, with mechanistic analysis, to provide a solid basis for large-scale demonstration of the performance of the new adsorbents in ocean environments.	Document	FCR&D	FY2013
Improving the Understanding of the Coupled Thermal-Mechanical-Hydrologic Behavior of Consolidating Granular Salt	University of New Mexico	$800,000	Reasearchers will increase the understanding of granular salt seal materials for shafts, drifts and boreholes. By coupling thermal, mechanical and hydrological responses, the study will result in greater confidence in granular salt consolidation as a principal strategy for closure and isolation of long-term waste repositories.	Document	FCR&D	FY2013
Fission Fragment Yield Data in Support of Advanced Reactor Technology	University of New Mexico	$399,816	Reasearchers will produce a highly accurate data set for thermal fission. These precision data are necessary for high-accuracy simulations of nuclear criticality, transmutation rates, radiation effects and heating as well as for nuclear fuel, material accounting and identification needs.	Document	FCR&D	FY2013
Molecular dynamics-based simulations of bulk/interfacial structures and diffusion behaviors in nuclear waste glasses	University of North Texas	$700,000	Reasearchers will generate accurate atomic structural models for use in Monte Carlo simulations of the dissolution of nuclear waste glasses. Large-scale molecular dynamics-based computer simulations will be used to investigate self-diffusion behaviors, interfacial structure, and other structures formed during dissolution of these glasses.	Document	FCR&D	FY2013
U3Si2 Fabrication and Testing for Implementation into the BISON Fuel Performance Code	University of South Carolina	$800,000	Reasearchers will fabricate, test and model a high uranium density, advanced nuclear fuel that operates at a much lower temperature and stores less energy. The work will deliver key research data on creep and grain growth, improving economics, through possible power uprates, and advancing accident tolerant fuels research.	Document	FCR&D	FY2013
Structural Health Monitoring of Nuclear Spent Fuel Storage Facilities	University of South Carolina	$738,618	Reasearchers will develop a nuclear structural health monitoring system based on a sensing technology that monitors material degradation and aging for dry cask storage systems. The low-cost, low-profile sensors will perform on-demand monitoring of the structural integrity of individual components as well as the entire system.	Document	FCR&D	FY2013
ORIGEN-based Nuclear Fuel Depletion Module for Fuel Cycle Assessment	University of Tennessee at Knoxville	$755,181	Reasearchers will develop a flexible reactor analysis module for the CYCLUS fuel cycle simulator based on established tools for reactor fuel depletion and decay. They will use ORIGEN, a mature and experimentally validated code, affording greater flexibility and allowing for accurate evaluations of impacts of both present and future fuel cycle options.	Document	FCR&D	FY2013
Cost and System Analysis of Innovative Fuel Resources Concepts	University of Texas at Austin	$295,960	_This project will develop and test braided polymer fiber adsorbents that surpass the sorption capacity, selectivity and durability of the best existing technology to recover uranium from seawater.	Document	FCR&D	FY2013
Risk Assessment of Structural Integrity of Transportation Casks	University of Utah	$789,296	Reasearchers will assess the loss of structural integrity of transportation casks and fuel cladding after extended storage. This risk assessment will conduct experimental tests and simulations to evaluate the structural performance of fuel, fuel assemblies and cask components when subjected to vibration and impact loads during transport.	Document	FCR&D	FY2013
Market-Based and System-Wide Fuel Cycle Optimization	University of Wisconsin, Madison	$612,731	Reasearchers will create market and economic optimizers to improve calculations for the CYCLUS fuel cycle simulator. The team will leverage existing optimization software frameworks within the simulator to resolve top level policy questions. The optimizations will allow CYCLUS to move beyond static material compositions, providing a holistic view of the fuel cycle system.		FCR&D	FY2013
Optical Fiber Based System for Multiple Thermophysical Properties for Glove Box, Hot Cell and In-Pile Applications	Utah State University	$799,975	Reasearchers will use a small pressure vessel to develop a robust technique for the measurement of multiple thermophysical properties at very high temperatures. The technique will lead to a system design moving toward the eventual measurement of irradiated fuels in a glovebox and/or hot cell with all sensors and electronics outside of the glovebox and/or hot cell.	Document	FCR&D	FY2013
Development of a Nano-Modified Concrete for Next Generation of Storage Systems	Vanderbilt University	$796,268	Reasearchers will use nano-sized and nano-structured particles based on enhanced reactivity to develop a superior concrete for the long-term storage of used nuclear fuel. The project will use state-of-the-art experimental chemical and mechanical characterizations and computation analysis to assess the performance of nano-modified concretes.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Thorium Fuel Cycle Options	Vanderbilt University	$797,995	Reasearchers will develop six fuel cycle data packages for multi-stage, thermal fuel cycles which incorporate thorium. These new fuel cycle data packages will provide the opportunity to examine fuel cycle options beyond those which have traditionally been considered. A thorium fuel cycle database will also be assembled as a basis for thorium literature for future evaluations of the thorium fuel cycle.	Document	FCR&D	FY2013
Enhanced Shielding Performance of HLW Storage Packages via Multi-Component Coatings	Virginia Polytechnic Institute and State University	$796,947	Reasearchers will develop a multi-layer composite that will enhance long-term storage and facilitate safe transport of storage packages. This novel multi-layer, multi-component coating would create an outer shield material that is resistant to the corrosion, radiation, diffusion and thermal cycling processes that affect fuel packages during long term storage.	Document	FCR&D	FY2013
Managing Zirconium Chemistry and Phase Compatibility in Combined Process Separations for Minor Actinide Partitioning	Washington State University	$700,000	Reasearchers will address unique challenges for combining TRUEX and TALSPEAK processes for partitioning of lanthanides and minor actinides. The project will develop improved information on the thermodynamics of fission product zirconium and develop a framework for an organic phase solvation model. Combined process development could streamline separations processes.	Document	FCR&D	FY2013
Advances in the Recovery of Uranium from Seawater: Studies Under Real Ocean Conditions	Woods Hole Oceanographic Institution	$398,882	Reasearchers will provide infrastructure and expertise for marine testing of currently available adsorbents in real ocean conditions. The team will move adsorbent research from the lab to field testing in order to quantify sorptive properties and uranium uptake. The project will provide valuable field data that will show the potential of large scale applications of these technologies.	Document	FCR&D	FY2013
NEUP Project 20-19172: Irradiation of Sensors and Adhesive Couplants for Application in LWR Primary Loop Piping and Components		$497,881	Reasearchers paln to attach ultrasonic transducers to substrates using various adhesive couplants that will be irradiated at elevated temperature to simulate LWR primary loop conditions at the PULSTAR reactor at North Carolina State University. Ultrasonic data will be taken in-situ. Subsequently, the sensors and couplant interfaces will be characterized using the LAMDA facility at ORNL. The results will be used to benefit a parallel EPRI project on online monitoring of cracks in LWR primary loop piping._	Document	R&D NSUF	FY2013
NEUP Project 20-19404: Extension of MSTDB to Provide a High-Quality, Validated Thermochemical Database for Predicting/Simulating Corrosion in Molten Salt Reactor SystemsUniversity of South Carolina		$600,000	Reasearchers will generate a validated, consistent database of initial fuel compositions and potential corrossion products of fluoride and chloride salts, allowing for important phenomena predictions in molten salt reactors to guide confident decisions. The database will be integral to the currently being developed Molten Salt Thermochemical Database (MSTDB), structured to allow use by commercial and open source codes._	Document	NEAMS	FY2013
Lower Length Scale Characterization and Validation of Formation and Stability of Helium Bubbles in Nano-structured Ferritic Alloys under Irradiation	Clemson University	$399,870	Reasearchers will provide a fundamental knowledge about the formation and stability of ultra-fine helium bubbles within 14YWT after neutron/ion irradiation for further design of new advanced structural materials with a characteristic high density nanoparticles feature which can increase the mechanical strength, hardness, irradiation resistance and the operational temperature range of materials.	Document	NEAMS	FY2013
Three-Dimensional Fuel Pin Model Validation by Prediction of Hydrogen Distribution in Cladding and Comparison with Experiment	Pennsylvania State University	$800,000	Reasearchers will validate important three-dimensional aspects of the fuel pin modeling by using specialized numerical modeling techniques coupled with laboratory experiments to validate existing models for predicting fuel performance in light water reactors.	Document	NEAMS	FY2013
Collocation-Based Surrogate Models for Uncertainty Quantification and Validation of Coupled, Multiphysics Fuel Performance Simulation Tools	University of Michigan	$596,835	Reasearchers will provide the necessary high fidelity, coupled, multiphysics fuel performance simulator for computational modeling and develop surrogates which will accelerate and focus the validation of the coupled codes. This will be achieved by utilizing the high fidelity coupled fuel performance, thermal-hydraulics and neutronics codes BISON/STAR-CCM+/MPACT and an innovative collocation-based surrogate methodology.	Document	NEAMS	FY2013
Multi-Resolution In-Situ Testing and Mutliscale Simulation for Creep Damage Fatigue Damage Analysis of Alloy 617	Arizona State University	$800,000	This project will develop novel testing and experimentally validated prediction methodologies for micro-structural damage mechanisms of structural materials for advanced reactor systems. The investigations will focus on the characterization and testing of specific metal alloys, but the proposed testing and life-prediction methodologies are applicable to other structural materials as well.	Document	RCRD&D	FY2013
Novel High Temperature and Radiation Resistant Infrared Glasses and Optical Fibers for Sensing in Advanced Small Modular Reactors	Clemson University	$800,000	Clemson University, in partnership with the Iowa State University and the Pacific Northwest National Laboratory, will develop novel optical materials with improved heat and radiation exposure resistance in order to enable in-vessel fiber optic sensing for advanced Small Modular Reactors.	Document	RCRD&D	FY2013
Validation Data Acquisition in HTTF during PCC Events	George Washington University	$800,000	Reasearchers at the George Washington University and Oregon State University will collaborate with NASA Langley Research Center to measure flow velocities in a high temperature test facility. This work supports the development of very-high temperature reactors with passive safety systems.	Document	RCRD&D	FY2013
Advanced High Temperature Inspection Capabilities for Small Modular Reactors	Iowa State University	$790,822	The objective of this project is to develop non-destructive evaluation techniques for advanced small modular reactors. The research will provide key enabling inspection technologies needed to support the design and the reactor component performance validation process for advanced small modular reactors.	Document	RCRD&D	FY2013
Experimental and Computational Investigations of Plenum-to-Plenum Heat Transfer under Natural Circulation in a Prismatic Very High Temperature Reactor	Missouri University of Science and Technology	$799,999	Reasearchers will perform experimental and computational investigations to study heat transfer and natural circulation phenomena in very-high temperature reactors. The study will assist in the ability to predict and analyze passive safety systems.	Document	RCRD&D	FY2013
New Mechanistic Models of Creep-Fatigue Crack Growth Interactions for Advanced High Temperature Reactor Components	Oregon State University	$790,790	Reasearchers will create and validate a robust, multi-scale, numerical model to predict material degradation in nickel-based reactor alloys. If successful, this project will provide better numerical tools for reactor designers and greatly improve their capability to design against material failures for reactor alloys in the long term.	Document	RCRD&D	FY2013
Self-Powered Wireless Dual-mode Langasite Sensor for Pressure/Temperature Monitoring of Nuclear Reactors	State University of New York, Stony Brook	$800,000	This research will develop a novel self-powered wireless hybrid sensor that can accurately monitor both pressure and temperature using a single device without requiring external electricity, even in extreme harsh environments.	Document	RCRD&D	FY2013
Compact Heat Exchanger Design and Testing for Advanced Nuclear Reactors and Advanced Power Cycles	The Ohio State University	$800,000	The goal of this project is to investigate optimal heat exchanger designs for advanced reactors. The research will study the optimization of printed circuit heat exchangers for specific fluids under a variety of conditions as well as perform numerical modeling. Experiments will focus on thermal performance and heat stress during extreme conditions.	Document	RCRD&D	FY2013
Fundamental Understanding of Creep-Fatigue Interactions in 9Cr-1MoV Steel Welds	The Ohio State University	$798,000	This project will advance the state of knowledge and fundamental understanding of deforming materials and welds under loading conditions. Specifically, new integrated testing procedures will be evaluated and applied for conditions that are most detrimental to material stability leading to improved predictions of life expectancy for reactor steels and welds.	Document	RCRD&D	FY2013
Advanced Mechanistic 3D Spatial Modeling and Analysis Methods to Accurately Represent Nuclear Facility External Event Scenarios	The Ohio State University	$800,000	Reasearchers will develop three-dimensional characterization uncertainty analysis for commercial power plants. The project will involve combining experts from the fields of seismic structural modeling and advanced methods of risk assessment. This effort is expected to result in next generation tools that can be used for assessment of seismic risks.	Document	RCRD&D	FY2013
Tritium Mitigation/Control for Advanced Reactor Systems	The Ohio State University	$400,000	Reasearchers will develop a fluoride salt cooled high-temperature reactor featuring a specialized system to control tritium production. If successful, this will result in a significant reduction in size and cost in comparison to other reactor designs.	Document	RCRD&D	FY2013
A Pebble-Bed Breed and Burn Reactor	University of California, Berkeley	$400,000	Reasearchers will assess the feasibility of designing a type of metal cooled reactor able to establish and maintain operation when fueled with depleted uranium. If successful, this reactor will offer at least a 30-fold increase in the uranium ore utilization versus that achieved in contemporary light water reactors without the need for fuel reprocessing and recycling.	Document	RCRD&D	FY2013
Investigation of Thermal Aging Effects on the Evolution of Microstructure and Mechanical Properties of Cast Duplex Stainless Steels	University of Maryland, College Park	$799,966	This research will provide a better understanding of the microstructural evolution and simultaneous change in mechanical response during aging. The results of the research will provide data that can be used to estimate degraded mechanical properties for an 80-year service life of light water reactors.	Document	RCRD&D	FY2013
Model validation using CFD-grade experimental database for NGNP Reactor Cavity Cooling Systems with water and air	University of Michigan	$799,348	Reasearchers will use advanced innovative instrumentation to build a high-resolution experimental database and to use the novel experimental data to assess and further develop the predictive capabilities of computer codes for thermal hydraulics and computational fluid dynamics. The improved models developed by this project will also have the direct benefit of improving the predictive capability of the passive systems of third generation light water reactors and small modular reactor systems.	Document	RCRD&D	FY2013
Long-Term Prediction of Emissivity of Structural Material for High Temperature Reactor Systems	University of Missouri	$799,117	Reasearchers will study specific types of emissivity driven cooling from a variety of materials that are relevant to nuclear reactors. The research will provide a basis for numerical modeling to support reactor development.	Document	RCRD&D	FY2013
Advanced I&C for Fault-Tolerant Supervisory Control of Small Modular Reactors	University of Pittsburgh	$800,000	The purpose of this research is to develop advanced instrumentation and control techniques for supervisory control of advanced small modular reactors. This research supports the operational goals of small modular reactor concepts through the development of improved oversight and surveillance techniques.	Document	RCRD&D	FY2013
Corrosion of Structural Materials for Advanced Supercritical Carbon-Dioxide Brayton Cycle	University of Wisconsin-Madison	$798,672	Reasearchers will study a variety of materials for corrosion resistance under conditions that improve power conversion. In addition to studying the corrosion resistance of the materials, researchers will study the effect of additives to mitigate corrosion. Development of corrosion theories and modeling aimed at prediction of long-term corrosion will be the underlying theme throughout the project.	Document	RCRD&D	FY2013
Component and Technology Development for Advanced Liquid Metal Reactors	University of Wisconsin-Madison	$798,920	In support of liquid metal cooled reactors, the University of Wisconsin, Madison will evaluate advanced alloys and ceramics that come in contact with liquid metals. Additionally, a robust oxygen sensor and for use in liquid metals will be developed in order to better evaluate corrosion profiles in support of diagnostic testing.	Document	RCRD&D	FY2013
A New Paradigm for Understanding Multi-phase Ceramic Waste Form Performance	Clemson University	$800,000	Researchers will use advanced characterization tools to develop 3-D microstructural data that can be incorporated into computer-based simulations in order to predict the performance of waste forms. Materials system modeling will incorporate elemental release and the interconnected microstructural network of phases to better understand performance and degradation, which will accelerate waste form acceptance in repository settings.	Document	FCR&D	FY2014
Controlling Hexavalent Americium: A Centerpiece to a Compact Nuclear Fuel Cycle	Colorado School of Mines	$800,000	Researchers will develop and exploit the fundamental chemistry of Americium to enable an industrially viable means to co-recover the major and minor actinide elements from used nuclear fuel. The results would be a significant step forward in the development of aqueous separations approaches designed to recover the U-Am actinides based on the availability of the hexavalent oxidation state.	Document	FCR&D	FY2014
Zeolite Membranes for Krypton/Xenon Separation from Spent Nuclear Fuel Reprocessing Off-Gas	Georgia Institute of Technology	$400,000	Researchers will develop a high-performance, lower-cost zeolitic membrane process for Kr/Xe separations during spent nuclear fuel processing. Current separation methods are not considered economical and a membrane process would have relatively lower cost, equipment size, and ambient operating temperature. The process would form a sound basis for further development of this transformative separation technology for the nuclear fuel cycle.	Document	FCR&D	FY2014
Optimizing Polymer-Grafted Amidoxime-based Adsorbents for Uranium Uptake from Seawater	Georgia Institute of Technology	$399,999	Researchers will work to increase the adsorbent capacity and selectivity toward uranium by optimizing the adsorbent morphology, synthesis variables, and conditioning parameters and by investigating the rate-limiting variables through transport and reaction modeling. A novel adsorption/partition concept that has the potential to substantially increase the adsorbent capacity will be tested, making uranium from seawater extraction more economically viable.	Document	FCR&D	FY2014
Extraction of Uranium from Seawater: Design and Testing of a Symbiotic System	Massachusetts Institute of Technology	$400,000	Researchers will develop a seawater uranium extraction system that will work symbiotically with an offshore windmill by utilizing the structure, mooring and power of the windmill, while increasing the energy harvested by the installation. Uranium will be extracted by an adsorbent polymer belt, which will be cycled through the seawater and an elution plant located at the base of the windmill tower. Increasing the frequency of harvesting could overcome current economic barriers to seawater uranium extraction.	Document	FCR&D	FY2014
Imaging a Dry Storage Cask with Cosmic Ray Muons	Oregon State University	$799,871	Researchers will develop an imaging system to monitor the content of a dry storage cask with cosmic ray muons. A very large amount of plutonium under nuclear safeguards is contained in used fuel assemblies stored in dry storage casks. Muon imaging will allow a cost effective and reliable way to evaluate dry storage cask content and integrity before transport.	Document	FCR&D	FY2014
Apatite and sodalite based glass-bonded waste forms for immobilization of 129I and mixed halide radioactive wastes	Rutgers University	$800,000	Researchers will develop advanced and chemically durable waste forms for immobilizing 129I (aqueous based reprocessing of fuel) and mixed-halide wastes (molten-salt processing of fuel) by low temperature synthesis. Halide-containing sodalite and calcium phosphate-based apatite minerals will be synthesized, consolidated and tested for chemical durability. The project will provide needed baseline data for the development of advanced waste forms for immobilization of iodine and mixed-halide wastes.	Document	FCR&D	FY2014
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$350,000	Researchers will develop modeling tools supported by experiments for off-gas capture from future nuclear-fuel recycling facilities. Target species include tritium, iodine, krypton, and xenon. The models are intended to provide path forward recommendations to develop off-gas treatment adsorption processes. The project will contribute to the evaluation of options for environmentally acceptable recycle systems.	Document	FCR&D	FY2014
Development of high performance ODS alloys	Texas A&M University	$800,000	Researchers will study swelling, radiation hardening and changes in mechanical properties of ODS alloys to develop two sets of advanced ODS alloys. Two sets of first-round candidate alloys that have already undergone extensive development and testing will evaluate irradiation performance. The study will meet the need for high strength, radiation-tolerant cladding and core components that have enhanced resistance to void swelling.	Document	FCR&D	FY2014
Rare Earth Electrochemical Property Measurements and Phase Diagram Development in a Complex Molten Salt Mixture for Molten Salt Recycle	The Ohio State University	$800,000	Researchers will investigate rare earth (RE) properties in complex molten salt mixtures. In a molten salt recycle approach, the RE drawdown by electrolysis is a key step in which REs are separated from salt containing other fission products. Investigation of RE electrolysis must consider the electrochemical properties of the REs. We propose to conduct studies of detailed experiments and corresponding models to provide the physical properties and phase diagrams required to predict the performance of RE drawdown for processing complex molten salts.	Document	FCR&D	FY2014
Studies of Lanthanide Transport in Metallic Nuclear Fuels	The Ohio State University	$800,000	Researchers will study the redistribution of lanthanides and migration of lanthanides to the fuel surface. The mechanisms of lanthanide transport in metallic fuel based on the novel discovery of a Ôliquid-likeÕ transport mechanism will be studied analytically and experimentally. The project will develop a fundamental understanding of lanthanide fission product migration and redistribution in advanced metallic nuclear fuels, and theory and data to mitigate fuel-cladding chemical interactions.	Document	FCR&D	FY2014
Computational and Experimental Studies of Microstructure-Scale Porosity in Metallic Fuels for Improved Gas Swelling Behavior	University of Arkansas	$796,823	Researchers will study the microstructure of metallic uranium alloy fuels, and their resistance to densification, to minimize in-pile irradiation swelling through bimodal pore size distribution. The project will develop a predictive approach to design metallic fuel microstructures for optimal swelling resistance and fission gas retention.	Document	FCR&D	FY2014
Improved Hybrid Modeling of Spent Fuel Storage Facilities	University of California, Berkeley	$645,393	Researchers will develop a variance reduction method for computational transport that will improve the ability to design and operate monitoring systems for interim used fuel installations through enhanced modeling and simulation. This new tool will demonstrate that modeling calculations can be done more accurately in less time than with current tools and will perform studies characterizing how changes in material, cask configurations, and number of casks could impact monitoring systems.	Document	FCR&D	FY2014
Selective ligands for uranyl via combinatorial peptoid libraries: A synthetic, structural, thermodynamic and computational study	University of California, Berkeley	$400,000	Researchers will study how donor ligands bind to the uranyl ion, UO22+, with the longer-term goal of using this information to tackle selective recognition of uranyl in aqueous solution. The study will impact underlying approaches to controlling the behavior of uranium in these systems. The actinide separation technology could be used in several areas including uranium extraction from seawater, nuclear waste remediation and nuclear materials.	Document	FCR&D	FY2014
Combining Experiments and Simulations of Extraction Kinetics and Thermodynamics in Advanced Separation Processes for Used Nuclear Fuel	University of California, Irvine	$799,938	Researchers will study how the kinetics and thermodynamics of metal ion extraction in advanced separation processes for used nuclear fuel can be described by molecular dynamic (MD) simulations and how the simulations can be validated by experimental data. The project would have broad impacts on several separations processes including advanced TALSPEAK, ALSEP and GANEX by increasing the confidence and accuracy of computer modeling of metal ion extraction._	Document	FCR&D	FY2014
Effect of Metallic Li on the Behavior of Metals in Molten Salts	University of Nevada, Reno	$458,250	Researchers will identify the effect of metallic lithium on materials that are used in molten salt recycling. The study will try to understand how the presence of Li(0) in molten salts affects the degradation of alloys. Studying these changes will help accurately predict container material behavior and longevity.	Document	FCR&D	FY2014
Assessment of Corrosion Resistance of Promising Accident Tolerant Fuel Cladding under Reactor Conditions	University of Notre Dame	$800,000	Researchers will assess the corrosion behavior of accident tolerant fuel candidate iron-based alloys under normal LWR operating conditions consisting of high temperature, relevant water chemistry and irradiation. The assessment will produce data about possible irradiation-accelerated corrosion rates of iron-based alloys, and the mechanisms by which such corrosion rates are accelerated. The project will advance the selection of appropriate replacements for Zircaloy cladding.	Document	FCR&D	FY2014
Functionalized Porous Organic Polymers as Uranium Nano-Traps for Efficient Recovery of Uranium from Seawaterr	University of South Florida	$399,000	Researchers will develop functionalized porous organic polymers, or Ônano-trapsÕ for extraction of uranium from seawater. This technique allows for increased surface area and custom-designed pore size and chemistry to fit specific parameters. The adsorbent materials have high efficiency and effectiveness for uranium recovery from seawater, providing a potential supply for nuclear fuel.	Document	FCR&D	FY2014
Enhanced Accident-Tolerant Fuel Performance and Reliability for Aggressive iPWR/SMR Operation	University of Tennessee	$799,967	To develop a process that evaluates operational and safety performance of reactor-and-fuel combinations by integrating whole-core 3D neutronics with MOOSE/BISON fuel performance assessments via explicit time and space dependent fuel rod operational power histories. The project will be valuable in analyzing and evaluating accident tolerant fuel concepts and furthering the understanding of reactor physics and fuel performance aspects of key accident tolerant fuel concepts.	Document	FCR&D	FY2014
Nuclear Technology R&D Strategies in an Era of Energy Price Uncertainty	University of Texas, Austin	$799,112	Researchers will identify nuclear technology options that are competitive over a wide range of plausible future business environments. No single nuclear technology or business practice will be the best choice across all or even most future conditions. The study will focus on hybrid nuclear-fossil technologies, energy storage and conversion, which will result in an identification of nuclear strategies that can succeed under future market conditions.	Document	FCR&D	FY2014
Development and Optimization of Voltammetric Methods for Real Time Analysis of Electrorefiner Salt with High Concentrations of Actinides and Fission Products	University of Utah	$621,612	Researchers will develop an advanced voltammetry method to pursue the objective of real time monitoring of actinide concentrations in electrorefiner salt. This will include experimental measurement of key parameters such as activity coefficients and exchange current density. It will also involve simulation of voltammetry processes based on first principles. The project will allow for real time measurements that could support the commercialization of pyroprocessing.	Document	FCR&D	FY2014
Development of Self-Healing Zirconium-Silicide Coatings for Improved Performance of Zirconium-Alloy Fuel Cladding	University of Wisconsin, Madison	$798,621	Researchers will study the deposition of self-healing zirconium-silicide coatings on zirconium-alloy fuel cladding material to improve corrosion resistance under normal and accident conditions. Under these conditions, Zr-Si coating evolves into a highly protective functionally-graded multilayered system. The study will lead to improved performance of zirconium-alloy fuels._	Document	FCR&D	FY2014
Thermal Conductivity in Metallic Fuels	Virginia Polytechnic Institute and State University	$799,837	Researchers will calculate the thermal conductivity of metallic uranium and neptunium alloys, including the effects of noble gasses, using density functional theory. The experiments will validate the calculated effective thermal conductivity using the MARMOT code and by helping determine DFT simulation parameters. The study works to improve fuel lifetime by understanding its thermal behavior.	Document	FCR&D	FY2014
SiC-ODS Alloy Gradient Nanocomposites as Novel Cladding Materials	Virginia Polytechnic Institute and State University	$799,998	Researchers will combine nuclear nanomaterial design, processing, testing, and characterization efforts to develop revolutionary materials that can withstand neutron irradiation for long period of time using nanostructured SiC and oxide dispersion strengthened steel. The ultimate objective is to offer new cladding materials with increased corrosion resistance, strength, and creep resistance in both steady state and accident conditions.	Document	FCR&D	FY2014
Experimental Breeder Reactor II Benchmark Evaluation	Idaho State University	$400,000	Researchers will develop a benchmark evaluation of the Experimental Breeder Reactor II (EBR-II). During nearly 30 years of operation numerous experiments were conducted at EBR-II. The most significant of these experiments were conducted in 1986 demonstrating inherent safety features in loss of flow without reactor scram and loss of heat sink without reactor scram. Benchmark evaluation will be valuable for the reactor design efforts in the United States and South Korea.	Document	MSNE	FY2014
Integral full core multi-physics PWR benchmark with measured data	Massachusetts Institute of Technology	$400,000	Researchers will introduce BEAVRS, a new multi-cycle full-core Pressurized Water Reactor (PWR) depletion benchmark based on two operational cycles of a commercial nuclear power plant. This project aims at addressing the uncertainty quantification of the measured data and on making this benchmark a true non-proprietary international benchmark for the validation of high-fidelity multi-physics computational tools.	Document	MSNE	FY2014
Benchmark Evaluation of PROTEUS Gas-Cooled Reactor Experiments	University of Florida	$400,000	Researchers will create International Reactor Physics Experiment Evaluation Project (IRPhEP) benchmarks using data from 1970s experiments of the neutronics of gas-cooled fast reactor (GCFR) designs investigated in the PROTEUS reactor. The GCFR-PROTEUS experiments fill a gap in current integral benchmark data. These experiments can provide validation of computational models and nuclear data for next generation reactors.	Document	MSNE	FY2014
An Investigation To Establish Multiphysical Property Dataset Of Nuclear Materials Based On In-Situ Observations And Measurements	Purdue University	$800,000	Researchers will create an in-situ measurement based experimental approach to develop experimental validation dataset for NEAMS based code validation. Particular emphasis is on supplying data set for multiphysics simulations in extreme conditions as a function of material microstructure.	Document	NEAMS	FY2014
Experimental Validation of UO2 Microstructural Evolutions for NEAMS tool MARMOT	University of Florida	$798,000	Researchers will experimentally validate MARMOT for predicting the microstructural evolutions of UO2 oxide fuel under the driving forces of high temperatures and large temperature gradient in reactors. By performing the experiments and simulations simultaneously using precisely defined initial conditions, the experiment data will provide direct benchmarking of the MARMOT code.	Document	NEAMS	FY2014
High-resolution time-resolved experiments on mixing and entrainment of buoyant jets in stratified environments	University of Michigan	$799,983	Researchers will study high spatial and time-resolution experimental data of the fluid dynamics phenomena of flow jets interacting with a stratified layer. The issue plays an important role in the safety of several reactor designs, including sodium-cooled reactors. The data addresses the NEAMS needs for the validation of high fidelity computational fluid dynamics methodologies.	Document	NEAMS	FY2014
Fundamental study of key issues related to advanced S-CO2 Brayton Cycle: prototypic HX development and Cavitation	Georgia Institute of Technology	$799,000	Researchers will study scientific and operational issues pertinent to compact heat exchanger systems and turbo-machinery. The project will work to resolve issues with the fabrication of diffusion bonded compact heat exchangers, alternate heat exchange technology for recuperators, and resolution of issues with cavitation and fluid instabilities.	Document	RCRD&D	FY2014
Advanced Models for Nondestructive Evaluation of Aging Nuclear Power Plant Cables	Iowa State University	$787,291	Researchers will develop advanced models that relate environmentally induced microstructural and chemical changes in cable insulation polymers to their macroscopic electrical parameters. These parameters will be measured and modeled over a wide range of the electromagnetic spectrum, covering several potential nondestructive evaluation techniques, enabling identification of the most sensitive techniques for future development.	Document	RCRD&D	FY2014
Development of Novel Functionally Graded Transition Joints for Improving the Creep Strength of Dissimilar Metal Welds in Nuclear Applications	Lehigh University	$800,000	Researchers will develop graded transition joints and improved creep life models for increasing the life of dissimilar metal welds (DMWs) in nuclear reactors. The research represents the first application of functionally graded material concepts for solving the problem of DMW failures through an integrated approach of additive manufacturing, modeling, microstructural characterization, and advanced strain-sensing techniques.	Document	RCRD&D	FY2014
Feasibility Assessment of a Micro Modular Reactor (MMR)	North Carolina State University	$400,000	Researchers will develop an innovative compact reactor concept that integrates power production, power conversion and electricity generation in a single unit: the Micro Modular Reactor (MMR). It is designed to be absolutely melt-down proof (MDP) under all circumstances including complete loss of coolant scenarios with no possible release of radioactive material, to have a cycle length of greater than 10 years, and to be highly proliferation resistant.	Document	RCRD&D	FY2014
Scaling Studies for Advanced Gas Reactor Concepts	Oregon State University	$681,834	Researchers will expand the utilization of the Oregon State University High Temperature Test Facility (HTTF) to validate a broader range of advanced high temperature reactors and events. The facility will be revised to add a detailed scaling analysis of additional gas reactor concepts including advanced gas-cooled, molten salt, and sodium cooled reactors.	Document	RCRD&D	FY2014
Fluid Stratification Separate Effects Analysis, Testing and Benchmarking	Oregon State University	$800,000	Researchers will study fluid stratification in high temperature gas reactors. Coolant stratification is the result of incomplete mixing of one or more fluids, leading to a density gradient, which may or may not dissipate under diffusive or convective effects. This combined analytical and experimental project seeks to investigate stratification driven by diffusive and convective mechanisms and is expected to yield insight into this phenomenon.	Document	RCRD&D	FY2014
Probabilistic Economic Valuation of Safety Margin Management Analysis	Oregon State University	$795,364	Researchers will use RAVEN and develop a companion software package to facilitate economic analysis of safety margins. The project is a proof of concept that will use techniques to examine the cost of improving safety margins vs. the risk of accidents from not improving safety margins. This analysis can be used to evaluate the economic viability of various plant upgrades.	Document	RCRD&D	FY2014
Novel Dissimilar Joints Between Alloy 800H and 2.25%Cr and 1%Mo Steel	Pennsylvania State University	$800,000	Researchers will fabricate and test dissimilar metal joints between a nickel base alloy and a steel with gradual variations of chemical composition, microstructure and properties in a manner that reduces abrupt thermal expansion mismatch and the resulting residual stresses. Data on structure and properties will serve as valuable inputs for the initiation of an ASME code case.	Document	RCRD&D	FY2014
Multi-Phase Model Development to Assess RCIC System Capabilities under Severe Accident Conditions	Texas A&M University	$564,246	Researchers will develop physics-based models of the Reactor Core Isolation Cooling (RCIC) System and incorporating them into a multi-phase code for validation. The project will tackle the current major challenges in RCIC System analysis and enable evaluation of two-phase thermodynamic aspects.	Document	RCRD&D	FY2014
Experimental Investigation and CFD Analysis of Steam Ingress Accidents in HTGRs	The Ohio State University	$800,000	Researchers will study the steam ingress scenario for HTGRs. The study will investigate thermal-hydraulic behavior and graphite oxidation of stream ingress phenomena to validate predictive CFD models. This work will resolve concerns about possible steam generator tube ruptures in a HTGR He-Steam Rankine cycle.	Document	RCRD&D	FY2014
Coiled Tube Gas Heaters For Nuclear Gas-Brayton Power Conversion	University of California, Berkeley	$800,000	Researchers will develop heat exchangers for Brayton-cycle power conversion in reactors using sodium, NaK, or salt as intermediate coolants. The proposed coiled tube gas heaters (CTGHs) are expected to have excellent power density, thermal shock/creep, in-service inspection, and reparability characteristics.	Document	RCRD&D	FY2014
Fundamental Studies of Irradiation-Induced Modifications in Microstructural Evolution and Mechanical Properties of Advanced Alloys	University of Illinois, Urbana-Champaign	$800,000	Researchers will develop and test a mechanism for predicting neutron irradiation performance for optimized Grade 92 and Alloy 709 for applications in advanced reactor systems. The work will employ ion irradiations and available information from neutron irradiations of related alloys to develop a basis for predicting the neutron irradiation performance of the optimized alloys.	Document	RCRD&D	FY2014
Integrated Computational and Experimental Study of Radiation Damage Effects in Grade 92 Steel and Alloy 709	University of Tennessee	$800,000	Researchers will develop a mechanistic understanding and predictive models of irradiation-induced microstructural evolution and resulting mechanical properties in optimized ferritic-martensitic Grade 92 steel and austenitic alloy 709 using multiscale simulations coupled with rigorous experimental validation. The project will provide insights into the correlation between ion irradiation and fast neutron damage.	Document	RCRD&D	FY2014
Meta-Level Design Guidance and Operator Performance Measures for Hybrid Control Rooms	Vanderbilt University	$799,869	Researchers will apply human factors engineering methods and relevant expertise from non-nuclear high-risk high-consequence domains toward the measurement of operator performance in analog, digital, and hybrid main control rooms. Performance measures will be developed for evaluating the situation awareness and decision-making proficiencies to support the transition to digital or hybrid control room displays.	Document	RCRD&D	FY2014

FY 2021 Research and Development Awards

DOE is awarding more than $48.8 million through NEUP to support 69 university-led nuclear energy research and development projects in 27 states. NEUP seeks to maintain U.S. leadership in nuclear research across the country by providing top science and engineering faculty and their students with opportunities to develop innovative technologies and solutions for civil nuclear capabilities.

A complete list of R&D projects with their associated abstracts is available below.

Title	Institution	Estimated Funding*	Project Description	Abstract	Project Type	Fiscal Year
Neutron Damage and MAX Phase Ternary Compounds	Drexel University			Document	IIR	FY2009
Atomistic Calculations of the Effect of Minor Actinides on Thermodynamic and Kinetic Properties of UO2+x	Georgia Institute of Technology			Document	IIR	FY2009
Maximum Fuel Utilization in Fast Reactors without Chemical Reprocessing	University of California, Berkeley			Document	IIR	FY2009
Developing a High Thermal Conductivity Fuel with Silicon Carbide Additives	University of Florida			Document	IIR	FY2009
Fabrication of Tungsten-Rhenium Cladding Materials via Spark Plasma Sintering for Ultra High Temperature Reactor Applications	University of Idaho			Document	IIR	FY2009
Ionic Liquid and Supercritical Fluid Hyphenated Techniques for Dissolution and Separation of Lanthanides, Actinides, and Fission Products	University of Idaho			Document	IIR	FY2009
Improved Fission Neutron Data Base for Active Interrogation of Actinides	University of Michigan			Document	IIR	FY2009
Utilization of Methacrylates and Polymer Matrices for the Synthesis of Ion Specific Resins	University of Nevada, Las Vegas			Document	IIR	FY2009
Improved LWR Cladding Performance by EPD Surface Modification Technique	University of Wisconsin, Madison			Document	IIR	FY2009
Advanced Models of LWR Pressure Vessel Embrittlement for Low Flux-High Fluence Conditions	University of California, Santa Barbara			Document	LWRS	FY2009
Irradiation Creep in Graphite	Boise State University			Document	NGNP	FY2009
Modeling the Stress Strain Relationships and Predicting Failure Probabilities For Graphite Core Components	Cleveland State University			Document	NGNP	FY2009
TRISO-Coated Fuel Durability Under Extreme Conditions	Colorado School of Mines			Document	NGNP	FY2009
An Innovative and Advanced Coupled Neutron Transport and Thermal Hydraulic Method (Tool) for the Design, Analysis and Optimization of VHTR/NGNP Prismatic Reactors	Georgia Institute of Technology			Document	NGNP	FY2009
Removal of 14C from Irradiated Graphite for Graphite Recycle and Waste Volume Reduction	Idaho State University			Document	NGNP	FY2009
Millimeter-Wave Thermal Analysis Development and Application to Gen IV Reactor Materials	Massachusetts Institute of Technology			Document	NGNP	FY2009
Accurate Development of Thermal Neutron Scattering Cross Section Libraries	North Carolina State University			Document	NGNP	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
Understanding Creep Mechanisms in Graphite with Experiments, Multiscale Simulations, and Modeling	North Carolina State University			Document	NGNP	FY2009
Simulations of the Thermodynamic and Diffusion Properties of Actinide Oxide Fuel Materials	University of Michigan			Document	AFCI	FY2009
Verification & Validation of High-Order Short-Characteristics-Based Deterministic Transport Methodology on Unstructured Grids	North Carolina State University			Document	NGNP	FY2009
Adsorptive Separation and Sequestration of Krypton, I and C14 on Diamond Nanoparticles	University of Missouri, Columbia			Document	AFCI	FY2009
Microscale Heat Conduction Models and Doppler Feedback	North Carolina State University			Document	NGNP	FY2009
Fundamental Understanding of Ambient and High-Temperature Plasticity Phenomena in Structural Materials in Advanced Reactors	Georgia Institute of Technology			Document	AFCI	FY2009
Development of Alternative Technetium Waste Forms	University of Nevada, Las Vegas			Document	AFCI	FY2009
Optimizing Neutron Thermal Scattering Effects in Very High Temperature Reactors	North Carolina State University			Document	NGNP	FY2009
Advanced Elastic/Inelastic Nuclear Data Development Project	Idaho State University			Document	AFCI	FY2009
Heterogeneous Recycling in Fast Reactors	Massachusetts Institute of Technology			Document	AFCI	FY2009
Quantification of UV-Visible and Laser Spectroscopic Techniques for Materials Accountability and Process Control	University of Nevada, Las Vegas			Document	AFCI	FY2009
Multiaxial Creep-Fatigue and CreepRatcheting Failures of Grade 91 and Haynes 230 Alloys Toward Addressing Design Issues of Gen IV Nuclear Power Plants	North Carolina State University			Document	NGNP	FY2009
Thermodynamic Development of Corrosion Rate Modeling in Iron Phosphate Glasses	Missouri University of Science and Technology			Document	AFCI	FY2009
Development of Subspace-Based Hybrid Monte Carlo-Deterministic Algorithms for Reactor Physics Calculations	North Carolina State University			Document	AFCI	FY2009
High-Fidelity Space-Time Adaptive Multiphysics Simulations in Nuclear Engineering	University of Nevada, Reno			Document	AFCI	FY2009
Improvements to Nuclear Data and Its Uncertainties by Theoretical Modeling	Rensselaer Polytechnic Institute			Document	AFCI	FY2009
Investigation of Countercurrent Helium-air Flows in Air-ingress Accidents for VHTRs	Ohio State University			Document	NGNP	FY2009
Sharp Interface Tracking in Rotating Microflows of Solvent Extraction	State University of New York at Stony Brook			Document	AFCI	FY2009
Bulk Nanostructured FCC Steels with Enhanced Radiation Tolerance	Texas A&M University			Document	AFCI	FY2009
Simulations of Failure via Three-Dimensional Cracking in Fuel Cladding for Advanced Nuclear Fuels	University of Texas, Dallas			Document	AFCI	FY2009
Testing of Performance of Optical Fibers Under Irradiation in Intense Radiation Fields, When Subjected to Very High Temperatures	Ohio State University			Document	NGNP	FY2009
Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels	Texas A&M University			Document	AFCI	FY2009
SiC Schottky Diode Detectors for Measurement of Actinide Concentrations from Alpha Activities in Molten Salt Electrolyte	The Ohio State University			Document	AFCI	FY2009
Computational Design of Advanced Nuclear Fuels	University of California, Davis			Document	AFCI	FY2009
Advanced Mesh-Enabled Monte Carlo Capability for Multi-Physics Reactor Analysis	University of Wisconsin, Madison			Document	AFCI	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
A Distributed Fiber Optic Sensor Network for Online 3-D Temperature and Neutron Fluence Mapping in a VHTR Environment	Texas A&M University			Document	NGNP	FY2009
Ab Initio Enhanced Calphad Modeling of Actinide Rich Nuclear Fuels	University of Wisconsin, Madison			Document	AFCI	FY2009
Investigation on the Core Bypass Flow in a Very High Temperature Reactor	Texas A&M University			Document	NGNP	FY2009
Development of Diffusion Barrier Coatings and Deposition Technologies for Mitigating Fuel Cladding Chemical Interactions (FCCI)	University of Wisconsin, Madison			Document	AFCI	FY2009
CFD Model Development and Validation for High Temperature Gas Cooled Reactor Cavity Cooling System (RCCS) Applications	Texas A&M University			Document	NGNP	FY2009
Thermal Properties of LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin, Madison			Document	AFCI	FY2009
Study of Air ingress across the duct during the accident conditions	Texas A&M University			Document	NGNP	FY2009
Verification of the CENTRM Module for Adaptation of the SCALE Code to NGNP Prismatic and PBR Core Designs	University of Arizona			Document	NGNP	FY2009
Integral and Separate Effects Tests for Thermal Hydraulics Code Validation for Liquid-Salt Cooled Nuclear Reactors	University of California, Berkeley			Document	NGNP	FY2009
Mechanisms Governing the Creep Behavior of High Temperature Alloys for Generation IV Nuclear Energy Systems	University of Cincinnati			Document	NGNP	FY2009
ALD Produced B2O3, Al2O3 and TiO2 Coatings on Gd2O3 Burnable Poison Nanoparticles	University of Colorado, Boulder			Document	NGNP	FY2009
Experimental Study and Computational Simulations of Key Pebble Bed Thermomechanics Issues for Design and Safety	University of Idaho			Document	NGNP	FY2009
Prediction and Monitoring Systems of Creep-Fracture Behavior of 9Cr-1Mo Steels for Reactor Pressure Vessels	University of Idaho			Document	NGNP	FY2009
Understanding Fundamental Material Degradation Processes in High Temperature Aggressive Chemomechanical Environments	University of Illinois, Urbana-Champaign			Document	NGNP	FY2009
Multi-Scale Multi-physics Methods Development for the Calculation of Hot-Spots in the NGNP	University of Michigan			Document	NGNP	FY2009
Corrosion and Creep of Candidate Alloys in High Temperature Helium and Steam Environments for the NGNP	University of Michigan			Document	NGNP	FY2009
Creation of a Full-Core HTR Benchmark with the Fort St. Vrain Initial Core and Validation of the DHF Method with Helios for NGNP Configurations	University of Michigan			Document	NGNP	FY2009
Fission Product Sorptivity in Graphite	University of Missouri, Columbia			Document	NGNP	FY2009
Identifying and Understanding Environment-Induced Crack Propagation Behavior in Ni-Based Superalloy INCONEL 617	University of Nevada, Las Vegas			Document	NGNP	FY2009
Graphite Oxidation Simulation in HTR Accident Conditions	University of New Mexico			Document	NGNP	FY2009
Non Destructive Thermal Analysis and In Situ Investigation of Creep Mechanism of Graphite and Ceramic Composites using Phase-sensitive THz Imaging & Nonlinear Resonant Ultrasonic Spectroscopy	University of Rochester			Document	NGNP	FY2009
Tritium Sequestration in Gen IV NGNP Gas Stream via Proton Conducting Ceramic Pumps	University of South Carolina			Document	NGNP	FY2009
Materials, Turbomachinery and Heat Exchangers for Supercritical CO2 Systems	University of Wisconsin, Madison			Document	NGNP	FY2009
Experimental Studies of NGNP Reactor Cavity Cooling System with Water	University of Wisconsin, Madison			Document	NGNP	FY2009
Assessment of Embrittlement of VHTR Structural Alloys in Impure Helium Environments	University of Wisconsin, Madison			Document	NGNP	FY2009
Modeling Fission Product Sorption in Graphite Structures	University of Wisconsin, Madison			Document	NGNP	FY2009
Liquid Salt Heat Exchanger Technology for VHTR Based Applications	University of Wisconsin, Madison			Document	NGNP	FY2009
Effect of Post-Weld Heat Treatment on Creep Rupture Properties of Grade 91 Steel Heavy Section Welds	Utah State University			Document	NGNP	FY2009
Alpha Radiolysis of Nuclear Solvent Extraction Ligands used for An(III) and Ln(III) Separations	California State University, Long Beach	$1,390,252		Document	FCR&D	FY2010
Predictive Maturity of Multi-Scale Simulation Models for Fuel Performance	Clemson University	$614,690		Document	FCR&D	FY2010
Freeze-casting as a Novel Manufacturing Process for Fast Reactor Fuels	Drexel University	$1,149,327		Document	FCR&D	FY2010
Fuel Performance Experiments on the Atomistic Level, Studying Fuel Through Engineered Single Crystal UO2	Idaho State University	$650,000		Document	FCR&D	FY2010
Development of A Self Biased High Efficiency Solid-State Neutron Detector for MPACT Applications	Rensselaer Polytechnic Institute	$810,141		Document	FCR&D	FY2010
Development of a Innovative High Thermal Conductivity UO 2 Ceramic Composites Fuel Pellets with Carbon Nano-Tubes Using Spark Plasma Sintering	University of Florida	$894,042		Document	FCR&D	FY2010
Exploration and Modeling of Structural Changes in Waste Glass under Corrosion	Pennsylvania State University	$1,377,444		Document	FCR&D	FY2010
Evaluation of materials for interim storage of spent fuel for more than 100 years	University of Michigan	$931,603		Document	FCR&D	FY2010
Implementation of On-the-Fly Doppler Broadening in MCNP5 for Multiphysics Simulation of Nuclear Reactors	University of Michigan	$406,712		Document	FCR&D	FY2010
Methods and tools to allow molecular flow simulations to be coupled to higher level continuum descriptions of flows in porous/fractured media and aerosol/dust dynamics	University of Missouri-Columbi	$541,286		Document	FCR&D	FY2010
Characterization and Modeling of Materials for Kr-Xe Separations	University of Nevada-Las Vegas	$989,800		Document	FCR&D	FY2010
Modeling Solute Thermokinetics in LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin-Madison	$616,073		Document	FCR&D	FY2010
Advanced Aqueous Separation Systems for Actinide Partitioning: Develop Fundamental Understanding of An(III)/Ln(III) Separation	Washington State University	$1,451,784		Document	FCR&D	FY2010
Consistent Multigroup Theory Enabling Accurate Coarse-Group Simulation of GenIV Reactors	Georgia Institute of Technology	$1,046,277		Document	GEN IV	FY2010
Studies of Deteriorated Heat Transfer in Prismatic Cores Stemming from Irradiation-Induced Geometry Distortion	Idaho State University	$1,287,921		Document	GEN IV	FY2010
Carbide Coatings for Nickel Alloys, Graphite, and Carbon/Carbon Composites to be Used in Fluoride Salt Valves	Johns Hopkins University	$1,183,239		Document	GEN IV	FY2010
Design, Testing, and Modeling of the Direct Reactor Auxiliary Cooling System for AHTRs	Ohio State University	$1,366,627		Document	GEN IV	FY2010
Monitoring microstructural evolution of Alloy 617 with nonlinear acoustics for remaining useful life prediction; multiaxial creep-fatigue and creep-ratcheting	Pennsylvania State University	$1,000,000		Document	GEN IV	FY2010
Development and Validation of Multidimensional Models of Supercritical CO 2 Energy Conversion Systems for Nuclear Power Reactors	Rensselaer Polytechnic Institute	$475,005		Document	GEN IV	FY2010
Multiscale Concrete Modeling for Aging Degradation	Mississippi State University	$345,941		Document	LWRS	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term and Elevated Temperature Irradiation: Modeling and Experimental Investigation	University of California-Berkeley	$1,320,667		Document	GEN IV	FY2010
Development of an advanced computational fluid dynamics technology for the next-generation nuclear reactor system analysis and safety margin characterization code	North Carolina State University	$418,199		Document	LWRS	FY2010
Development of Barrier Layers for the Protection of Candidate Alloys in the VHTR	University of California-Santa Barbara	$995,232		Document	GEN IV	FY2010
Precursor Derived Nanostructured Si-C-X Materials for Nuclear Applications	University of Washington	$899,518		Document	MRIIR	FY2010
Investigation of a Novel NDE Method for Monitoring Thermo-Mechanical Damage and Microstructure Evolution in Ferritic-Martensitic Steels for Generation IV Nuclear Energy Systems	University of Cincinnati	$833,109		Document	GEN IV	FY2010
Development and Testing of an Open-Loop Oscillator for Small Reactivity Worth Samples	Idaho State University	$597,252		Document	MRIIR	FY2010
Fission Product Transport in TRISO Particle Layers under Operating and Off-Normal Conditions	University of Michigan	$966,581		Document	GEN IV	FY2010
Understanding the Irradiation Behavior of Zirconium Carbide	Pennsylvania State University	$870,613		Document	MRIIR	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term Irradiation at Elevated Temperature: Critical Experiments	University of Michigan	$1,181,379		Document	GEN IV	FY2010
Modeling investigation of the stability and irradiation-induced evolution of nanoscale precipitates in advanced structural materials	University of Tennessee-Knoxville	$380,653		Document	MRIIR	FY2010
Three-dimensional NDE of VHTR Core Components via Simulation-based Testing	University of Minnesota	$1,366,163		Document	GEN IV	FY2010
Investigation of Laser Shock Peening for Enhancing Fatigue and Stress Corrosion Cracking Resistance of Nuclear Energy Materials	University of Cincinnati	$1,242,019		Document	MRIIR	FY2010
Failure Predictions for VHTR Core Components using a Probabilistic Continuum Damage Mechanics Model	University of Minnesota	$854,542		Document	GEN IV	FY2010
Irradiation Accelerated Corrosion of Reactor Core Materials	University of Michigan	$798,943		Document	MRIIR	FY2010
Development of a Scanning Microscale Fast Neutron Irradiation Platform for Examining the Correlation Between Local Neutron Damage and Graphite Microstructure	University of Missouri-Columbia	$703,064		Document	GEN IV	FY2010
Study of Interfacial Interactions using Thin Film Surface Modification: Radiation and Oxidation Effects in Materials	University of Wisconsin-Madison	$538,032		Document	MRIIR	FY2010
Development of Thermal Transient Flow Rate Sensors for High Temperature, Irradiation, Corrosive Environment	University of Nevada-Las Vegas	$451,269		Document	GEN IV	FY2010
Novel Engineered Refractory Materials for Advanced Reactor Applications	North Carolina State University	$1,129,304		Document	MRIIR	FY2010
Novel Methods of Tritium Sequestration: High Temperature Gettering and Separation Membrane Materials Discovery for Nuclear Energy Systems	University of South Carolina	$1,366,626		Document	GEN IV	FY2010
Heat Transfer Salts for Nuclear Reactor Systems - Chemistry Control, Corrosion Mitigation, and Modeling	University of Wisconsin-Madison	$1,352,040		Document	GEN IV	FY2010
Pulsed Magnetic Welding for Advanced Core and Cladding Steels	University of Wisconsin-Madison	$525,206		Document	GEN IV	FY2010
Corrosion in Supercritical Carbon Dioxide: Materials, Environmental Purity, Surface Treatments, and Flow Issues	University of Wisconsin-Madison	$651,447		Document	GEN IV	FY2010
Quantification of Cation Sorption to Engineered Barrier Materials Under Extreme Conditions	Clemson University	$1,171,380		Document	FCR&D	FY2011
In-Pile Instrumentation Multi-Parameter System Utilizing Photonic Fibers and Nanovision	Idaho State University	$1,199,990		Document	FCR&D	FY2011
Development of Plasmonically Cloaked Nanoparticles	Idaho State University	$800,000		Document	FCR&D	FY2011
Fission Product Transmutation in Mixed Radiation Fields	Idaho State University	$800,000		Document	FCR&D	FY2011
Life Prediction of Spent Fuel Storage Canister Material	Massachusetts Institute of Technology	$899,826		Document	FCR&D	FY2011
Active Interrogation using Photofission Technique for Nuclear Materials Control and Accountability	Oregon State University	$900,000		Document	FCR&D	FY2011
Anisotropic Azimuthal Power and Temperature Distribution on Fuel Rod: Impact of Hydride Distribution	Pennsylvania State University	$631,956		Document	FCR&D	FY2011
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$1,000,000		Document	FCR&D	FY2011
Recovery of Uranium from Seawater: Preparation and Development of Polymer-Supported Extractants	City College of New York, Hunter	$363,716		Document	MSTR	FY2011
Microemulsions and Aggregation Formation in Extraction Processes for Used Nuclear Fuel: Thermodynamics and Structural Studies	University of California, Irvine	$1,000,000		Document	FCR&D	FY2011
One-Dimensional Nanostructures for Neutron Detection	North Carolina State University	$455,629		Document	MSTR	FY2011
Optimized Processing Fabrication Paths for Larger Heats of Nanostructured Ferritic Alloys	University of California, Santa Barbara	$1,000,000		Document	FCR&D	FY2011
Feasibility and Safety Assessment for Advanced Reactor Concepts Using Vented Fuel	Oregon State University	$600,000		Document	MSTR	FY2011
Basic Physics Data: Measurement of Neutron Multiplicity from Induced Fission	University of Michigan	$973,364		Document	FCR&D	FY2011
Development of an Efficient Meso-Scale Multi-Phase Flow Solver in Nuclear Applications	City College of New York	$505,858		Document	NEAMS	FY2011
High Temperature Transducers for Online Monitoring of Microstructure Evolution	Pennsylvania State University	$455,628		Document	MSTR	FY2011
Radionuclide Incorporation and Long Term Performance of Apatite Waste Forms	University of Michigan	$862,500		Document	FCR&D	FY2011
Multiscale Modeling and Uncertainty Quantification for Nuclear Fuel Performance	Colorado State University	$1,098,250		Document	NEAMS	FY2011
Laser-Arc Hybrid Welding of Thick Section Ni-base Alloys- Advanced Modeling and Experiments	Pennsylvania State University	$536,117		Document	MSTR	FY2011
Actinide Foil Production for MPACT Research	University of Nevada-Las Vegas	$156,897		Document	FCR&D	FY2011
Fundamental Studies of the Role of Grain Boundaries on Uniform Corrosion of Advanced Nuclear Reactor Materials	Drexel University	$1,098,250		Document	NEAMS	FY2011
Correlates of Sensitive Technologies	Texas A&M University	$509,467		Document	MSTR	FY2011
Enriched Boron-Doped Amorphous Selenium Based Position-Sensitive Solid-State Thermal Neutron Detector for MPACT Applications	University of South Carolina	$1,000,000		Document	FCR&D	FY2011
Phenomena-based Uncertainty Quantification in Predictive Coupled-Physics Reactor Simulations	Texas A&M University	$1,098,250		Document	NEAMS	FY2011
Improved Safety Margin Characterization of Risk from Loss of Offsite Power	Texas A&M University	$600,000		Document	MSTR	FY2011
Development of Advanced High Uranium Density Fuels for Light Water Reactors	University of Wisconsin-Madison	$1,000,000		Document	FCR&D	FY2011
Characterization of Modeling of Grain Boundary Chemistry Evolution in Ferritic Steels Under Irradiation	University of Michigan	$1,098,250		Document	NEAMS	FY2011
Diffusion, Thermal Properties and chemical Compatibilities of Select MAX Phases with Materials for Advanced Nuclear Systems	Drexel University	$535,927		Document	NEET	FY2011
A High Temperature-Tolerant and Radiation-Resistant In-Core Neutron Sensor for Advanced Reactors	The Ohio State University	$455,629		Document	MSTR	FY2011
Developing the User Experience for a Next Generation Nuclear Fuel Cycle Simulator	University of Wisconsin-Madison	$1,200,000		Document	FCR&D	FY2011
Development of Multiscale Materials Modeling Techniques and Coarse-Graining Strategies for Predicting Materials Degradation in Extreme Irradiation Environments	University of Tennessee, Knoxville	$750,000		Document	NEAMS	FY2011
A New Light Weight Structural Material for Nuclear Structures	North Carolina State University	$399,490		Document	NEET	FY2011
Pathway Aggregation in the Risk Assessment of Proliferation Resistance and Physical Protection (PR&PP) of Nuclear Energy Systems	The Ohio State University	$534,471		Document	MSTR	FY2011
Experimental Investigation of Convection and Heat Transfer in the Reactor Core for a VHTR	City College of New York	$1,118,856		Document	RCRD&D	FY2011
Preparation of High Purity, High Molecular-Weight Chitin from Ionic Liquids for Use as an Adsorbate for the Extraction of Uranium from Seawater	University of Alabama	$338,260		Document	MSTR	FY2011
Graphite Microstructural Characterization Using Time-Domain and Correlation-Based Ultrasonics	Johns Hopkins University	$1,199,997		Document	RCRD&D	FY2011
Selectivity in Ligand Binding to Uranyl Compounds: A Synthetic, Structural, Thermodynamic and Computational Study	University of California-Berkeley	$500,000		Document	MSTR	FY2011
Methodology Development for Passive Component Reliability Modeling in a Multi-Physics Simulation Environment	The Ohio State University	$533,457		Document	RCRD&D	FY2011
Development of Seismic Isolation Systems Using Periodic Materials	University of Houston	$538,154		Document	MSTR	FY2011
Pebble Fuel Handling and Reactivity Control for Salt-Cooled High Temperature Reactors	University of California, Berkeley	$612,721		Document	RCRD&D	FY2011
Innovative Elution Processes for Recovering Uranium from Seawater	University of Idaho	$400,000		Document	MSTR	FY2011
Self-Sustaining Thorium Boiling Water Reactors	University of California, Berkeley	$1,145,932		Document	RCRD&D	FY2011
Development of Austenitic ODS Strengthened Alloys for Very High Temperature Applications	University of Illinois-Urbana Champaign	$538,154		Document	MSTR	FY2011
High Fluency Low Flux Embrittlement Models of LWR Reactor Pressure Vessel Embrittlement and a Supporting Database from the UCSB ATR-2 Irradiation Experiment	University of California, Santa Barbara	$1,199,607		Document	RCRD&D	FY2011
Enhancement of the Extraction of the Uranium from Seawater	University of Maryland	$400,000		Document	MSTR	FY2011
A Research Program for Fission Product/Dust Transport in HTGR's	University of Missouri-Columbia	$1,157,367		Document	RCRD&D	FY2011
Transient Safety Analysis of Fast Spectrum TRU Burning LWR with Internal Blankets	University of Michigan	$599,475		Document	MSTR	FY2011
Development and Validation of a Lifecycle-based Prognostics Architecture with Test Bed Validation	University of Tennessee, Knoxville	$846,315		Document	RCRD&D	FY2011
Development of Novel Sorbents for Uranium Extraction from Seawater	University of North Carolina, Chapel Hill	$400,000		Document	MSTR	FY2011
In-situ Condition Monitoring of Components in Small Modular Reactors Using Process and Electrical Signature Analysis	University of Tennessee, Knoxville	$650,000		Document	RCRD&D	FY2011
Radiation Behavior of High-Entropy Alloys for Advanced Reactors	University of Tennessee, Knoxville	$538,159		Document	MSTR	FY2011
Technical Development for S-CO2 Advanced Energy Conversion	University of Wisconsin	$815,000		Document	RCRD&D	FY2011
Rapid Computer Aided Ligand Design and Screening of Precious Metal Extractants from TRUEX Raffinate with Experimental Validation	Washington State University	$500,000		Document	MSTR	FY2011
Ag Transport Through Non-Irradiated and Irradiated SiC	University of Wisconsin-Madison	$1,055,456		Document	RCRD&D	FY2011
Critical Heat Flux Phenomena at High Pressure and Low Mass Fluxes: Tests and Models	University of Wisconsin-Madison	$1,199,781		Document	RCRD&D	FY2011
Modeling and Test Validation of a Reactor Cavity Cooling System with Air	University of Wisconsin-Madison	$1,199,988		Document	RCRD&D	FY2011
Transient Mixed Convection Validation for NGNP	Utah State University	$635,860		Document	RCRD&D	FY2011
Alternative High-Performance Ceramic Waste Forms	Alfred University	$840,000	This project aims to advance fundamental understanding of the kinetics of structural evolution of crystalline ceramic waste forms. The structure/property relationships will be identified and will reveal new formulations, improved processing routes, and strategies for improved performance or ceramic waste forms.	Document	FCR&D	FY2012
Surface Layer Bulk Glass Interface Evolution with Aqueous Corrosion	Alfred University	$880,000	This project will investigate the links between the morphology, structure and chemistry of surface layer-bulk glass interface and the long-term corrosion-reaction kinetics using in-situ and ex-situ experiments. The understanding will result in improved models for long-term predictive behavior of high-level-waste (HLW) glasses under repository conditions.	Document	FCR&D	FY2012
Improved Accident Tolerance of Austenitic Stainless Steel Cladding through Colossal Supersaturation with Interstitial Solutes	Case Western Reserve University	$850,000	This project aims to develop new case-hardened austenitic stainless steels by saturating them with materials that improve their mechanical properties, corrosion resistance and radiation resistance. This project, if successful, will result in safer, longer-lasting, and more accident tolerant fuel claddings.	Document	FCR&D	FY2012
Optimization of Deep Borehole Systems for HLW Disposal	Massachusetts Institute of Technology	$850,000	Researchers aim to carry out a comprehensive evaluation of the deep borehole option for disposal of used nuclear fuel and high livel waste. The models developed will predict potential movement of water through natural and engineered barriers and release of radionuclides to the biosphere which will aide in site selection.	Document	FCR&D	FY2012
Scholarship for Nuclear Communications and Methods for Evaluation of Nuclear Project Acceptability	Massachusetts Institute of Technology	$800,000	Researchers will work to develop a model to characterize the factors affecting social acceptance of nuclear projects with potential stakeholders. The resultant model will strengthen the ability to design and implement large projects more efficiently, leading to higher rates of success of future nuclear projects.	Document	FCR&D	FY2012
Accurate Holdup Calculations with Predictive Modeling and Data Integration	North Carolina State University	$875,000	Researchers will develop and use state-of-the-art radiation transport codes to account accurately for the fissile material in a nuclear materials processing facility. An accurate estimation of the materials will allow for ensured radiological safety, security, waste management and efficient plant operation.	Document	FCR&D	FY2012
Novel Metal Sulfides to Achieve Effective Capture and Durable Consolidation of Radionuclides	Northwestern University	$760,000	Researchers will evaluate the effectiveness of chalcogenide based materials design novel metal sulfides to effectively capture and store of radioisotopes released during reprocessing of used nuclear fuel. This project will focus on understanding structure-property relationships to enable refined and direct synthesis approaches for improved and cost-efficient nuclear waste forms.	Document	FCR&D	FY2012
Nonlinear Ultrasonic Diagnosis and Prognosis of ASR Damage in Dry Cask Storage	Northwestern University	$885,000	Researchers aim to use nondestructive damage characterization methods to detect, manage and mitigate the degradation/damage mechanisms of dry cask storage systems for nuclear fuels. This project, if successful, will provide tools that will allow the prediction of the reliability and the safety of concrete structures in dry cask storage systems.	Document	FCR&D	FY2012
Prototype Demonstration of Gamma-Blind Tensioned Metastable Fluid Neutron/Multiplicity/Alpha Detector- Real Time Methods for Advanced Fuel Cycle Applications	Texas A&M University	$875,000	This project aims to create a prototype demonstration of a novel neutron/alpha detector based on a technology that is blind to gamma field used fuel. The prototype, if successful, will enhance instrumentation for monitoring real-time material balance during various stages of the nuclear cycle.	Document	FCR&D	FY2012
Testing of Sapphire Optical Fiber and Sensors in Intense Radiation Fields, when Subjected to Very High Temperatures	The Ohio State University	$885,000	The researchers on this project will investigate the performance of sapphire optical fibers and sensors in reactor environments. The project, if successful, will result in improved instrumentation to understand the behavior and predict performance of nuclear fuel systems at the microstructural level.	Document	FCR&D	FY2012
Concrete Materials with Ultra-High Damage Resistance and Self-Sensing Capacity for Extended Nuclear Fuel Storage Systems	University of California, Irvine	$800,000	Researchers aim to design a new class of multifunctional concrete materials. This project, if successful, will result in a novel multifunctional concrete material that possesses inherent degradation monitoring capability and is suitable for an extended storage system for the used nuclear fuel.	Document	FCR&D	FY2012
Development of Innovative Accident Tolerant High Thermal Conductivity UO2 Fuel Pellets with a Diamond Dopant	University of Florida	$800,000	Researchers will evaluate the use of diamond nanoparticles composite material in innovative accident tolerant fuel pellets. This could significantly improve both the thermal conductivity of fuel pellets and light water reactors' efficiency safety.	Document	FCR&D	FY2012
Probabilistic Multi-Hazard Assessment of Dry Cask Structures	University of Houston	$865,000	This project aims to investigate the performance of dry cask storage systems under multiple hazard systems (earthquake, tornados, combined with aging effects) using a probabilistic multi-hazard framework. This framework will be validated based on experimental research and will provide improved models for safety and reliability of spent nuclear fuels during storage and transportation.	Document	FCR&D	FY2012
Measurement of Irradiated Pyroprocessing Samples via Laser Induced Breakdown Spectroscopy	University of Idaho	$820,000	This project aims to use advanced characterization techniques to investigate microstructural changes and the micromechanisms related to irradiation induced damage in used nuclear fuels and waste forms. This project, if successful, will result in enhanced models to predict the structural and chemical response of used fuel and waster forms during interim storage and permanent disposal.	Document	FCR&D	FY2012
Elastic/Inelastic Measurement Project	University of Kentucky	$880,523	Researchers will measure nuclear data for elastic/inelastic scattered neutrons on coolants and structural materials. The data generated, will be useful for future R&D programs that will study innovative next generation LWR and future fast systems.	Document	FCR&D	FY2012
Electrochemical Corrosion Studies for Modeling Metallic Waste Form Release Rates	University of Nevada- Las Vegas	$790,000	This project aims to use advanced electrochemical methods to investigate the corrosion related degradation of metal alloys used for housing fission products. The data obtained from this study will allow for the prediction of the long-term behavior of the metallic host phase materials over geological time-scales.	Document	FCR&D	FY2012
Thermodynamic and Microstructural Mechanisms in the Corrosion of Advanced Ceramic Tc-bearing Waste Forms and Thermophysical Properties	University of Nevada- Las Vegas	$795,000	This project team will harvest thermodynamic and microstructural data on the evolution of ceramic based waste forms. The data will be used to advance the current state-of-the-art methodology used for isolation and stabilization of fission products and improve on nuclear fuel recycling processes.	Document	FCR&D	FY2012
Development and Experimental Benchmark of Simulations to Predict Used Nuclear Fuel Cladding Temperatures during Drying and Transfer Operations	University of Nevada- Reno	$745,000	Researchers will conduct experiments to investigate and develop advanced computational models of heat transfer in post-pool-storage drying operations. This project, if successful, will result in tools that can be used to design efficient drying processes to as to ensure suitability for dry-cask systems for long-term storage and transport.	Document	FCR&D	FY2012
Better Radiation Response and Accident Tolerance of Nanostructured Ceramic Fuel Materials?	University of Tennessee	$815,000	Researchers will use novel experimental methods to investigate the links between microstructure, phase stability and damage evolution in nanostructured ceramic fuel materials. The project will study fuel materials at temperatures and irradiation conditions relevant to operation and accidental scenarios.	Document	FCR&D	FY2012
Radiation and Thermal Effects on Used Nuclear Fuel and Nuclear Waste Forms	University of Tennesssee	$770,000	This project aims to investigate the structural and chemical response of used nuclear fuel and waste forms during interim storage and permanent disposal. If successful, this project will generate models that will allow the prediction of structural evolution and hence the radiological safety and security of nuclear fuel and waste forms.	Document	FCR&D	FY2012
Seismic Performance of Dry Casks Storage for Long-Term Exposure	University of Utah	$873,319	Researchers will evaluate the mechanical performance of dry-cask storage under seismic loading for mid-term operational periods. Simulations will include scenarios for freestanding, anchored, and vaulted casks. The experimental tests will also evaluate the dynamic seismic response of freestanding and anchored dry-cask storage prototypes, providing recommendations for optimal Interim Spent Fuel Storage Installations (ISFSIs) design.	Document	FCR&D	FY2012
Validation Experiments for Spent-Fuel Dry-Cask In-Basket Convection	Utah State University	$690,000	Researchers in this project aim to conduct experiments that generate data on natural convection through a fuel assembly. The data will be used to validate the computational models being developed for nuclear safety and design.	Document	FCR&D	FY2012
Re-Branding the Nuclear Fuel Cycle	Virginia Commonwealth University	$850,000	This project will create a comprehensive framework for the evaluation of alternative fuel cycle systems that will be used to identify and analyze key elements related to long-term management of nuclear fuels , with the ultimate goal to develop a communications strategy to reach stakeholders.	Document	FCR&D	FY2012
Advanced Characterization of Molecular Interactions in TALSPEAK-like Separations Systems	Washington State University	$875,000	Researchers will use advanced characterization techniques (experimental and computational) to improve understanding of the molecular level processes/interactions during separation processes for advanced fuel cycles. The understanding of these interactions will be used to develop more robust and streamlined separation processes for advanced fuel cycles.	Document	FCR&D	FY2012
Coupling of Nuclear Waste Form Corrosion and Radionuclide Transport in Presence of Relevant Repository Sediments	Washington State University	$885,000	Researchers will conduct experiments to understand the mechanisms responsible for the corrosion of nuclear waste forms in realistic chemical environments. The data generated from these experiments will enable increased reliability of the models used to predict the waste form performance in repository environments.	Document	FCR&D	FY2012
Stationary Liquid Fuel Fast Reactor (SLFFR) Concept for TRU Burning	Purdue University	$450,000	Reasearchers will investigate a new type of molten metallic fuel reactor concept that will consume hazardous transuranic waste. The liquid fuel alloy has several advantages over solid fuel fast reactors that are used for the same purpose.	Document	MSTR	FY2012
ABR for TRU Transmutation with Breed & Burn Thorium Blanket for Improved Economics and Resource Utilization	University of California- Berkeley	$450,000	The research team will use detailed neutronic analysis for a new Advanced Burner Reactor concept with low conversion ratio. The concept will use a new core shape to improve the utilization of neutrons to perform breed and burn.	Document	MSTR	FY2012
New Materials for High Temperature Thermoelecric Power Generation	University of California, Davis	$450,000	Reasearchers will work to develop nanostructured and other new materials to support the development of higher efficiency thermoelectric devices. These devices convert thermal energy to electricity with no moving parts. The new materials will operate at higher efficiencies and over a wider temperature range than those currently available--an important quality for future nuclear-powered deep space exploration.	Document	MSTR	FY2012
Microscopic Fuel Particles Produced by Self-Assembly of Actinide Nanoclusters on Carbon Nanomaterials	University of Notre Dame	$440,000	Reasearchers will develop the mechanisms, conditions and protocols to prepare uranium-carbon nanocomposite materials to make them more flexible. This could result in the generation of wholesale electricity, providing process heat, and providing power for households.	Document	MSTR	FY2012
High Hydrogen Content Graphene Hydride Compounds & High Cross-Section Cladding Coatings for Fast Neutron Detection	University of South Carolina	$430,000	This project will exploit recent breakthroughs to grow epitaxial graphene on commercial SiC wafers. This will allow researchers to develop a new detection method for fast neutrons. In addition, it will lead to better and more compact neutron detection system.	Document	MSTR	FY2012
Reducing Actinide Production Using Inert Matrix Fuels	University of Texas- Austin	$435,000	Reasearchers will perform a neutronic analysis, a thermal-hydraulic analysis and a simulation of fuel decay heat as a functionof fuel burnup, to determine if inert matrix fuel in coventional reactors will continue to be licensable. If successful, the inert matrix fuel mixtures will reduce harmful transuranic components in the fuel discharge streams at a level comparable to a fast reactcor burner.	Document	MSTR	FY2012
An Integrated Fuel Depletion Calculator for Fuel Cycle Options Analysis	University of Texas- Austin	$395,000	Reasearchers use new analysis techniques to better predict nuclear fuel behavior. The new model will allow improved fuel cycle for a larger number of users.	Document	MSTR	FY2012
Atomic-Scale to Meso-Scale Simulation Studies of Thermal Ageing and Irradiation Effects in Fe-Cr Alloys	Boston University	$874,997	Reasearchers will develop predictive, multi-scale simulation tools for iron-chromium alloys, which are expected to be key components of advanced steels envisioned as fuel cladding and structural components for Generation IV reactors. Such modeling is necessary to avoid resource intensive and costly thermal and neutron irradiation experiments to obtain required performance data.	Document	NEAMS	FY2012
Validation Data and Model Development for Fuel Assembly Response to Seismic Loads	George Washington University	$862,435	Reasearchers will conduct experiments that will provide comprehensive data characterizing the dynamics of the fluid and the structure in Pressurized Water Reactors (PWR) fuel assemblies under seismic loads (earthquakes and loss of coolant accidents). Completion of their project will greatly benefit the safety of existing and future nuclear reactors.	Document	NEAMS	FY2012
Uncertainty Quantification and Management for Multiscale Nuclear Materials Modeling	Georgia Institute of Technology	$743,444	Reasearchers will address the question of uncertainty propogation and error estimates associated with model prediction of material behavior under irradiation. Their work will facilitate a better understanding of the connection of various unit processes to collective responses in a multiscale model chain enabling the development of high strength and high ductility materials.	Document	NEAMS	FY2012
Fuel and Core Design Options to Overcome the Heavy Metal Loading Limit and Improve Performance and Safety of Liquid Salt Cooled Reactors	Georgia Insitute of Technology	$784,689	Reasearchers will examine new options for fuel and core designs in liquid salt cooled reactors where the current standard of TRISO type fuel has limitations due to loading characteristics. The research could enable new, more feasible fuel-core-reload options that will improve safety and performance parameters.	Document	RCRD&D	FY2012
Nonlinear Ultrasonic Techniques to Monitor Radiation Damage in RPV and Internal Components	Georgia Institute of Technology	$877,000	Reasearchers will explore new nondestructive materials evaluation and monitoring techniques utilizing nonlinear ultrasonic measurements . This technique will allow researchers to assess remaining useful life of select reactor components. Breakthroughs in this area will lead to the ability to characterize radiation damage in reactor pressure vessels and other components-leading to a clearer definition of reactor safety margins.	Document	RCRD&D	FY2012
Intergral Reactor Containment Condensation Model and Experimental Validation	Oregon State University	$871,119	Reasearchers will conduct experiments to enhance the safety and efficiency of small modular reactors (SMRs). This project will assess the impact of high-pressure steam condensation on steel containment vessels to be used for SMR deigns.	Document	RCRD&D	FY2012
Investigation of Natural Circulation Instability and Transients in Passively Safe Small Modular Reactors	Purdue University	$871,100	Reasearchers will perform scaled experiments to study the thermal-hydraulic instabilities that can occur in Small Modular Reactors (SMR) which rely on natural circulation cooling during normal operation and accident conditions. Their work will not only improve our understanding of general natural circulation instability but also lead to the development of stability criteria and predictability in the operation of SMRÃs.	Document	RCRD&D	FY2012
Thermoelectric-Driven Sustainable Sensing and Actuation Systems for Fault-Tolerant Nuclear Incidents	State University of New York, Stony Brook	$599,802	Reasearchers will examine the use of solid-state thermoelectric generators to produce electricity to sense and opeate during both normal and abnormal situations. This will provide indefinite monitoring of key components during power outages or station blackouts.	Document	RCRD&D	FY2012
Experimental and CFD Studies of Coolant Flow Mixing within Scaled Models of the Upper and Lower Plenums of NGNP Gas-Cooled Reactors	Texas A&M University	$713,051	Reasearchers will model the internal coolant flow of a prismatic core very high temperature reactor (VHTR) by using large eddy simulation tools. This method will enable more accurate prediction of flow field characteristics and better evaluation of VHTR behavior under operational and accidental conditions.	Document	RCRD&D	FY2012
Demonstrating Hybrid Heat Transport and Energy Conversion System Performance Characterization Using Intelligent Control Systems	University of Idaho	$877,000	Reasearchers will demonstrate an intelligent control systems in a hybrid energy conversion loop for a next generation nuclear power plant. Hybrid energy systems are a method of optimizing the use of natural resources for energy production. Hybrid systems present an opportunity to develop domestic energy sources to improve energy security.	Document	RCRD&D	FY2012
Advanced Reactor-Intermediate Heat Exchanger (IHX) Coupling: Theoretical Modeling and Experimental Validation	University of Idaho	$869,997	Reasearchers will model the behavior of the Advanced Reactor Intermediate Heat Exchanger Chemical Process system and develop advanced control techniques that take into account abnormal scenarios. The data and information obtained will assist in the development of intelligent control systems for next generation nuclear reactor systems.	Document	RCRD&D	FY2012
Irradiation Performance of Fe-Cr Base Alloys	University of Illinois- Urbana Champaign	$876,332	Reasearchers will perform post-radiation analysis and develop tools for future development and application of the Fe-Cr class of alloys. The results of this research will lead to better modeling of performance and development of an alloy designated as the primary choice for reactor fuel cladding and structural applications in advanced systems.	Document	RCRD&D	FY2012
Accelerated Irradiations for High Dose Microstructures in Fast Reactor Alloys	University of Michigan	$831,876	Reasearchers will determine the extent to which high dose rate irradiation can be used as an irradiation damage tool to understand microstructure evolution at high doses and temperatures relevant to advanced fast reactors. The project will provide fundamental understanding of the effectiveness of this process and thus of microstructure development in irradiated materials.	Document	RCRD&D	FY2012
Mitigating IASCC of Reactor Core Internals by Post-Irradiation Annealing Advanced Mitigation Strategies	University of Michigan	$876,985	Reasearchers will determine the optimum Post-irradiation annealing (PIA)-driven mitigation strategy to extend the potential lifetime of light water reactors. Samples that have already been irradiated in a light water reactor will be used to test PIA treatments to understand IASCC initiation and propoagation, annealing kinetics, the role of microstructure features in irradation hardening and localized deformation, and the optimum mitigation strategy based on PIA.	Document	RCRD&D	FY2012
Experimentally Validated Numerical Models for Effects of Non-Isothermal Turbulent Mixing on Wall Stresses in High Temperature Reactors	University of Pittsburgh	$876,422	Reasearchers will develop a comprehensive experimentally validated computational framework for the turbulent mixing in the lower plenum of a very high temperature reactor (VHTR). Through CFD modeling and experimental validation, the results from this project will lay the groundwork for future stress analysis, failure and fatigue studies, and uncertainty quantification for the VHTR system.	Document	RCRD&D	FY2012
Role of Defects in Swelling and Creep of Irradiated SiC	University of Wisconsin- Madison	$875,350	Reasearchers will study mechanisms controlling both radiation swelling and radiation creep in silicon carbide. These two effects are crucial to understanding the issues associated with the brittle silicon carbide composite. Success in this project will ground progress in the adoption of silicon carbide for reactor solutions, particularly as fuel cladding.	Document	RCRD&D	FY2012
Advanced Supercritical Carbon Dioxide Brayton Cycle Development	University of Wisconsin, Madison	$877,000	Reasearchers will investigate the benefits of utilizing advanced Brayton cycles with supercritical carbon dioxide in new reactor systems and components. Benefits of this research include improvement of analysis and performance of components currently utilizing these cycles as well as the potential for a large scale advanced CO2 power system.	Document	RCRD&D	FY2012
Mechanical Behavior of UO2 at Sub-grain Length Scales: Quantification of Elastic, Plastic and Creep Properties via Microscale Testing	Arizona State University	$800,000	Reasearchers will develop techniques to measure properties at sub-grain scales using depleted Uranium Oxide samples. The project will provide a framework to measure sub-grain scale mechanical properties, as well as provide experimental data to improve the understanding of advanced oxide fuels.	Document	FCR&D	FY2013
The Impacts of Pore-Scale Physical and Chemical Heterogeneities on the Transport of Radionuclide-Carrying Colloids	Colorado School of Mines	$800,000	Reasearchers will identify the dominant transport mechanisms to develop models that predict radionuclide distribution in porous materials. Experimental and computational models will be created that couple pore-scale geometric and interfacial structures. Simulators such as these are a necessary step towards fully predictive models for field-scale applications in the future.	Document	FCR&D	FY2013
Recovery of Uranium from Seawater: Polymer-Supported Aminophosphinates as Selective Extractants	Hunter College, CUNY	$399,999	Reasearchers will prepare a polymer-supported extractant for the recovery of uranium from seawater. The project will focus on primary amines that could provide a 3-fold increase in uranium capture capacity than current methods.	Document	FCR&D	FY2013
In-pile Thermal Conductivity Characterization with Single-laser Heating/Time Resolved Raman	Iowa State University	$800,000	Reasearchers will develop a time-resolved Raman-based thermal conductivity measurement system to improve remote in-pile thermal conductivity measurement. These measurements will provide new insights into the behavior of materials exposed to extreme radiation and temperature environments. Understanding the behavior of materials at the microstructural level will support optimized fuel designs.	Document	FCR&D	FY2013
Organic Speciation and Interactions in ALSEP - One Step Partitioning Process of Minor Actinides, Lanthanides, and Fission Products	Oregon State University	$600,000	Reasearchers will investigate the Actinide-Lanthanide Separation (ALSEP) process organic phase prior to aqueous phase separation and after aqueous separation phases of bare and metal-loaded acids. Quantifying these effects can be used to determine how an engineering scale process will perform and generate an accurate chemical model for the system.	Document	FCR&D	FY2013
Glass Composition and Solution Speciation Effects on Stage III Dissolution	Pennsylvania State University	$700,000	Reasearchers will study the chemical and structural triggers of long-term vitrified nuclear waste form behavior. They will study a range of waste glass compositions in corrosive environments. The study will improve understanding of the long-term residual rate and may provide new options for environmental control of glass dissolution rates.	Document	FCR&D	FY2013
Correlating Thermal, Mechanical, and Electrical Coupling Based Multiphysics Behavior of Nuclear Materials Through In-Situ Measurements	Purdue University	$800,000	Reasearchers will use in-situ experimental techniques to monitor the influence of extreme conditions on fuel cladding. The project will establish an in-situ experimental setup that can predict change in thermal properties and their correlation with mechanical properties and correlate such changes to changes in microstructural and chemical features.	Document	FCR&D	FY2013
Creation of a Geant4 Muon Tomography Package for Imaging of Nuclear Fuel in Dry Cask Storage	Purdue University	$440,000	Reasearchers will develop a simulation and analysis package to aid in the non-destructive assessment of sealed used nuclear fuel dry casks using cosmic ray muons. Cosmic ray muon tomography allows for non-destructive assessment that can independently verify and identify weapons grade material sealed within dense dry casks.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Two-stage Fast Reactor Fuel Cycle Options for Optimum Resource Utilization and Waste Management	Purdue University	$400,000	Reasearchers will evaluate the two different two-stage fast reactor fuel cycle options that will offer efficient use of uranium resources and the ability to burn actinides and long-live fission products. Evaluation of these fast fuel cycle options will serve as a useful complement to the options currently being considered in the Fuel Cycle Options Campaign.	Document	FCR&D	FY2013
Mixed Metal Phosphonate-Phosphate Resins for Separation of Lanthanides from Actinides	Texas A&M University	$650,000	Reasearchers will use ion exchangers to cleanly separate lanthanides and curium from reusable actinides. The study will assist in the development of an inexpensive, simple way in which to separate lanthanides from actinides found in used nuclear fuel rods and to recover a large portion of the usable fuel.	Document	FCR&D	FY2013
Safeguards in Pyroprocessing: an Integrated Model Development and Measurement Data Analysis	The Ohio State University	$626,151	Reasearchers will develop a comprehensive and effective safeguards approach for a pyroprocessing facility to support safeguards for future fuel cycles in the United States. The new approach and design will focus directly on the special nuclear materials in the electrorefiner where actinides are separated from fission products through electrochemical process.	Document	FCR&D	FY2013
Using Ionic Liquids for the Development of Renewable Biopolymer-Based Adsorbents for the Extraction of Uranium from Seawater and Testing Under Marine Conditions	University of Alabama	$400,000	Reasearchers will explore the fundamental engineering parameters for a renewable high-performance adsorbent for the extraction of uranium from sweater based on a recently proven ionic liquid (IL)-chitin platform. The project will use the platform to develop a versatile, modifiable adsorbent and characterize its performance and degradation in marine conditions.	Document	FCR&D	FY2013
Developing Ultra-Small Scale Mechanical Testing Methods and Microstructural Investigation Procedures for Irradiated Materials.	University of California, Berkeley	$800,000	Reasearchers will develop new small-scale mechanical testing techniques to allow for the estimation or direct measurement of bulk properties. The combined experiments and modeling will significantly enhance the statistics and information that can be obtained on small radioactive archived samples, as well as new ion beam irradiated specimens.	Document	FCR&D	FY2013
Improved Delayed-Neutron Spectroscopy Using Trapped Ions	University of California, Berkeley	$400,000	Reasearchers will develop innovative spectroscopy techniques to measure the decay of fission fragments. The resulting data from these new techniques will be used to better understand reactor kinetics under accident conditions and failure scenarios.	Document	FCR&D	FY2013
Thermally and Chemically Responsive Nanoporous Materials for Efficient Capture of Fission Product Gases	University of California, Davis	$750,000	Reasearchers will create new nanoporous materials that will be highly effective at capturing fission product gases. These materials would be relevant to both reactor fuels applications and reprocessing operations. Tests will be performed in carbon based and nitride based nanostructures, with the most promising materials from the modeling perspective undergoing further testing.	Document	FCR&D	FY2013
Multiphase Nanocrystalline Ceramic Concept for Nuclear Fuel	University of California, Irvine	$800,000	Researchers will study the use of nanoparticles and nanostructured ceramics to create new materials that can extend the service life and increase efficiency for nuclear fuel. Multiphase nanocrystalline ceramics will be used to design simulated nuclear fuel that can provide added plasticity, better radiation tolerance and improved thermal conductivity.	Document	FCR&D	FY2013
Development of Novel Porous Sorbents for Extraction of Uranium from Seawater	University of Chicago	$400,000	Reasearchers will develop a highly porous sorbent for the extraction of uranium from seawater. Previous research has established sorbent performance. This project will use past foundational studies to design and investigate a new nanocomposites that will be processed into tacks or braids for field tests in seawater tests. The technology may also be used for other metals.	Document	FCR&D	FY2013
Microwave Readout Techniques for Very Large Arrays of Nuclear Sensors	University of Colorado, Boulder	$799,937	Reasearchers will develop a powerful readout technique based on microwave transmission and reflection. The technique will enable very large arrays of diverse sensor types for nuclear materials quantification and tracking. It will provide more accurate data on material composition and quantity.	Document	FCR&D	FY2013
BiI3 Gamma-Ray Spectrometers for Reliable Room-Temperature Nuclear Materials Safeguarding	University of Florida	$799,999	Reasearchers will develop gamma-ray spectrometers based on BiI3 single crystals for MPACT applications such as burnup validation quantification, improved assay of plutonium, determination of uranium enrichment and overall monitoring spent fuel within the fuel cycle. The project will improve energy resolution, efficiency and environmental performance with this new gamma-ray detector.	Document	FCR&D	FY2013
Innovative Coating of Nanostructured Vanadium Carbide on the F/M Cladding Tube Inner Surface for Mitigating the Fuel Cladding Chemical Interactions	University of Florida	$760,276	Researchers will develop barrier coatings on the inner surface of fuel cladding tubes to improve performance of materials at elevated temperatures and high neutron exposures in fast reactors. The project will develop and test a low temperature coating process of nanostructured vanadium carbide that will provide a benchmark for use in future studies.	Document	FCR&D	FY2013
Doubling the Life of Concrete Structures	University of Idaho	$800,000	Reasearchers will use nanoscale techniques to develop methods for doubling the service life of concrete structures. They will study the effect of temperature load and temperature cycling (freezing and thawing) on the durability of concrete with nanoscale viscosity modifiers. The project will benefit from non-destructive evaluation of concrete performance through electrochemical techniques.	Document	FCR&D	FY2013
Off-Gas Treatment: Evaluation of Nano-structured Sorbents for Selective Removal of Contaminants	University of Idaho	$785,910	Reasearchers will evaluate nanostructured sorbent materials for their effectiveness in removing and immobilizing radionuclides for the off-gas treatment from used nuclear fuel recycling operations. The project aims at achieving near-zero emissions of radionuclides by capturing them from the off-gas of recycling operations, allowing for the development of advanced fuel cycles.	Document	FCR&D	FY2013
Innovative Elution Processes for Recovering Uranium and Transition Metals from Amidoxime-Based Sorbents	University of Idaho	$399,864	Reasearchers will develop a new two-step elution process to achieve total recovery of uranium and effective recycling of the sorbent. The extraction process would selectively remove uranium from the sorbent with little or no damage. The process would then remove transition metals and regenerate the sorbent for repeated use, making uranium extraction from seawater economically viable.	Document	FCR&D	FY2013
Performance of a Steel/Oxide Composite Waste Form for Combined Waste Streams from Advanced Electrochemical Processes over Geologic Time Scales	University of Illinois at Chicago	$700,000	Reasearchers will develop and validate a mechanistically-based corrosion model for cermet-type waste forms, creating a testing protocol and modeling approach for predicting long-term performance. The study will apply novel electrochemical testing and modeling methods to the behavior of metal/oxide phase boundaries to evaluate waste form performance.	Document	FCR&D	FY2013
Enhancement of the Extraction of Uranium from Seawater	University of Maryland, College Park	$400,000	Reasearchers will develop and optimize novel adsorbents for uranium recovery from seawater. The team will use radiation-induced grafting of organic phosphates onto polymers. The experiments will use ocean water, with mechanistic analysis, to provide a solid basis for large-scale demonstration of the performance of the new adsorbents in ocean environments.	Document	FCR&D	FY2013
Improving the Understanding of the Coupled Thermal-Mechanical-Hydrologic Behavior of Consolidating Granular Salt	University of New Mexico	$800,000	Reasearchers will increase the understanding of granular salt seal materials for shafts, drifts and boreholes. By coupling thermal, mechanical and hydrological responses, the study will result in greater confidence in granular salt consolidation as a principal strategy for closure and isolation of long-term waste repositories.	Document	FCR&D	FY2013
Fission Fragment Yield Data in Support of Advanced Reactor Technology	University of New Mexico	$399,816	Reasearchers will produce a highly accurate data set for thermal fission. These precision data are necessary for high-accuracy simulations of nuclear criticality, transmutation rates, radiation effects and heating as well as for nuclear fuel, material accounting and identification needs.	Document	FCR&D	FY2013
Molecular dynamics-based simulations of bulk/interfacial structures and diffusion behaviors in nuclear waste glasses	University of North Texas	$700,000	Reasearchers will generate accurate atomic structural models for use in Monte Carlo simulations of the dissolution of nuclear waste glasses. Large-scale molecular dynamics-based computer simulations will be used to investigate self-diffusion behaviors, interfacial structure, and other structures formed during dissolution of these glasses.	Document	FCR&D	FY2013
U3Si2 Fabrication and Testing for Implementation into the BISON Fuel Performance Code	University of South Carolina	$800,000	Reasearchers will fabricate, test and model a high uranium density, advanced nuclear fuel that operates at a much lower temperature and stores less energy. The work will deliver key research data on creep and grain growth, improving economics, through possible power uprates, and advancing accident tolerant fuels research.	Document	FCR&D	FY2013
Structural Health Monitoring of Nuclear Spent Fuel Storage Facilities	University of South Carolina	$738,618	Reasearchers will develop a nuclear structural health monitoring system based on a sensing technology that monitors material degradation and aging for dry cask storage systems. The low-cost, low-profile sensors will perform on-demand monitoring of the structural integrity of individual components as well as the entire system.	Document	FCR&D	FY2013
ORIGEN-based Nuclear Fuel Depletion Module for Fuel Cycle Assessment	University of Tennessee at Knoxville	$755,181	Reasearchers will develop a flexible reactor analysis module for the CYCLUS fuel cycle simulator based on established tools for reactor fuel depletion and decay. They will use ORIGEN, a mature and experimentally validated code, affording greater flexibility and allowing for accurate evaluations of impacts of both present and future fuel cycle options.	Document	FCR&D	FY2013
Cost and System Analysis of Innovative Fuel Resources Concepts	University of Texas at Austin	$295,960	_This project will develop and test braided polymer fiber adsorbents that surpass the sorption capacity, selectivity and durability of the best existing technology to recover uranium from seawater.	Document	FCR&D	FY2013
Risk Assessment of Structural Integrity of Transportation Casks	University of Utah	$789,296	Reasearchers will assess the loss of structural integrity of transportation casks and fuel cladding after extended storage. This risk assessment will conduct experimental tests and simulations to evaluate the structural performance of fuel, fuel assemblies and cask components when subjected to vibration and impact loads during transport.	Document	FCR&D	FY2013
Market-Based and System-Wide Fuel Cycle Optimization	University of Wisconsin, Madison	$612,731	Reasearchers will create market and economic optimizers to improve calculations for the CYCLUS fuel cycle simulator. The team will leverage existing optimization software frameworks within the simulator to resolve top level policy questions. The optimizations will allow CYCLUS to move beyond static material compositions, providing a holistic view of the fuel cycle system.		FCR&D	FY2013
Optical Fiber Based System for Multiple Thermophysical Properties for Glove Box, Hot Cell and In-Pile Applications	Utah State University	$799,975	Reasearchers will use a small pressure vessel to develop a robust technique for the measurement of multiple thermophysical properties at very high temperatures. The technique will lead to a system design moving toward the eventual measurement of irradiated fuels in a glovebox and/or hot cell with all sensors and electronics outside of the glovebox and/or hot cell.	Document	FCR&D	FY2013
Development of a Nano-Modified Concrete for Next Generation of Storage Systems	Vanderbilt University	$796,268	Reasearchers will use nano-sized and nano-structured particles based on enhanced reactivity to develop a superior concrete for the long-term storage of used nuclear fuel. The project will use state-of-the-art experimental chemical and mechanical characterizations and computation analysis to assess the performance of nano-modified concretes.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Thorium Fuel Cycle Options	Vanderbilt University	$797,995	Reasearchers will develop six fuel cycle data packages for multi-stage, thermal fuel cycles which incorporate thorium. These new fuel cycle data packages will provide the opportunity to examine fuel cycle options beyond those which have traditionally been considered. A thorium fuel cycle database will also be assembled as a basis for thorium literature for future evaluations of the thorium fuel cycle.	Document	FCR&D	FY2013
Enhanced Shielding Performance of HLW Storage Packages via Multi-Component Coatings	Virginia Polytechnic Institute and State University	$796,947	Reasearchers will develop a multi-layer composite that will enhance long-term storage and facilitate safe transport of storage packages. This novel multi-layer, multi-component coating would create an outer shield material that is resistant to the corrosion, radiation, diffusion and thermal cycling processes that affect fuel packages during long term storage.	Document	FCR&D	FY2013
Managing Zirconium Chemistry and Phase Compatibility in Combined Process Separations for Minor Actinide Partitioning	Washington State University	$700,000	Reasearchers will address unique challenges for combining TRUEX and TALSPEAK processes for partitioning of lanthanides and minor actinides. The project will develop improved information on the thermodynamics of fission product zirconium and develop a framework for an organic phase solvation model. Combined process development could streamline separations processes.	Document	FCR&D	FY2013
Advances in the Recovery of Uranium from Seawater: Studies Under Real Ocean Conditions	Woods Hole Oceanographic Institution	$398,882	Reasearchers will provide infrastructure and expertise for marine testing of currently available adsorbents in real ocean conditions. The team will move adsorbent research from the lab to field testing in order to quantify sorptive properties and uranium uptake. The project will provide valuable field data that will show the potential of large scale applications of these technologies.	Document	FCR&D	FY2013
NEUP Project 20-19172: Irradiation of Sensors and Adhesive Couplants for Application in LWR Primary Loop Piping and Components		$497,881	Reasearchers paln to attach ultrasonic transducers to substrates using various adhesive couplants that will be irradiated at elevated temperature to simulate LWR primary loop conditions at the PULSTAR reactor at North Carolina State University. Ultrasonic data will be taken in-situ. Subsequently, the sensors and couplant interfaces will be characterized using the LAMDA facility at ORNL. The results will be used to benefit a parallel EPRI project on online monitoring of cracks in LWR primary loop piping._	Document	R&D NSUF	FY2013
NEUP Project 20-19404: Extension of MSTDB to Provide a High-Quality, Validated Thermochemical Database for Predicting/Simulating Corrosion in Molten Salt Reactor SystemsUniversity of South Carolina		$600,000	Reasearchers will generate a validated, consistent database of initial fuel compositions and potential corrossion products of fluoride and chloride salts, allowing for important phenomena predictions in molten salt reactors to guide confident decisions. The database will be integral to the currently being developed Molten Salt Thermochemical Database (MSTDB), structured to allow use by commercial and open source codes._	Document	NEAMS	FY2013
Lower Length Scale Characterization and Validation of Formation and Stability of Helium Bubbles in Nano-structured Ferritic Alloys under Irradiation	Clemson University	$399,870	Reasearchers will provide a fundamental knowledge about the formation and stability of ultra-fine helium bubbles within 14YWT after neutron/ion irradiation for further design of new advanced structural materials with a characteristic high density nanoparticles feature which can increase the mechanical strength, hardness, irradiation resistance and the operational temperature range of materials.	Document	NEAMS	FY2013
Three-Dimensional Fuel Pin Model Validation by Prediction of Hydrogen Distribution in Cladding and Comparison with Experiment	Pennsylvania State University	$800,000	Reasearchers will validate important three-dimensional aspects of the fuel pin modeling by using specialized numerical modeling techniques coupled with laboratory experiments to validate existing models for predicting fuel performance in light water reactors.	Document	NEAMS	FY2013
Collocation-Based Surrogate Models for Uncertainty Quantification and Validation of Coupled, Multiphysics Fuel Performance Simulation Tools	University of Michigan	$596,835	Reasearchers will provide the necessary high fidelity, coupled, multiphysics fuel performance simulator for computational modeling and develop surrogates which will accelerate and focus the validation of the coupled codes. This will be achieved by utilizing the high fidelity coupled fuel performance, thermal-hydraulics and neutronics codes BISON/STAR-CCM+/MPACT and an innovative collocation-based surrogate methodology.	Document	NEAMS	FY2013
Multi-Resolution In-Situ Testing and Mutliscale Simulation for Creep Damage Fatigue Damage Analysis of Alloy 617	Arizona State University	$800,000	This project will develop novel testing and experimentally validated prediction methodologies for micro-structural damage mechanisms of structural materials for advanced reactor systems. The investigations will focus on the characterization and testing of specific metal alloys, but the proposed testing and life-prediction methodologies are applicable to other structural materials as well.	Document	RCRD&D	FY2013
Novel High Temperature and Radiation Resistant Infrared Glasses and Optical Fibers for Sensing in Advanced Small Modular Reactors	Clemson University	$800,000	Clemson University, in partnership with the Iowa State University and the Pacific Northwest National Laboratory, will develop novel optical materials with improved heat and radiation exposure resistance in order to enable in-vessel fiber optic sensing for advanced Small Modular Reactors.	Document	RCRD&D	FY2013
Validation Data Acquisition in HTTF during PCC Events	George Washington University	$800,000	Reasearchers at the George Washington University and Oregon State University will collaborate with NASA Langley Research Center to measure flow velocities in a high temperature test facility. This work supports the development of very-high temperature reactors with passive safety systems.	Document	RCRD&D	FY2013
Advanced High Temperature Inspection Capabilities for Small Modular Reactors	Iowa State University	$790,822	The objective of this project is to develop non-destructive evaluation techniques for advanced small modular reactors. The research will provide key enabling inspection technologies needed to support the design and the reactor component performance validation process for advanced small modular reactors.	Document	RCRD&D	FY2013
Experimental and Computational Investigations of Plenum-to-Plenum Heat Transfer under Natural Circulation in a Prismatic Very High Temperature Reactor	Missouri University of Science and Technology	$799,999	Reasearchers will perform experimental and computational investigations to study heat transfer and natural circulation phenomena in very-high temperature reactors. The study will assist in the ability to predict and analyze passive safety systems.	Document	RCRD&D	FY2013
New Mechanistic Models of Creep-Fatigue Crack Growth Interactions for Advanced High Temperature Reactor Components	Oregon State University	$790,790	Reasearchers will create and validate a robust, multi-scale, numerical model to predict material degradation in nickel-based reactor alloys. If successful, this project will provide better numerical tools for reactor designers and greatly improve their capability to design against material failures for reactor alloys in the long term.	Document	RCRD&D	FY2013
Self-Powered Wireless Dual-mode Langasite Sensor for Pressure/Temperature Monitoring of Nuclear Reactors	State University of New York, Stony Brook	$800,000	This research will develop a novel self-powered wireless hybrid sensor that can accurately monitor both pressure and temperature using a single device without requiring external electricity, even in extreme harsh environments.	Document	RCRD&D	FY2013
Compact Heat Exchanger Design and Testing for Advanced Nuclear Reactors and Advanced Power Cycles	The Ohio State University	$800,000	The goal of this project is to investigate optimal heat exchanger designs for advanced reactors. The research will study the optimization of printed circuit heat exchangers for specific fluids under a variety of conditions as well as perform numerical modeling. Experiments will focus on thermal performance and heat stress during extreme conditions.	Document	RCRD&D	FY2013
Fundamental Understanding of Creep-Fatigue Interactions in 9Cr-1MoV Steel Welds	The Ohio State University	$798,000	This project will advance the state of knowledge and fundamental understanding of deforming materials and welds under loading conditions. Specifically, new integrated testing procedures will be evaluated and applied for conditions that are most detrimental to material stability leading to improved predictions of life expectancy for reactor steels and welds.	Document	RCRD&D	FY2013
Advanced Mechanistic 3D Spatial Modeling and Analysis Methods to Accurately Represent Nuclear Facility External Event Scenarios	The Ohio State University	$800,000	Reasearchers will develop three-dimensional characterization uncertainty analysis for commercial power plants. The project will involve combining experts from the fields of seismic structural modeling and advanced methods of risk assessment. This effort is expected to result in next generation tools that can be used for assessment of seismic risks.	Document	RCRD&D	FY2013
Tritium Mitigation/Control for Advanced Reactor Systems	The Ohio State University	$400,000	Reasearchers will develop a fluoride salt cooled high-temperature reactor featuring a specialized system to control tritium production. If successful, this will result in a significant reduction in size and cost in comparison to other reactor designs.	Document	RCRD&D	FY2013
A Pebble-Bed Breed and Burn Reactor	University of California, Berkeley	$400,000	Reasearchers will assess the feasibility of designing a type of metal cooled reactor able to establish and maintain operation when fueled with depleted uranium. If successful, this reactor will offer at least a 30-fold increase in the uranium ore utilization versus that achieved in contemporary light water reactors without the need for fuel reprocessing and recycling.	Document	RCRD&D	FY2013
Investigation of Thermal Aging Effects on the Evolution of Microstructure and Mechanical Properties of Cast Duplex Stainless Steels	University of Maryland, College Park	$799,966	This research will provide a better understanding of the microstructural evolution and simultaneous change in mechanical response during aging. The results of the research will provide data that can be used to estimate degraded mechanical properties for an 80-year service life of light water reactors.	Document	RCRD&D	FY2013
Model validation using CFD-grade experimental database for NGNP Reactor Cavity Cooling Systems with water and air	University of Michigan	$799,348	Reasearchers will use advanced innovative instrumentation to build a high-resolution experimental database and to use the novel experimental data to assess and further develop the predictive capabilities of computer codes for thermal hydraulics and computational fluid dynamics. The improved models developed by this project will also have the direct benefit of improving the predictive capability of the passive systems of third generation light water reactors and small modular reactor systems.	Document	RCRD&D	FY2013
Long-Term Prediction of Emissivity of Structural Material for High Temperature Reactor Systems	University of Missouri	$799,117	Reasearchers will study specific types of emissivity driven cooling from a variety of materials that are relevant to nuclear reactors. The research will provide a basis for numerical modeling to support reactor development.	Document	RCRD&D	FY2013
Advanced I&C for Fault-Tolerant Supervisory Control of Small Modular Reactors	University of Pittsburgh	$800,000	The purpose of this research is to develop advanced instrumentation and control techniques for supervisory control of advanced small modular reactors. This research supports the operational goals of small modular reactor concepts through the development of improved oversight and surveillance techniques.	Document	RCRD&D	FY2013
Corrosion of Structural Materials for Advanced Supercritical Carbon-Dioxide Brayton Cycle	University of Wisconsin-Madison	$798,672	Reasearchers will study a variety of materials for corrosion resistance under conditions that improve power conversion. In addition to studying the corrosion resistance of the materials, researchers will study the effect of additives to mitigate corrosion. Development of corrosion theories and modeling aimed at prediction of long-term corrosion will be the underlying theme throughout the project.	Document	RCRD&D	FY2013
Component and Technology Development for Advanced Liquid Metal Reactors	University of Wisconsin-Madison	$798,920	In support of liquid metal cooled reactors, the University of Wisconsin, Madison will evaluate advanced alloys and ceramics that come in contact with liquid metals. Additionally, a robust oxygen sensor and for use in liquid metals will be developed in order to better evaluate corrosion profiles in support of diagnostic testing.	Document	RCRD&D	FY2013
A New Paradigm for Understanding Multi-phase Ceramic Waste Form Performance	Clemson University	$800,000	Researchers will use advanced characterization tools to develop 3-D microstructural data that can be incorporated into computer-based simulations in order to predict the performance of waste forms. Materials system modeling will incorporate elemental release and the interconnected microstructural network of phases to better understand performance and degradation, which will accelerate waste form acceptance in repository settings.	Document	FCR&D	FY2014
Controlling Hexavalent Americium: A Centerpiece to a Compact Nuclear Fuel Cycle	Colorado School of Mines	$800,000	Researchers will develop and exploit the fundamental chemistry of Americium to enable an industrially viable means to co-recover the major and minor actinide elements from used nuclear fuel. The results would be a significant step forward in the development of aqueous separations approaches designed to recover the U-Am actinides based on the availability of the hexavalent oxidation state.	Document	FCR&D	FY2014
Zeolite Membranes for Krypton/Xenon Separation from Spent Nuclear Fuel Reprocessing Off-Gas	Georgia Institute of Technology	$400,000	Researchers will develop a high-performance, lower-cost zeolitic membrane process for Kr/Xe separations during spent nuclear fuel processing. Current separation methods are not considered economical and a membrane process would have relatively lower cost, equipment size, and ambient operating temperature. The process would form a sound basis for further development of this transformative separation technology for the nuclear fuel cycle.	Document	FCR&D	FY2014
Optimizing Polymer-Grafted Amidoxime-based Adsorbents for Uranium Uptake from Seawater	Georgia Institute of Technology	$399,999	Researchers will work to increase the adsorbent capacity and selectivity toward uranium by optimizing the adsorbent morphology, synthesis variables, and conditioning parameters and by investigating the rate-limiting variables through transport and reaction modeling. A novel adsorption/partition concept that has the potential to substantially increase the adsorbent capacity will be tested, making uranium from seawater extraction more economically viable.	Document	FCR&D	FY2014
Extraction of Uranium from Seawater: Design and Testing of a Symbiotic System	Massachusetts Institute of Technology	$400,000	Researchers will develop a seawater uranium extraction system that will work symbiotically with an offshore windmill by utilizing the structure, mooring and power of the windmill, while increasing the energy harvested by the installation. Uranium will be extracted by an adsorbent polymer belt, which will be cycled through the seawater and an elution plant located at the base of the windmill tower. Increasing the frequency of harvesting could overcome current economic barriers to seawater uranium extraction.	Document	FCR&D	FY2014
Imaging a Dry Storage Cask with Cosmic Ray Muons	Oregon State University	$799,871	Researchers will develop an imaging system to monitor the content of a dry storage cask with cosmic ray muons. A very large amount of plutonium under nuclear safeguards is contained in used fuel assemblies stored in dry storage casks. Muon imaging will allow a cost effective and reliable way to evaluate dry storage cask content and integrity before transport.	Document	FCR&D	FY2014
Apatite and sodalite based glass-bonded waste forms for immobilization of 129I and mixed halide radioactive wastes	Rutgers University	$800,000	Researchers will develop advanced and chemically durable waste forms for immobilizing 129I (aqueous based reprocessing of fuel) and mixed-halide wastes (molten-salt processing of fuel) by low temperature synthesis. Halide-containing sodalite and calcium phosphate-based apatite minerals will be synthesized, consolidated and tested for chemical durability. The project will provide needed baseline data for the development of advanced waste forms for immobilization of iodine and mixed-halide wastes.	Document	FCR&D	FY2014
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$350,000	Researchers will develop modeling tools supported by experiments for off-gas capture from future nuclear-fuel recycling facilities. Target species include tritium, iodine, krypton, and xenon. The models are intended to provide path forward recommendations to develop off-gas treatment adsorption processes. The project will contribute to the evaluation of options for environmentally acceptable recycle systems.	Document	FCR&D	FY2014
Development of high performance ODS alloys	Texas A&M University	$800,000	Researchers will study swelling, radiation hardening and changes in mechanical properties of ODS alloys to develop two sets of advanced ODS alloys. Two sets of first-round candidate alloys that have already undergone extensive development and testing will evaluate irradiation performance. The study will meet the need for high strength, radiation-tolerant cladding and core components that have enhanced resistance to void swelling.	Document	FCR&D	FY2014
Rare Earth Electrochemical Property Measurements and Phase Diagram Development in a Complex Molten Salt Mixture for Molten Salt Recycle	The Ohio State University	$800,000	Researchers will investigate rare earth (RE) properties in complex molten salt mixtures. In a molten salt recycle approach, the RE drawdown by electrolysis is a key step in which REs are separated from salt containing other fission products. Investigation of RE electrolysis must consider the electrochemical properties of the REs. We propose to conduct studies of detailed experiments and corresponding models to provide the physical properties and phase diagrams required to predict the performance of RE drawdown for processing complex molten salts.	Document	FCR&D	FY2014
Studies of Lanthanide Transport in Metallic Nuclear Fuels	The Ohio State University	$800,000	Researchers will study the redistribution of lanthanides and migration of lanthanides to the fuel surface. The mechanisms of lanthanide transport in metallic fuel based on the novel discovery of a Ôliquid-likeÕ transport mechanism will be studied analytically and experimentally. The project will develop a fundamental understanding of lanthanide fission product migration and redistribution in advanced metallic nuclear fuels, and theory and data to mitigate fuel-cladding chemical interactions.	Document	FCR&D	FY2014
Computational and Experimental Studies of Microstructure-Scale Porosity in Metallic Fuels for Improved Gas Swelling Behavior	University of Arkansas	$796,823	Researchers will study the microstructure of metallic uranium alloy fuels, and their resistance to densification, to minimize in-pile irradiation swelling through bimodal pore size distribution. The project will develop a predictive approach to design metallic fuel microstructures for optimal swelling resistance and fission gas retention.	Document	FCR&D	FY2014
Improved Hybrid Modeling of Spent Fuel Storage Facilities	University of California, Berkeley	$645,393	Researchers will develop a variance reduction method for computational transport that will improve the ability to design and operate monitoring systems for interim used fuel installations through enhanced modeling and simulation. This new tool will demonstrate that modeling calculations can be done more accurately in less time than with current tools and will perform studies characterizing how changes in material, cask configurations, and number of casks could impact monitoring systems.	Document	FCR&D	FY2014
Selective ligands for uranyl via combinatorial peptoid libraries: A synthetic, structural, thermodynamic and computational study	University of California, Berkeley	$400,000	Researchers will study how donor ligands bind to the uranyl ion, UO22+, with the longer-term goal of using this information to tackle selective recognition of uranyl in aqueous solution. The study will impact underlying approaches to controlling the behavior of uranium in these systems. The actinide separation technology could be used in several areas including uranium extraction from seawater, nuclear waste remediation and nuclear materials.	Document	FCR&D	FY2014
Combining Experiments and Simulations of Extraction Kinetics and Thermodynamics in Advanced Separation Processes for Used Nuclear Fuel	University of California, Irvine	$799,938	Researchers will study how the kinetics and thermodynamics of metal ion extraction in advanced separation processes for used nuclear fuel can be described by molecular dynamic (MD) simulations and how the simulations can be validated by experimental data. The project would have broad impacts on several separations processes including advanced TALSPEAK, ALSEP and GANEX by increasing the confidence and accuracy of computer modeling of metal ion extraction._	Document	FCR&D	FY2014
Effect of Metallic Li on the Behavior of Metals in Molten Salts	University of Nevada, Reno	$458,250	Researchers will identify the effect of metallic lithium on materials that are used in molten salt recycling. The study will try to understand how the presence of Li(0) in molten salts affects the degradation of alloys. Studying these changes will help accurately predict container material behavior and longevity.	Document	FCR&D	FY2014
Assessment of Corrosion Resistance of Promising Accident Tolerant Fuel Cladding under Reactor Conditions	University of Notre Dame	$800,000	Researchers will assess the corrosion behavior of accident tolerant fuel candidate iron-based alloys under normal LWR operating conditions consisting of high temperature, relevant water chemistry and irradiation. The assessment will produce data about possible irradiation-accelerated corrosion rates of iron-based alloys, and the mechanisms by which such corrosion rates are accelerated. The project will advance the selection of appropriate replacements for Zircaloy cladding.	Document	FCR&D	FY2014
Functionalized Porous Organic Polymers as Uranium Nano-Traps for Efficient Recovery of Uranium from Seawaterr	University of South Florida	$399,000	Researchers will develop functionalized porous organic polymers, or Ônano-trapsÕ for extraction of uranium from seawater. This technique allows for increased surface area and custom-designed pore size and chemistry to fit specific parameters. The adsorbent materials have high efficiency and effectiveness for uranium recovery from seawater, providing a potential supply for nuclear fuel.	Document	FCR&D	FY2014
Enhanced Accident-Tolerant Fuel Performance and Reliability for Aggressive iPWR/SMR Operation	University of Tennessee	$799,967	To develop a process that evaluates operational and safety performance of reactor-and-fuel combinations by integrating whole-core 3D neutronics with MOOSE/BISON fuel performance assessments via explicit time and space dependent fuel rod operational power histories. The project will be valuable in analyzing and evaluating accident tolerant fuel concepts and furthering the understanding of reactor physics and fuel performance aspects of key accident tolerant fuel concepts.	Document	FCR&D	FY2014
Nuclear Technology R&D Strategies in an Era of Energy Price Uncertainty	University of Texas, Austin	$799,112	Researchers will identify nuclear technology options that are competitive over a wide range of plausible future business environments. No single nuclear technology or business practice will be the best choice across all or even most future conditions. The study will focus on hybrid nuclear-fossil technologies, energy storage and conversion, which will result in an identification of nuclear strategies that can succeed under future market conditions.	Document	FCR&D	FY2014
Development and Optimization of Voltammetric Methods for Real Time Analysis of Electrorefiner Salt with High Concentrations of Actinides and Fission Products	University of Utah	$621,612	Researchers will develop an advanced voltammetry method to pursue the objective of real time monitoring of actinide concentrations in electrorefiner salt. This will include experimental measurement of key parameters such as activity coefficients and exchange current density. It will also involve simulation of voltammetry processes based on first principles. The project will allow for real time measurements that could support the commercialization of pyroprocessing.	Document	FCR&D	FY2014
Development of Self-Healing Zirconium-Silicide Coatings for Improved Performance of Zirconium-Alloy Fuel Cladding	University of Wisconsin, Madison	$798,621	Researchers will study the deposition of self-healing zirconium-silicide coatings on zirconium-alloy fuel cladding material to improve corrosion resistance under normal and accident conditions. Under these conditions, Zr-Si coating evolves into a highly protective functionally-graded multilayered system. The study will lead to improved performance of zirconium-alloy fuels._	Document	FCR&D	FY2014
Thermal Conductivity in Metallic Fuels	Virginia Polytechnic Institute and State University	$799,837	Researchers will calculate the thermal conductivity of metallic uranium and neptunium alloys, including the effects of noble gasses, using density functional theory. The experiments will validate the calculated effective thermal conductivity using the MARMOT code and by helping determine DFT simulation parameters. The study works to improve fuel lifetime by understanding its thermal behavior.	Document	FCR&D	FY2014
SiC-ODS Alloy Gradient Nanocomposites as Novel Cladding Materials	Virginia Polytechnic Institute and State University	$799,998	Researchers will combine nuclear nanomaterial design, processing, testing, and characterization efforts to develop revolutionary materials that can withstand neutron irradiation for long period of time using nanostructured SiC and oxide dispersion strengthened steel. The ultimate objective is to offer new cladding materials with increased corrosion resistance, strength, and creep resistance in both steady state and accident conditions.	Document	FCR&D	FY2014
Experimental Breeder Reactor II Benchmark Evaluation	Idaho State University	$400,000	Researchers will develop a benchmark evaluation of the Experimental Breeder Reactor II (EBR-II). During nearly 30 years of operation numerous experiments were conducted at EBR-II. The most significant of these experiments were conducted in 1986 demonstrating inherent safety features in loss of flow without reactor scram and loss of heat sink without reactor scram. Benchmark evaluation will be valuable for the reactor design efforts in the United States and South Korea.	Document	MSNE	FY2014
Integral full core multi-physics PWR benchmark with measured data	Massachusetts Institute of Technology	$400,000	Researchers will introduce BEAVRS, a new multi-cycle full-core Pressurized Water Reactor (PWR) depletion benchmark based on two operational cycles of a commercial nuclear power plant. This project aims at addressing the uncertainty quantification of the measured data and on making this benchmark a true non-proprietary international benchmark for the validation of high-fidelity multi-physics computational tools.	Document	MSNE	FY2014
Benchmark Evaluation of PROTEUS Gas-Cooled Reactor Experiments	University of Florida	$400,000	Researchers will create International Reactor Physics Experiment Evaluation Project (IRPhEP) benchmarks using data from 1970s experiments of the neutronics of gas-cooled fast reactor (GCFR) designs investigated in the PROTEUS reactor. The GCFR-PROTEUS experiments fill a gap in current integral benchmark data. These experiments can provide validation of computational models and nuclear data for next generation reactors.	Document	MSNE	FY2014
An Investigation To Establish Multiphysical Property Dataset Of Nuclear Materials Based On In-Situ Observations And Measurements	Purdue University	$800,000	Researchers will create an in-situ measurement based experimental approach to develop experimental validation dataset for NEAMS based code validation. Particular emphasis is on supplying data set for multiphysics simulations in extreme conditions as a function of material microstructure.	Document	NEAMS	FY2014
Experimental Validation of UO2 Microstructural Evolutions for NEAMS tool MARMOT	University of Florida	$798,000	Researchers will experimentally validate MARMOT for predicting the microstructural evolutions of UO2 oxide fuel under the driving forces of high temperatures and large temperature gradient in reactors. By performing the experiments and simulations simultaneously using precisely defined initial conditions, the experiment data will provide direct benchmarking of the MARMOT code.	Document	NEAMS	FY2014
High-resolution time-resolved experiments on mixing and entrainment of buoyant jets in stratified environments	University of Michigan	$799,983	Researchers will study high spatial and time-resolution experimental data of the fluid dynamics phenomena of flow jets interacting with a stratified layer. The issue plays an important role in the safety of several reactor designs, including sodium-cooled reactors. The data addresses the NEAMS needs for the validation of high fidelity computational fluid dynamics methodologies.	Document	NEAMS	FY2014
Fundamental study of key issues related to advanced S-CO2 Brayton Cycle: prototypic HX development and Cavitation	Georgia Institute of Technology	$799,000	Researchers will study scientific and operational issues pertinent to compact heat exchanger systems and turbo-machinery. The project will work to resolve issues with the fabrication of diffusion bonded compact heat exchangers, alternate heat exchange technology for recuperators, and resolution of issues with cavitation and fluid instabilities.	Document	RCRD&D	FY2014
Advanced Models for Nondestructive Evaluation of Aging Nuclear Power Plant Cables	Iowa State University	$787,291	Researchers will develop advanced models that relate environmentally induced microstructural and chemical changes in cable insulation polymers to their macroscopic electrical parameters. These parameters will be measured and modeled over a wide range of the electromagnetic spectrum, covering several potential nondestructive evaluation techniques, enabling identification of the most sensitive techniques for future development.	Document	RCRD&D	FY2014
Development of Novel Functionally Graded Transition Joints for Improving the Creep Strength of Dissimilar Metal Welds in Nuclear Applications	Lehigh University	$800,000	Researchers will develop graded transition joints and improved creep life models for increasing the life of dissimilar metal welds (DMWs) in nuclear reactors. The research represents the first application of functionally graded material concepts for solving the problem of DMW failures through an integrated approach of additive manufacturing, modeling, microstructural characterization, and advanced strain-sensing techniques.	Document	RCRD&D	FY2014
Feasibility Assessment of a Micro Modular Reactor (MMR)	North Carolina State University	$400,000	Researchers will develop an innovative compact reactor concept that integrates power production, power conversion and electricity generation in a single unit: the Micro Modular Reactor (MMR). It is designed to be absolutely melt-down proof (MDP) under all circumstances including complete loss of coolant scenarios with no possible release of radioactive material, to have a cycle length of greater than 10 years, and to be highly proliferation resistant.	Document	RCRD&D	FY2014
Scaling Studies for Advanced Gas Reactor Concepts	Oregon State University	$681,834	Researchers will expand the utilization of the Oregon State University High Temperature Test Facility (HTTF) to validate a broader range of advanced high temperature reactors and events. The facility will be revised to add a detailed scaling analysis of additional gas reactor concepts including advanced gas-cooled, molten salt, and sodium cooled reactors.	Document	RCRD&D	FY2014
Fluid Stratification Separate Effects Analysis, Testing and Benchmarking	Oregon State University	$800,000	Researchers will study fluid stratification in high temperature gas reactors. Coolant stratification is the result of incomplete mixing of one or more fluids, leading to a density gradient, which may or may not dissipate under diffusive or convective effects. This combined analytical and experimental project seeks to investigate stratification driven by diffusive and convective mechanisms and is expected to yield insight into this phenomenon.	Document	RCRD&D	FY2014
Probabilistic Economic Valuation of Safety Margin Management Analysis	Oregon State University	$795,364	Researchers will use RAVEN and develop a companion software package to facilitate economic analysis of safety margins. The project is a proof of concept that will use techniques to examine the cost of improving safety margins vs. the risk of accidents from not improving safety margins. This analysis can be used to evaluate the economic viability of various plant upgrades.	Document	RCRD&D	FY2014
Novel Dissimilar Joints Between Alloy 800H and 2.25%Cr and 1%Mo Steel	Pennsylvania State University	$800,000	Researchers will fabricate and test dissimilar metal joints between a nickel base alloy and a steel with gradual variations of chemical composition, microstructure and properties in a manner that reduces abrupt thermal expansion mismatch and the resulting residual stresses. Data on structure and properties will serve as valuable inputs for the initiation of an ASME code case.	Document	RCRD&D	FY2014
Multi-Phase Model Development to Assess RCIC System Capabilities under Severe Accident Conditions	Texas A&M University	$564,246	Researchers will develop physics-based models of the Reactor Core Isolation Cooling (RCIC) System and incorporating them into a multi-phase code for validation. The project will tackle the current major challenges in RCIC System analysis and enable evaluation of two-phase thermodynamic aspects.	Document	RCRD&D	FY2014
Experimental Investigation and CFD Analysis of Steam Ingress Accidents in HTGRs	The Ohio State University	$800,000	Researchers will study the steam ingress scenario for HTGRs. The study will investigate thermal-hydraulic behavior and graphite oxidation of stream ingress phenomena to validate predictive CFD models. This work will resolve concerns about possible steam generator tube ruptures in a HTGR He-Steam Rankine cycle.	Document	RCRD&D	FY2014
Coiled Tube Gas Heaters For Nuclear Gas-Brayton Power Conversion	University of California, Berkeley	$800,000	Researchers will develop heat exchangers for Brayton-cycle power conversion in reactors using sodium, NaK, or salt as intermediate coolants. The proposed coiled tube gas heaters (CTGHs) are expected to have excellent power density, thermal shock/creep, in-service inspection, and reparability characteristics.	Document	RCRD&D	FY2014
Fundamental Studies of Irradiation-Induced Modifications in Microstructural Evolution and Mechanical Properties of Advanced Alloys	University of Illinois, Urbana-Champaign	$800,000	Researchers will develop and test a mechanism for predicting neutron irradiation performance for optimized Grade 92 and Alloy 709 for applications in advanced reactor systems. The work will employ ion irradiations and available information from neutron irradiations of related alloys to develop a basis for predicting the neutron irradiation performance of the optimized alloys.	Document	RCRD&D	FY2014
Integrated Computational and Experimental Study of Radiation Damage Effects in Grade 92 Steel and Alloy 709	University of Tennessee	$800,000	Researchers will develop a mechanistic understanding and predictive models of irradiation-induced microstructural evolution and resulting mechanical properties in optimized ferritic-martensitic Grade 92 steel and austenitic alloy 709 using multiscale simulations coupled with rigorous experimental validation. The project will provide insights into the correlation between ion irradiation and fast neutron damage.	Document	RCRD&D	FY2014
Meta-Level Design Guidance and Operator Performance Measures for Hybrid Control Rooms	Vanderbilt University	$799,869	Researchers will apply human factors engineering methods and relevant expertise from non-nuclear high-risk high-consequence domains toward the measurement of operator performance in analog, digital, and hybrid main control rooms. Performance measures will be developed for evaluating the situation awareness and decision-making proficiencies to support the transition to digital or hybrid control room displays.	Document	RCRD&D	FY2014

FY 2020 Research and Development Awards

DOE is awarding more than $38.6 million through NEUP to support 57 university-led nuclear energy research and development projects in 24 states. NEUP seeks to maintain U.S. leadership in nuclear research across the country by providing top science and engineering faculty and their students with opportunities to develop innovative technologies and solutions for civil nuclear capabilities.

A complete list of R&D projects with their associated abstracts is available below.

Title	Institution	Estimated Funding*	Project Description	Abstract	Project Type	Fiscal Year
Neutron Damage and MAX Phase Ternary Compounds	Drexel University			Document	IIR	FY2009
Atomistic Calculations of the Effect of Minor Actinides on Thermodynamic and Kinetic Properties of UO2+x	Georgia Institute of Technology			Document	IIR	FY2009
Maximum Fuel Utilization in Fast Reactors without Chemical Reprocessing	University of California, Berkeley			Document	IIR	FY2009
Developing a High Thermal Conductivity Fuel with Silicon Carbide Additives	University of Florida			Document	IIR	FY2009
Fabrication of Tungsten-Rhenium Cladding Materials via Spark Plasma Sintering for Ultra High Temperature Reactor Applications	University of Idaho			Document	IIR	FY2009
Ionic Liquid and Supercritical Fluid Hyphenated Techniques for Dissolution and Separation of Lanthanides, Actinides, and Fission Products	University of Idaho			Document	IIR	FY2009
Improved Fission Neutron Data Base for Active Interrogation of Actinides	University of Michigan			Document	IIR	FY2009
Utilization of Methacrylates and Polymer Matrices for the Synthesis of Ion Specific Resins	University of Nevada, Las Vegas			Document	IIR	FY2009
Improved LWR Cladding Performance by EPD Surface Modification Technique	University of Wisconsin, Madison			Document	IIR	FY2009
Advanced Models of LWR Pressure Vessel Embrittlement for Low Flux-High Fluence Conditions	University of California, Santa Barbara			Document	LWRS	FY2009
Irradiation Creep in Graphite	Boise State University			Document	NGNP	FY2009
Modeling the Stress Strain Relationships and Predicting Failure Probabilities For Graphite Core Components	Cleveland State University			Document	NGNP	FY2009
TRISO-Coated Fuel Durability Under Extreme Conditions	Colorado School of Mines			Document	NGNP	FY2009
An Innovative and Advanced Coupled Neutron Transport and Thermal Hydraulic Method (Tool) for the Design, Analysis and Optimization of VHTR/NGNP Prismatic Reactors	Georgia Institute of Technology			Document	NGNP	FY2009
Removal of 14C from Irradiated Graphite for Graphite Recycle and Waste Volume Reduction	Idaho State University			Document	NGNP	FY2009
Millimeter-Wave Thermal Analysis Development and Application to Gen IV Reactor Materials	Massachusetts Institute of Technology			Document	NGNP	FY2009
Accurate Development of Thermal Neutron Scattering Cross Section Libraries	North Carolina State University			Document	NGNP	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
Understanding Creep Mechanisms in Graphite with Experiments, Multiscale Simulations, and Modeling	North Carolina State University			Document	NGNP	FY2009
Simulations of the Thermodynamic and Diffusion Properties of Actinide Oxide Fuel Materials	University of Michigan			Document	AFCI	FY2009
Verification & Validation of High-Order Short-Characteristics-Based Deterministic Transport Methodology on Unstructured Grids	North Carolina State University			Document	NGNP	FY2009
Adsorptive Separation and Sequestration of Krypton, I and C14 on Diamond Nanoparticles	University of Missouri, Columbia			Document	AFCI	FY2009
Microscale Heat Conduction Models and Doppler Feedback	North Carolina State University			Document	NGNP	FY2009
Fundamental Understanding of Ambient and High-Temperature Plasticity Phenomena in Structural Materials in Advanced Reactors	Georgia Institute of Technology			Document	AFCI	FY2009
Development of Alternative Technetium Waste Forms	University of Nevada, Las Vegas			Document	AFCI	FY2009
Optimizing Neutron Thermal Scattering Effects in Very High Temperature Reactors	North Carolina State University			Document	NGNP	FY2009
Advanced Elastic/Inelastic Nuclear Data Development Project	Idaho State University			Document	AFCI	FY2009
Heterogeneous Recycling in Fast Reactors	Massachusetts Institute of Technology			Document	AFCI	FY2009
Quantification of UV-Visible and Laser Spectroscopic Techniques for Materials Accountability and Process Control	University of Nevada, Las Vegas			Document	AFCI	FY2009
Multiaxial Creep-Fatigue and CreepRatcheting Failures of Grade 91 and Haynes 230 Alloys Toward Addressing Design Issues of Gen IV Nuclear Power Plants	North Carolina State University			Document	NGNP	FY2009
Thermodynamic Development of Corrosion Rate Modeling in Iron Phosphate Glasses	Missouri University of Science and Technology			Document	AFCI	FY2009
Development of Subspace-Based Hybrid Monte Carlo-Deterministic Algorithms for Reactor Physics Calculations	North Carolina State University			Document	AFCI	FY2009
High-Fidelity Space-Time Adaptive Multiphysics Simulations in Nuclear Engineering	University of Nevada, Reno			Document	AFCI	FY2009
Improvements to Nuclear Data and Its Uncertainties by Theoretical Modeling	Rensselaer Polytechnic Institute			Document	AFCI	FY2009
Investigation of Countercurrent Helium-air Flows in Air-ingress Accidents for VHTRs	Ohio State University			Document	NGNP	FY2009
Sharp Interface Tracking in Rotating Microflows of Solvent Extraction	State University of New York at Stony Brook			Document	AFCI	FY2009
Bulk Nanostructured FCC Steels with Enhanced Radiation Tolerance	Texas A&M University			Document	AFCI	FY2009
Simulations of Failure via Three-Dimensional Cracking in Fuel Cladding for Advanced Nuclear Fuels	University of Texas, Dallas			Document	AFCI	FY2009
Testing of Performance of Optical Fibers Under Irradiation in Intense Radiation Fields, When Subjected to Very High Temperatures	Ohio State University			Document	NGNP	FY2009
Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels	Texas A&M University			Document	AFCI	FY2009
SiC Schottky Diode Detectors for Measurement of Actinide Concentrations from Alpha Activities in Molten Salt Electrolyte	The Ohio State University			Document	AFCI	FY2009
Computational Design of Advanced Nuclear Fuels	University of California, Davis			Document	AFCI	FY2009
Advanced Mesh-Enabled Monte Carlo Capability for Multi-Physics Reactor Analysis	University of Wisconsin, Madison			Document	AFCI	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
A Distributed Fiber Optic Sensor Network for Online 3-D Temperature and Neutron Fluence Mapping in a VHTR Environment	Texas A&M University			Document	NGNP	FY2009
Ab Initio Enhanced Calphad Modeling of Actinide Rich Nuclear Fuels	University of Wisconsin, Madison			Document	AFCI	FY2009
Investigation on the Core Bypass Flow in a Very High Temperature Reactor	Texas A&M University			Document	NGNP	FY2009
Development of Diffusion Barrier Coatings and Deposition Technologies for Mitigating Fuel Cladding Chemical Interactions (FCCI)	University of Wisconsin, Madison			Document	AFCI	FY2009
CFD Model Development and Validation for High Temperature Gas Cooled Reactor Cavity Cooling System (RCCS) Applications	Texas A&M University			Document	NGNP	FY2009
Thermal Properties of LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin, Madison			Document	AFCI	FY2009
Study of Air ingress across the duct during the accident conditions	Texas A&M University			Document	NGNP	FY2009
Verification of the CENTRM Module for Adaptation of the SCALE Code to NGNP Prismatic and PBR Core Designs	University of Arizona			Document	NGNP	FY2009
Integral and Separate Effects Tests for Thermal Hydraulics Code Validation for Liquid-Salt Cooled Nuclear Reactors	University of California, Berkeley			Document	NGNP	FY2009
Mechanisms Governing the Creep Behavior of High Temperature Alloys for Generation IV Nuclear Energy Systems	University of Cincinnati			Document	NGNP	FY2009
ALD Produced B2O3, Al2O3 and TiO2 Coatings on Gd2O3 Burnable Poison Nanoparticles	University of Colorado, Boulder			Document	NGNP	FY2009
Experimental Study and Computational Simulations of Key Pebble Bed Thermomechanics Issues for Design and Safety	University of Idaho			Document	NGNP	FY2009
Prediction and Monitoring Systems of Creep-Fracture Behavior of 9Cr-1Mo Steels for Reactor Pressure Vessels	University of Idaho			Document	NGNP	FY2009
Understanding Fundamental Material Degradation Processes in High Temperature Aggressive Chemomechanical Environments	University of Illinois, Urbana-Champaign			Document	NGNP	FY2009
Multi-Scale Multi-physics Methods Development for the Calculation of Hot-Spots in the NGNP	University of Michigan			Document	NGNP	FY2009
Corrosion and Creep of Candidate Alloys in High Temperature Helium and Steam Environments for the NGNP	University of Michigan			Document	NGNP	FY2009
Creation of a Full-Core HTR Benchmark with the Fort St. Vrain Initial Core and Validation of the DHF Method with Helios for NGNP Configurations	University of Michigan			Document	NGNP	FY2009
Fission Product Sorptivity in Graphite	University of Missouri, Columbia			Document	NGNP	FY2009
Identifying and Understanding Environment-Induced Crack Propagation Behavior in Ni-Based Superalloy INCONEL 617	University of Nevada, Las Vegas			Document	NGNP	FY2009
Graphite Oxidation Simulation in HTR Accident Conditions	University of New Mexico			Document	NGNP	FY2009
Non Destructive Thermal Analysis and In Situ Investigation of Creep Mechanism of Graphite and Ceramic Composites using Phase-sensitive THz Imaging & Nonlinear Resonant Ultrasonic Spectroscopy	University of Rochester			Document	NGNP	FY2009
Tritium Sequestration in Gen IV NGNP Gas Stream via Proton Conducting Ceramic Pumps	University of South Carolina			Document	NGNP	FY2009
Materials, Turbomachinery and Heat Exchangers for Supercritical CO2 Systems	University of Wisconsin, Madison			Document	NGNP	FY2009
Experimental Studies of NGNP Reactor Cavity Cooling System with Water	University of Wisconsin, Madison			Document	NGNP	FY2009
Assessment of Embrittlement of VHTR Structural Alloys in Impure Helium Environments	University of Wisconsin, Madison			Document	NGNP	FY2009
Modeling Fission Product Sorption in Graphite Structures	University of Wisconsin, Madison			Document	NGNP	FY2009
Liquid Salt Heat Exchanger Technology for VHTR Based Applications	University of Wisconsin, Madison			Document	NGNP	FY2009
Effect of Post-Weld Heat Treatment on Creep Rupture Properties of Grade 91 Steel Heavy Section Welds	Utah State University			Document	NGNP	FY2009
Alpha Radiolysis of Nuclear Solvent Extraction Ligands used for An(III) and Ln(III) Separations	California State University, Long Beach	$1,390,252		Document	FCR&D	FY2010
Predictive Maturity of Multi-Scale Simulation Models for Fuel Performance	Clemson University	$614,690		Document	FCR&D	FY2010
Freeze-casting as a Novel Manufacturing Process for Fast Reactor Fuels	Drexel University	$1,149,327		Document	FCR&D	FY2010
Fuel Performance Experiments on the Atomistic Level, Studying Fuel Through Engineered Single Crystal UO2	Idaho State University	$650,000		Document	FCR&D	FY2010
Development of A Self Biased High Efficiency Solid-State Neutron Detector for MPACT Applications	Rensselaer Polytechnic Institute	$810,141		Document	FCR&D	FY2010
Development of a Innovative High Thermal Conductivity UO 2 Ceramic Composites Fuel Pellets with Carbon Nano-Tubes Using Spark Plasma Sintering	University of Florida	$894,042		Document	FCR&D	FY2010
Exploration and Modeling of Structural Changes in Waste Glass under Corrosion	Pennsylvania State University	$1,377,444		Document	FCR&D	FY2010
Evaluation of materials for interim storage of spent fuel for more than 100 years	University of Michigan	$931,603		Document	FCR&D	FY2010
Implementation of On-the-Fly Doppler Broadening in MCNP5 for Multiphysics Simulation of Nuclear Reactors	University of Michigan	$406,712		Document	FCR&D	FY2010
Methods and tools to allow molecular flow simulations to be coupled to higher level continuum descriptions of flows in porous/fractured media and aerosol/dust dynamics	University of Missouri-Columbi	$541,286		Document	FCR&D	FY2010
Characterization and Modeling of Materials for Kr-Xe Separations	University of Nevada-Las Vegas	$989,800		Document	FCR&D	FY2010
Modeling Solute Thermokinetics in LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin-Madison	$616,073		Document	FCR&D	FY2010
Advanced Aqueous Separation Systems for Actinide Partitioning: Develop Fundamental Understanding of An(III)/Ln(III) Separation	Washington State University	$1,451,784		Document	FCR&D	FY2010
Consistent Multigroup Theory Enabling Accurate Coarse-Group Simulation of GenIV Reactors	Georgia Institute of Technology	$1,046,277		Document	GEN IV	FY2010
Studies of Deteriorated Heat Transfer in Prismatic Cores Stemming from Irradiation-Induced Geometry Distortion	Idaho State University	$1,287,921		Document	GEN IV	FY2010
Carbide Coatings for Nickel Alloys, Graphite, and Carbon/Carbon Composites to be Used in Fluoride Salt Valves	Johns Hopkins University	$1,183,239		Document	GEN IV	FY2010
Design, Testing, and Modeling of the Direct Reactor Auxiliary Cooling System for AHTRs	Ohio State University	$1,366,627		Document	GEN IV	FY2010
Monitoring microstructural evolution of Alloy 617 with nonlinear acoustics for remaining useful life prediction; multiaxial creep-fatigue and creep-ratcheting	Pennsylvania State University	$1,000,000		Document	GEN IV	FY2010
Development and Validation of Multidimensional Models of Supercritical CO 2 Energy Conversion Systems for Nuclear Power Reactors	Rensselaer Polytechnic Institute	$475,005		Document	GEN IV	FY2010
Multiscale Concrete Modeling for Aging Degradation	Mississippi State University	$345,941		Document	LWRS	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term and Elevated Temperature Irradiation: Modeling and Experimental Investigation	University of California-Berkeley	$1,320,667		Document	GEN IV	FY2010
Development of an advanced computational fluid dynamics technology for the next-generation nuclear reactor system analysis and safety margin characterization code	North Carolina State University	$418,199		Document	LWRS	FY2010
Development of Barrier Layers for the Protection of Candidate Alloys in the VHTR	University of California-Santa Barbara	$995,232		Document	GEN IV	FY2010
Precursor Derived Nanostructured Si-C-X Materials for Nuclear Applications	University of Washington	$899,518		Document	MRIIR	FY2010
Investigation of a Novel NDE Method for Monitoring Thermo-Mechanical Damage and Microstructure Evolution in Ferritic-Martensitic Steels for Generation IV Nuclear Energy Systems	University of Cincinnati	$833,109		Document	GEN IV	FY2010
Development and Testing of an Open-Loop Oscillator for Small Reactivity Worth Samples	Idaho State University	$597,252		Document	MRIIR	FY2010
Fission Product Transport in TRISO Particle Layers under Operating and Off-Normal Conditions	University of Michigan	$966,581		Document	GEN IV	FY2010
Understanding the Irradiation Behavior of Zirconium Carbide	Pennsylvania State University	$870,613		Document	MRIIR	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term Irradiation at Elevated Temperature: Critical Experiments	University of Michigan	$1,181,379		Document	GEN IV	FY2010
Modeling investigation of the stability and irradiation-induced evolution of nanoscale precipitates in advanced structural materials	University of Tennessee-Knoxville	$380,653		Document	MRIIR	FY2010
Three-dimensional NDE of VHTR Core Components via Simulation-based Testing	University of Minnesota	$1,366,163		Document	GEN IV	FY2010
Investigation of Laser Shock Peening for Enhancing Fatigue and Stress Corrosion Cracking Resistance of Nuclear Energy Materials	University of Cincinnati	$1,242,019		Document	MRIIR	FY2010
Failure Predictions for VHTR Core Components using a Probabilistic Continuum Damage Mechanics Model	University of Minnesota	$854,542		Document	GEN IV	FY2010
Irradiation Accelerated Corrosion of Reactor Core Materials	University of Michigan	$798,943		Document	MRIIR	FY2010
Development of a Scanning Microscale Fast Neutron Irradiation Platform for Examining the Correlation Between Local Neutron Damage and Graphite Microstructure	University of Missouri-Columbia	$703,064		Document	GEN IV	FY2010
Study of Interfacial Interactions using Thin Film Surface Modification: Radiation and Oxidation Effects in Materials	University of Wisconsin-Madison	$538,032		Document	MRIIR	FY2010
Development of Thermal Transient Flow Rate Sensors for High Temperature, Irradiation, Corrosive Environment	University of Nevada-Las Vegas	$451,269		Document	GEN IV	FY2010
Novel Engineered Refractory Materials for Advanced Reactor Applications	North Carolina State University	$1,129,304		Document	MRIIR	FY2010
Novel Methods of Tritium Sequestration: High Temperature Gettering and Separation Membrane Materials Discovery for Nuclear Energy Systems	University of South Carolina	$1,366,626		Document	GEN IV	FY2010
Heat Transfer Salts for Nuclear Reactor Systems - Chemistry Control, Corrosion Mitigation, and Modeling	University of Wisconsin-Madison	$1,352,040		Document	GEN IV	FY2010
Pulsed Magnetic Welding for Advanced Core and Cladding Steels	University of Wisconsin-Madison	$525,206		Document	GEN IV	FY2010
Corrosion in Supercritical Carbon Dioxide: Materials, Environmental Purity, Surface Treatments, and Flow Issues	University of Wisconsin-Madison	$651,447		Document	GEN IV	FY2010
Quantification of Cation Sorption to Engineered Barrier Materials Under Extreme Conditions	Clemson University	$1,171,380		Document	FCR&D	FY2011
In-Pile Instrumentation Multi-Parameter System Utilizing Photonic Fibers and Nanovision	Idaho State University	$1,199,990		Document	FCR&D	FY2011
Development of Plasmonically Cloaked Nanoparticles	Idaho State University	$800,000		Document	FCR&D	FY2011
Fission Product Transmutation in Mixed Radiation Fields	Idaho State University	$800,000		Document	FCR&D	FY2011
Life Prediction of Spent Fuel Storage Canister Material	Massachusetts Institute of Technology	$899,826		Document	FCR&D	FY2011
Active Interrogation using Photofission Technique for Nuclear Materials Control and Accountability	Oregon State University	$900,000		Document	FCR&D	FY2011
Anisotropic Azimuthal Power and Temperature Distribution on Fuel Rod: Impact of Hydride Distribution	Pennsylvania State University	$631,956		Document	FCR&D	FY2011
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$1,000,000		Document	FCR&D	FY2011
Recovery of Uranium from Seawater: Preparation and Development of Polymer-Supported Extractants	City College of New York, Hunter	$363,716		Document	MSTR	FY2011
Microemulsions and Aggregation Formation in Extraction Processes for Used Nuclear Fuel: Thermodynamics and Structural Studies	University of California, Irvine	$1,000,000		Document	FCR&D	FY2011
One-Dimensional Nanostructures for Neutron Detection	North Carolina State University	$455,629		Document	MSTR	FY2011
Optimized Processing Fabrication Paths for Larger Heats of Nanostructured Ferritic Alloys	University of California, Santa Barbara	$1,000,000		Document	FCR&D	FY2011
Feasibility and Safety Assessment for Advanced Reactor Concepts Using Vented Fuel	Oregon State University	$600,000		Document	MSTR	FY2011
Basic Physics Data: Measurement of Neutron Multiplicity from Induced Fission	University of Michigan	$973,364		Document	FCR&D	FY2011
Development of an Efficient Meso-Scale Multi-Phase Flow Solver in Nuclear Applications	City College of New York	$505,858		Document	NEAMS	FY2011
High Temperature Transducers for Online Monitoring of Microstructure Evolution	Pennsylvania State University	$455,628		Document	MSTR	FY2011
Radionuclide Incorporation and Long Term Performance of Apatite Waste Forms	University of Michigan	$862,500		Document	FCR&D	FY2011
Multiscale Modeling and Uncertainty Quantification for Nuclear Fuel Performance	Colorado State University	$1,098,250		Document	NEAMS	FY2011
Laser-Arc Hybrid Welding of Thick Section Ni-base Alloys- Advanced Modeling and Experiments	Pennsylvania State University	$536,117		Document	MSTR	FY2011
Actinide Foil Production for MPACT Research	University of Nevada-Las Vegas	$156,897		Document	FCR&D	FY2011
Fundamental Studies of the Role of Grain Boundaries on Uniform Corrosion of Advanced Nuclear Reactor Materials	Drexel University	$1,098,250		Document	NEAMS	FY2011
Correlates of Sensitive Technologies	Texas A&M University	$509,467		Document	MSTR	FY2011
Enriched Boron-Doped Amorphous Selenium Based Position-Sensitive Solid-State Thermal Neutron Detector for MPACT Applications	University of South Carolina	$1,000,000		Document	FCR&D	FY2011
Phenomena-based Uncertainty Quantification in Predictive Coupled-Physics Reactor Simulations	Texas A&M University	$1,098,250		Document	NEAMS	FY2011
Improved Safety Margin Characterization of Risk from Loss of Offsite Power	Texas A&M University	$600,000		Document	MSTR	FY2011
Development of Advanced High Uranium Density Fuels for Light Water Reactors	University of Wisconsin-Madison	$1,000,000		Document	FCR&D	FY2011
Characterization of Modeling of Grain Boundary Chemistry Evolution in Ferritic Steels Under Irradiation	University of Michigan	$1,098,250		Document	NEAMS	FY2011
Diffusion, Thermal Properties and chemical Compatibilities of Select MAX Phases with Materials for Advanced Nuclear Systems	Drexel University	$535,927		Document	NEET	FY2011
A High Temperature-Tolerant and Radiation-Resistant In-Core Neutron Sensor for Advanced Reactors	The Ohio State University	$455,629		Document	MSTR	FY2011
Developing the User Experience for a Next Generation Nuclear Fuel Cycle Simulator	University of Wisconsin-Madison	$1,200,000		Document	FCR&D	FY2011
Development of Multiscale Materials Modeling Techniques and Coarse-Graining Strategies for Predicting Materials Degradation in Extreme Irradiation Environments	University of Tennessee, Knoxville	$750,000		Document	NEAMS	FY2011
A New Light Weight Structural Material for Nuclear Structures	North Carolina State University	$399,490		Document	NEET	FY2011
Pathway Aggregation in the Risk Assessment of Proliferation Resistance and Physical Protection (PR&PP) of Nuclear Energy Systems	The Ohio State University	$534,471		Document	MSTR	FY2011
Experimental Investigation of Convection and Heat Transfer in the Reactor Core for a VHTR	City College of New York	$1,118,856		Document	RCRD&D	FY2011
Preparation of High Purity, High Molecular-Weight Chitin from Ionic Liquids for Use as an Adsorbate for the Extraction of Uranium from Seawater	University of Alabama	$338,260		Document	MSTR	FY2011
Graphite Microstructural Characterization Using Time-Domain and Correlation-Based Ultrasonics	Johns Hopkins University	$1,199,997		Document	RCRD&D	FY2011
Selectivity in Ligand Binding to Uranyl Compounds: A Synthetic, Structural, Thermodynamic and Computational Study	University of California-Berkeley	$500,000		Document	MSTR	FY2011
Methodology Development for Passive Component Reliability Modeling in a Multi-Physics Simulation Environment	The Ohio State University	$533,457		Document	RCRD&D	FY2011
Development of Seismic Isolation Systems Using Periodic Materials	University of Houston	$538,154		Document	MSTR	FY2011
Pebble Fuel Handling and Reactivity Control for Salt-Cooled High Temperature Reactors	University of California, Berkeley	$612,721		Document	RCRD&D	FY2011
Innovative Elution Processes for Recovering Uranium from Seawater	University of Idaho	$400,000		Document	MSTR	FY2011
Self-Sustaining Thorium Boiling Water Reactors	University of California, Berkeley	$1,145,932		Document	RCRD&D	FY2011
Development of Austenitic ODS Strengthened Alloys for Very High Temperature Applications	University of Illinois-Urbana Champaign	$538,154		Document	MSTR	FY2011
High Fluency Low Flux Embrittlement Models of LWR Reactor Pressure Vessel Embrittlement and a Supporting Database from the UCSB ATR-2 Irradiation Experiment	University of California, Santa Barbara	$1,199,607		Document	RCRD&D	FY2011
Enhancement of the Extraction of the Uranium from Seawater	University of Maryland	$400,000		Document	MSTR	FY2011
A Research Program for Fission Product/Dust Transport in HTGR's	University of Missouri-Columbia	$1,157,367		Document	RCRD&D	FY2011
Transient Safety Analysis of Fast Spectrum TRU Burning LWR with Internal Blankets	University of Michigan	$599,475		Document	MSTR	FY2011
Development and Validation of a Lifecycle-based Prognostics Architecture with Test Bed Validation	University of Tennessee, Knoxville	$846,315		Document	RCRD&D	FY2011
Development of Novel Sorbents for Uranium Extraction from Seawater	University of North Carolina, Chapel Hill	$400,000		Document	MSTR	FY2011
In-situ Condition Monitoring of Components in Small Modular Reactors Using Process and Electrical Signature Analysis	University of Tennessee, Knoxville	$650,000		Document	RCRD&D	FY2011
Radiation Behavior of High-Entropy Alloys for Advanced Reactors	University of Tennessee, Knoxville	$538,159		Document	MSTR	FY2011
Technical Development for S-CO2 Advanced Energy Conversion	University of Wisconsin	$815,000		Document	RCRD&D	FY2011
Rapid Computer Aided Ligand Design and Screening of Precious Metal Extractants from TRUEX Raffinate with Experimental Validation	Washington State University	$500,000		Document	MSTR	FY2011
Ag Transport Through Non-Irradiated and Irradiated SiC	University of Wisconsin-Madison	$1,055,456		Document	RCRD&D	FY2011
Critical Heat Flux Phenomena at High Pressure and Low Mass Fluxes: Tests and Models	University of Wisconsin-Madison	$1,199,781		Document	RCRD&D	FY2011
Modeling and Test Validation of a Reactor Cavity Cooling System with Air	University of Wisconsin-Madison	$1,199,988		Document	RCRD&D	FY2011
Transient Mixed Convection Validation for NGNP	Utah State University	$635,860		Document	RCRD&D	FY2011
Alternative High-Performance Ceramic Waste Forms	Alfred University	$840,000	This project aims to advance fundamental understanding of the kinetics of structural evolution of crystalline ceramic waste forms. The structure/property relationships will be identified and will reveal new formulations, improved processing routes, and strategies for improved performance or ceramic waste forms.	Document	FCR&D	FY2012
Surface Layer Bulk Glass Interface Evolution with Aqueous Corrosion	Alfred University	$880,000	This project will investigate the links between the morphology, structure and chemistry of surface layer-bulk glass interface and the long-term corrosion-reaction kinetics using in-situ and ex-situ experiments. The understanding will result in improved models for long-term predictive behavior of high-level-waste (HLW) glasses under repository conditions.	Document	FCR&D	FY2012
Improved Accident Tolerance of Austenitic Stainless Steel Cladding through Colossal Supersaturation with Interstitial Solutes	Case Western Reserve University	$850,000	This project aims to develop new case-hardened austenitic stainless steels by saturating them with materials that improve their mechanical properties, corrosion resistance and radiation resistance. This project, if successful, will result in safer, longer-lasting, and more accident tolerant fuel claddings.	Document	FCR&D	FY2012
Optimization of Deep Borehole Systems for HLW Disposal	Massachusetts Institute of Technology	$850,000	Researchers aim to carry out a comprehensive evaluation of the deep borehole option for disposal of used nuclear fuel and high livel waste. The models developed will predict potential movement of water through natural and engineered barriers and release of radionuclides to the biosphere which will aide in site selection.	Document	FCR&D	FY2012
Scholarship for Nuclear Communications and Methods for Evaluation of Nuclear Project Acceptability	Massachusetts Institute of Technology	$800,000	Researchers will work to develop a model to characterize the factors affecting social acceptance of nuclear projects with potential stakeholders. The resultant model will strengthen the ability to design and implement large projects more efficiently, leading to higher rates of success of future nuclear projects.	Document	FCR&D	FY2012
Accurate Holdup Calculations with Predictive Modeling and Data Integration	North Carolina State University	$875,000	Researchers will develop and use state-of-the-art radiation transport codes to account accurately for the fissile material in a nuclear materials processing facility. An accurate estimation of the materials will allow for ensured radiological safety, security, waste management and efficient plant operation.	Document	FCR&D	FY2012
Novel Metal Sulfides to Achieve Effective Capture and Durable Consolidation of Radionuclides	Northwestern University	$760,000	Researchers will evaluate the effectiveness of chalcogenide based materials design novel metal sulfides to effectively capture and store of radioisotopes released during reprocessing of used nuclear fuel. This project will focus on understanding structure-property relationships to enable refined and direct synthesis approaches for improved and cost-efficient nuclear waste forms.	Document	FCR&D	FY2012
Nonlinear Ultrasonic Diagnosis and Prognosis of ASR Damage in Dry Cask Storage	Northwestern University	$885,000	Researchers aim to use nondestructive damage characterization methods to detect, manage and mitigate the degradation/damage mechanisms of dry cask storage systems for nuclear fuels. This project, if successful, will provide tools that will allow the prediction of the reliability and the safety of concrete structures in dry cask storage systems.	Document	FCR&D	FY2012
Prototype Demonstration of Gamma-Blind Tensioned Metastable Fluid Neutron/Multiplicity/Alpha Detector- Real Time Methods for Advanced Fuel Cycle Applications	Texas A&M University	$875,000	This project aims to create a prototype demonstration of a novel neutron/alpha detector based on a technology that is blind to gamma field used fuel. The prototype, if successful, will enhance instrumentation for monitoring real-time material balance during various stages of the nuclear cycle.	Document	FCR&D	FY2012
Testing of Sapphire Optical Fiber and Sensors in Intense Radiation Fields, when Subjected to Very High Temperatures	The Ohio State University	$885,000	The researchers on this project will investigate the performance of sapphire optical fibers and sensors in reactor environments. The project, if successful, will result in improved instrumentation to understand the behavior and predict performance of nuclear fuel systems at the microstructural level.	Document	FCR&D	FY2012
Concrete Materials with Ultra-High Damage Resistance and Self-Sensing Capacity for Extended Nuclear Fuel Storage Systems	University of California, Irvine	$800,000	Researchers aim to design a new class of multifunctional concrete materials. This project, if successful, will result in a novel multifunctional concrete material that possesses inherent degradation monitoring capability and is suitable for an extended storage system for the used nuclear fuel.	Document	FCR&D	FY2012
Development of Innovative Accident Tolerant High Thermal Conductivity UO2 Fuel Pellets with a Diamond Dopant	University of Florida	$800,000	Researchers will evaluate the use of diamond nanoparticles composite material in innovative accident tolerant fuel pellets. This could significantly improve both the thermal conductivity of fuel pellets and light water reactors' efficiency safety.	Document	FCR&D	FY2012
Probabilistic Multi-Hazard Assessment of Dry Cask Structures	University of Houston	$865,000	This project aims to investigate the performance of dry cask storage systems under multiple hazard systems (earthquake, tornados, combined with aging effects) using a probabilistic multi-hazard framework. This framework will be validated based on experimental research and will provide improved models for safety and reliability of spent nuclear fuels during storage and transportation.	Document	FCR&D	FY2012
Measurement of Irradiated Pyroprocessing Samples via Laser Induced Breakdown Spectroscopy	University of Idaho	$820,000	This project aims to use advanced characterization techniques to investigate microstructural changes and the micromechanisms related to irradiation induced damage in used nuclear fuels and waste forms. This project, if successful, will result in enhanced models to predict the structural and chemical response of used fuel and waster forms during interim storage and permanent disposal.	Document	FCR&D	FY2012
Elastic/Inelastic Measurement Project	University of Kentucky	$880,523	Researchers will measure nuclear data for elastic/inelastic scattered neutrons on coolants and structural materials. The data generated, will be useful for future R&D programs that will study innovative next generation LWR and future fast systems.	Document	FCR&D	FY2012
Electrochemical Corrosion Studies for Modeling Metallic Waste Form Release Rates	University of Nevada- Las Vegas	$790,000	This project aims to use advanced electrochemical methods to investigate the corrosion related degradation of metal alloys used for housing fission products. The data obtained from this study will allow for the prediction of the long-term behavior of the metallic host phase materials over geological time-scales.	Document	FCR&D	FY2012
Thermodynamic and Microstructural Mechanisms in the Corrosion of Advanced Ceramic Tc-bearing Waste Forms and Thermophysical Properties	University of Nevada- Las Vegas	$795,000	This project team will harvest thermodynamic and microstructural data on the evolution of ceramic based waste forms. The data will be used to advance the current state-of-the-art methodology used for isolation and stabilization of fission products and improve on nuclear fuel recycling processes.	Document	FCR&D	FY2012
Development and Experimental Benchmark of Simulations to Predict Used Nuclear Fuel Cladding Temperatures during Drying and Transfer Operations	University of Nevada- Reno	$745,000	Researchers will conduct experiments to investigate and develop advanced computational models of heat transfer in post-pool-storage drying operations. This project, if successful, will result in tools that can be used to design efficient drying processes to as to ensure suitability for dry-cask systems for long-term storage and transport.	Document	FCR&D	FY2012
Better Radiation Response and Accident Tolerance of Nanostructured Ceramic Fuel Materials?	University of Tennessee	$815,000	Researchers will use novel experimental methods to investigate the links between microstructure, phase stability and damage evolution in nanostructured ceramic fuel materials. The project will study fuel materials at temperatures and irradiation conditions relevant to operation and accidental scenarios.	Document	FCR&D	FY2012
Radiation and Thermal Effects on Used Nuclear Fuel and Nuclear Waste Forms	University of Tennesssee	$770,000	This project aims to investigate the structural and chemical response of used nuclear fuel and waste forms during interim storage and permanent disposal. If successful, this project will generate models that will allow the prediction of structural evolution and hence the radiological safety and security of nuclear fuel and waste forms.	Document	FCR&D	FY2012
Seismic Performance of Dry Casks Storage for Long-Term Exposure	University of Utah	$873,319	Researchers will evaluate the mechanical performance of dry-cask storage under seismic loading for mid-term operational periods. Simulations will include scenarios for freestanding, anchored, and vaulted casks. The experimental tests will also evaluate the dynamic seismic response of freestanding and anchored dry-cask storage prototypes, providing recommendations for optimal Interim Spent Fuel Storage Installations (ISFSIs) design.	Document	FCR&D	FY2012
Validation Experiments for Spent-Fuel Dry-Cask In-Basket Convection	Utah State University	$690,000	Researchers in this project aim to conduct experiments that generate data on natural convection through a fuel assembly. The data will be used to validate the computational models being developed for nuclear safety and design.	Document	FCR&D	FY2012
Re-Branding the Nuclear Fuel Cycle	Virginia Commonwealth University	$850,000	This project will create a comprehensive framework for the evaluation of alternative fuel cycle systems that will be used to identify and analyze key elements related to long-term management of nuclear fuels , with the ultimate goal to develop a communications strategy to reach stakeholders.	Document	FCR&D	FY2012
Advanced Characterization of Molecular Interactions in TALSPEAK-like Separations Systems	Washington State University	$875,000	Researchers will use advanced characterization techniques (experimental and computational) to improve understanding of the molecular level processes/interactions during separation processes for advanced fuel cycles. The understanding of these interactions will be used to develop more robust and streamlined separation processes for advanced fuel cycles.	Document	FCR&D	FY2012
Coupling of Nuclear Waste Form Corrosion and Radionuclide Transport in Presence of Relevant Repository Sediments	Washington State University	$885,000	Researchers will conduct experiments to understand the mechanisms responsible for the corrosion of nuclear waste forms in realistic chemical environments. The data generated from these experiments will enable increased reliability of the models used to predict the waste form performance in repository environments.	Document	FCR&D	FY2012
Stationary Liquid Fuel Fast Reactor (SLFFR) Concept for TRU Burning	Purdue University	$450,000	Reasearchers will investigate a new type of molten metallic fuel reactor concept that will consume hazardous transuranic waste. The liquid fuel alloy has several advantages over solid fuel fast reactors that are used for the same purpose.	Document	MSTR	FY2012
ABR for TRU Transmutation with Breed & Burn Thorium Blanket for Improved Economics and Resource Utilization	University of California- Berkeley	$450,000	The research team will use detailed neutronic analysis for a new Advanced Burner Reactor concept with low conversion ratio. The concept will use a new core shape to improve the utilization of neutrons to perform breed and burn.	Document	MSTR	FY2012
New Materials for High Temperature Thermoelecric Power Generation	University of California, Davis	$450,000	Reasearchers will work to develop nanostructured and other new materials to support the development of higher efficiency thermoelectric devices. These devices convert thermal energy to electricity with no moving parts. The new materials will operate at higher efficiencies and over a wider temperature range than those currently available--an important quality for future nuclear-powered deep space exploration.	Document	MSTR	FY2012
Microscopic Fuel Particles Produced by Self-Assembly of Actinide Nanoclusters on Carbon Nanomaterials	University of Notre Dame	$440,000	Reasearchers will develop the mechanisms, conditions and protocols to prepare uranium-carbon nanocomposite materials to make them more flexible. This could result in the generation of wholesale electricity, providing process heat, and providing power for households.	Document	MSTR	FY2012
High Hydrogen Content Graphene Hydride Compounds & High Cross-Section Cladding Coatings for Fast Neutron Detection	University of South Carolina	$430,000	This project will exploit recent breakthroughs to grow epitaxial graphene on commercial SiC wafers. This will allow researchers to develop a new detection method for fast neutrons. In addition, it will lead to better and more compact neutron detection system.	Document	MSTR	FY2012
Reducing Actinide Production Using Inert Matrix Fuels	University of Texas- Austin	$435,000	Reasearchers will perform a neutronic analysis, a thermal-hydraulic analysis and a simulation of fuel decay heat as a functionof fuel burnup, to determine if inert matrix fuel in coventional reactors will continue to be licensable. If successful, the inert matrix fuel mixtures will reduce harmful transuranic components in the fuel discharge streams at a level comparable to a fast reactcor burner.	Document	MSTR	FY2012
An Integrated Fuel Depletion Calculator for Fuel Cycle Options Analysis	University of Texas- Austin	$395,000	Reasearchers use new analysis techniques to better predict nuclear fuel behavior. The new model will allow improved fuel cycle for a larger number of users.	Document	MSTR	FY2012
Atomic-Scale to Meso-Scale Simulation Studies of Thermal Ageing and Irradiation Effects in Fe-Cr Alloys	Boston University	$874,997	Reasearchers will develop predictive, multi-scale simulation tools for iron-chromium alloys, which are expected to be key components of advanced steels envisioned as fuel cladding and structural components for Generation IV reactors. Such modeling is necessary to avoid resource intensive and costly thermal and neutron irradiation experiments to obtain required performance data.	Document	NEAMS	FY2012
Validation Data and Model Development for Fuel Assembly Response to Seismic Loads	George Washington University	$862,435	Reasearchers will conduct experiments that will provide comprehensive data characterizing the dynamics of the fluid and the structure in Pressurized Water Reactors (PWR) fuel assemblies under seismic loads (earthquakes and loss of coolant accidents). Completion of their project will greatly benefit the safety of existing and future nuclear reactors.	Document	NEAMS	FY2012
Uncertainty Quantification and Management for Multiscale Nuclear Materials Modeling	Georgia Institute of Technology	$743,444	Reasearchers will address the question of uncertainty propogation and error estimates associated with model prediction of material behavior under irradiation. Their work will facilitate a better understanding of the connection of various unit processes to collective responses in a multiscale model chain enabling the development of high strength and high ductility materials.	Document	NEAMS	FY2012
Fuel and Core Design Options to Overcome the Heavy Metal Loading Limit and Improve Performance and Safety of Liquid Salt Cooled Reactors	Georgia Insitute of Technology	$784,689	Reasearchers will examine new options for fuel and core designs in liquid salt cooled reactors where the current standard of TRISO type fuel has limitations due to loading characteristics. The research could enable new, more feasible fuel-core-reload options that will improve safety and performance parameters.	Document	RCRD&D	FY2012
Nonlinear Ultrasonic Techniques to Monitor Radiation Damage in RPV and Internal Components	Georgia Institute of Technology	$877,000	Reasearchers will explore new nondestructive materials evaluation and monitoring techniques utilizing nonlinear ultrasonic measurements . This technique will allow researchers to assess remaining useful life of select reactor components. Breakthroughs in this area will lead to the ability to characterize radiation damage in reactor pressure vessels and other components-leading to a clearer definition of reactor safety margins.	Document	RCRD&D	FY2012
Intergral Reactor Containment Condensation Model and Experimental Validation	Oregon State University	$871,119	Reasearchers will conduct experiments to enhance the safety and efficiency of small modular reactors (SMRs). This project will assess the impact of high-pressure steam condensation on steel containment vessels to be used for SMR deigns.	Document	RCRD&D	FY2012
Investigation of Natural Circulation Instability and Transients in Passively Safe Small Modular Reactors	Purdue University	$871,100	Reasearchers will perform scaled experiments to study the thermal-hydraulic instabilities that can occur in Small Modular Reactors (SMR) which rely on natural circulation cooling during normal operation and accident conditions. Their work will not only improve our understanding of general natural circulation instability but also lead to the development of stability criteria and predictability in the operation of SMRÃs.	Document	RCRD&D	FY2012
Thermoelectric-Driven Sustainable Sensing and Actuation Systems for Fault-Tolerant Nuclear Incidents	State University of New York, Stony Brook	$599,802	Reasearchers will examine the use of solid-state thermoelectric generators to produce electricity to sense and opeate during both normal and abnormal situations. This will provide indefinite monitoring of key components during power outages or station blackouts.	Document	RCRD&D	FY2012
Experimental and CFD Studies of Coolant Flow Mixing within Scaled Models of the Upper and Lower Plenums of NGNP Gas-Cooled Reactors	Texas A&M University	$713,051	Reasearchers will model the internal coolant flow of a prismatic core very high temperature reactor (VHTR) by using large eddy simulation tools. This method will enable more accurate prediction of flow field characteristics and better evaluation of VHTR behavior under operational and accidental conditions.	Document	RCRD&D	FY2012
Demonstrating Hybrid Heat Transport and Energy Conversion System Performance Characterization Using Intelligent Control Systems	University of Idaho	$877,000	Reasearchers will demonstrate an intelligent control systems in a hybrid energy conversion loop for a next generation nuclear power plant. Hybrid energy systems are a method of optimizing the use of natural resources for energy production. Hybrid systems present an opportunity to develop domestic energy sources to improve energy security.	Document	RCRD&D	FY2012
Advanced Reactor-Intermediate Heat Exchanger (IHX) Coupling: Theoretical Modeling and Experimental Validation	University of Idaho	$869,997	Reasearchers will model the behavior of the Advanced Reactor Intermediate Heat Exchanger Chemical Process system and develop advanced control techniques that take into account abnormal scenarios. The data and information obtained will assist in the development of intelligent control systems for next generation nuclear reactor systems.	Document	RCRD&D	FY2012
Irradiation Performance of Fe-Cr Base Alloys	University of Illinois- Urbana Champaign	$876,332	Reasearchers will perform post-radiation analysis and develop tools for future development and application of the Fe-Cr class of alloys. The results of this research will lead to better modeling of performance and development of an alloy designated as the primary choice for reactor fuel cladding and structural applications in advanced systems.	Document	RCRD&D	FY2012
Accelerated Irradiations for High Dose Microstructures in Fast Reactor Alloys	University of Michigan	$831,876	Reasearchers will determine the extent to which high dose rate irradiation can be used as an irradiation damage tool to understand microstructure evolution at high doses and temperatures relevant to advanced fast reactors. The project will provide fundamental understanding of the effectiveness of this process and thus of microstructure development in irradiated materials.	Document	RCRD&D	FY2012
Mitigating IASCC of Reactor Core Internals by Post-Irradiation Annealing Advanced Mitigation Strategies	University of Michigan	$876,985	Reasearchers will determine the optimum Post-irradiation annealing (PIA)-driven mitigation strategy to extend the potential lifetime of light water reactors. Samples that have already been irradiated in a light water reactor will be used to test PIA treatments to understand IASCC initiation and propoagation, annealing kinetics, the role of microstructure features in irradation hardening and localized deformation, and the optimum mitigation strategy based on PIA.	Document	RCRD&D	FY2012
Experimentally Validated Numerical Models for Effects of Non-Isothermal Turbulent Mixing on Wall Stresses in High Temperature Reactors	University of Pittsburgh	$876,422	Reasearchers will develop a comprehensive experimentally validated computational framework for the turbulent mixing in the lower plenum of a very high temperature reactor (VHTR). Through CFD modeling and experimental validation, the results from this project will lay the groundwork for future stress analysis, failure and fatigue studies, and uncertainty quantification for the VHTR system.	Document	RCRD&D	FY2012
Role of Defects in Swelling and Creep of Irradiated SiC	University of Wisconsin- Madison	$875,350	Reasearchers will study mechanisms controlling both radiation swelling and radiation creep in silicon carbide. These two effects are crucial to understanding the issues associated with the brittle silicon carbide composite. Success in this project will ground progress in the adoption of silicon carbide for reactor solutions, particularly as fuel cladding.	Document	RCRD&D	FY2012
Advanced Supercritical Carbon Dioxide Brayton Cycle Development	University of Wisconsin, Madison	$877,000	Reasearchers will investigate the benefits of utilizing advanced Brayton cycles with supercritical carbon dioxide in new reactor systems and components. Benefits of this research include improvement of analysis and performance of components currently utilizing these cycles as well as the potential for a large scale advanced CO2 power system.	Document	RCRD&D	FY2012
Mechanical Behavior of UO2 at Sub-grain Length Scales: Quantification of Elastic, Plastic and Creep Properties via Microscale Testing	Arizona State University	$800,000	Reasearchers will develop techniques to measure properties at sub-grain scales using depleted Uranium Oxide samples. The project will provide a framework to measure sub-grain scale mechanical properties, as well as provide experimental data to improve the understanding of advanced oxide fuels.	Document	FCR&D	FY2013
The Impacts of Pore-Scale Physical and Chemical Heterogeneities on the Transport of Radionuclide-Carrying Colloids	Colorado School of Mines	$800,000	Reasearchers will identify the dominant transport mechanisms to develop models that predict radionuclide distribution in porous materials. Experimental and computational models will be created that couple pore-scale geometric and interfacial structures. Simulators such as these are a necessary step towards fully predictive models for field-scale applications in the future.	Document	FCR&D	FY2013
Recovery of Uranium from Seawater: Polymer-Supported Aminophosphinates as Selective Extractants	Hunter College, CUNY	$399,999	Reasearchers will prepare a polymer-supported extractant for the recovery of uranium from seawater. The project will focus on primary amines that could provide a 3-fold increase in uranium capture capacity than current methods.	Document	FCR&D	FY2013
In-pile Thermal Conductivity Characterization with Single-laser Heating/Time Resolved Raman	Iowa State University	$800,000	Reasearchers will develop a time-resolved Raman-based thermal conductivity measurement system to improve remote in-pile thermal conductivity measurement. These measurements will provide new insights into the behavior of materials exposed to extreme radiation and temperature environments. Understanding the behavior of materials at the microstructural level will support optimized fuel designs.	Document	FCR&D	FY2013
Organic Speciation and Interactions in ALSEP - One Step Partitioning Process of Minor Actinides, Lanthanides, and Fission Products	Oregon State University	$600,000	Reasearchers will investigate the Actinide-Lanthanide Separation (ALSEP) process organic phase prior to aqueous phase separation and after aqueous separation phases of bare and metal-loaded acids. Quantifying these effects can be used to determine how an engineering scale process will perform and generate an accurate chemical model for the system.	Document	FCR&D	FY2013
Glass Composition and Solution Speciation Effects on Stage III Dissolution	Pennsylvania State University	$700,000	Reasearchers will study the chemical and structural triggers of long-term vitrified nuclear waste form behavior. They will study a range of waste glass compositions in corrosive environments. The study will improve understanding of the long-term residual rate and may provide new options for environmental control of glass dissolution rates.	Document	FCR&D	FY2013
Correlating Thermal, Mechanical, and Electrical Coupling Based Multiphysics Behavior of Nuclear Materials Through In-Situ Measurements	Purdue University	$800,000	Reasearchers will use in-situ experimental techniques to monitor the influence of extreme conditions on fuel cladding. The project will establish an in-situ experimental setup that can predict change in thermal properties and their correlation with mechanical properties and correlate such changes to changes in microstructural and chemical features.	Document	FCR&D	FY2013
Creation of a Geant4 Muon Tomography Package for Imaging of Nuclear Fuel in Dry Cask Storage	Purdue University	$440,000	Reasearchers will develop a simulation and analysis package to aid in the non-destructive assessment of sealed used nuclear fuel dry casks using cosmic ray muons. Cosmic ray muon tomography allows for non-destructive assessment that can independently verify and identify weapons grade material sealed within dense dry casks.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Two-stage Fast Reactor Fuel Cycle Options for Optimum Resource Utilization and Waste Management	Purdue University	$400,000	Reasearchers will evaluate the two different two-stage fast reactor fuel cycle options that will offer efficient use of uranium resources and the ability to burn actinides and long-live fission products. Evaluation of these fast fuel cycle options will serve as a useful complement to the options currently being considered in the Fuel Cycle Options Campaign.	Document	FCR&D	FY2013
Mixed Metal Phosphonate-Phosphate Resins for Separation of Lanthanides from Actinides	Texas A&M University	$650,000	Reasearchers will use ion exchangers to cleanly separate lanthanides and curium from reusable actinides. The study will assist in the development of an inexpensive, simple way in which to separate lanthanides from actinides found in used nuclear fuel rods and to recover a large portion of the usable fuel.	Document	FCR&D	FY2013
Safeguards in Pyroprocessing: an Integrated Model Development and Measurement Data Analysis	The Ohio State University	$626,151	Reasearchers will develop a comprehensive and effective safeguards approach for a pyroprocessing facility to support safeguards for future fuel cycles in the United States. The new approach and design will focus directly on the special nuclear materials in the electrorefiner where actinides are separated from fission products through electrochemical process.	Document	FCR&D	FY2013
Using Ionic Liquids for the Development of Renewable Biopolymer-Based Adsorbents for the Extraction of Uranium from Seawater and Testing Under Marine Conditions	University of Alabama	$400,000	Reasearchers will explore the fundamental engineering parameters for a renewable high-performance adsorbent for the extraction of uranium from sweater based on a recently proven ionic liquid (IL)-chitin platform. The project will use the platform to develop a versatile, modifiable adsorbent and characterize its performance and degradation in marine conditions.	Document	FCR&D	FY2013
Developing Ultra-Small Scale Mechanical Testing Methods and Microstructural Investigation Procedures for Irradiated Materials.	University of California, Berkeley	$800,000	Reasearchers will develop new small-scale mechanical testing techniques to allow for the estimation or direct measurement of bulk properties. The combined experiments and modeling will significantly enhance the statistics and information that can be obtained on small radioactive archived samples, as well as new ion beam irradiated specimens.	Document	FCR&D	FY2013
Improved Delayed-Neutron Spectroscopy Using Trapped Ions	University of California, Berkeley	$400,000	Reasearchers will develop innovative spectroscopy techniques to measure the decay of fission fragments. The resulting data from these new techniques will be used to better understand reactor kinetics under accident conditions and failure scenarios.	Document	FCR&D	FY2013
Thermally and Chemically Responsive Nanoporous Materials for Efficient Capture of Fission Product Gases	University of California, Davis	$750,000	Reasearchers will create new nanoporous materials that will be highly effective at capturing fission product gases. These materials would be relevant to both reactor fuels applications and reprocessing operations. Tests will be performed in carbon based and nitride based nanostructures, with the most promising materials from the modeling perspective undergoing further testing.	Document	FCR&D	FY2013
Multiphase Nanocrystalline Ceramic Concept for Nuclear Fuel	University of California, Irvine	$800,000	Researchers will study the use of nanoparticles and nanostructured ceramics to create new materials that can extend the service life and increase efficiency for nuclear fuel. Multiphase nanocrystalline ceramics will be used to design simulated nuclear fuel that can provide added plasticity, better radiation tolerance and improved thermal conductivity.	Document	FCR&D	FY2013
Development of Novel Porous Sorbents for Extraction of Uranium from Seawater	University of Chicago	$400,000	Reasearchers will develop a highly porous sorbent for the extraction of uranium from seawater. Previous research has established sorbent performance. This project will use past foundational studies to design and investigate a new nanocomposites that will be processed into tacks or braids for field tests in seawater tests. The technology may also be used for other metals.	Document	FCR&D	FY2013
Microwave Readout Techniques for Very Large Arrays of Nuclear Sensors	University of Colorado, Boulder	$799,937	Reasearchers will develop a powerful readout technique based on microwave transmission and reflection. The technique will enable very large arrays of diverse sensor types for nuclear materials quantification and tracking. It will provide more accurate data on material composition and quantity.	Document	FCR&D	FY2013
BiI3 Gamma-Ray Spectrometers for Reliable Room-Temperature Nuclear Materials Safeguarding	University of Florida	$799,999	Reasearchers will develop gamma-ray spectrometers based on BiI3 single crystals for MPACT applications such as burnup validation quantification, improved assay of plutonium, determination of uranium enrichment and overall monitoring spent fuel within the fuel cycle. The project will improve energy resolution, efficiency and environmental performance with this new gamma-ray detector.	Document	FCR&D	FY2013
Innovative Coating of Nanostructured Vanadium Carbide on the F/M Cladding Tube Inner Surface for Mitigating the Fuel Cladding Chemical Interactions	University of Florida	$760,276	Researchers will develop barrier coatings on the inner surface of fuel cladding tubes to improve performance of materials at elevated temperatures and high neutron exposures in fast reactors. The project will develop and test a low temperature coating process of nanostructured vanadium carbide that will provide a benchmark for use in future studies.	Document	FCR&D	FY2013
Doubling the Life of Concrete Structures	University of Idaho	$800,000	Reasearchers will use nanoscale techniques to develop methods for doubling the service life of concrete structures. They will study the effect of temperature load and temperature cycling (freezing and thawing) on the durability of concrete with nanoscale viscosity modifiers. The project will benefit from non-destructive evaluation of concrete performance through electrochemical techniques.	Document	FCR&D	FY2013
Off-Gas Treatment: Evaluation of Nano-structured Sorbents for Selective Removal of Contaminants	University of Idaho	$785,910	Reasearchers will evaluate nanostructured sorbent materials for their effectiveness in removing and immobilizing radionuclides for the off-gas treatment from used nuclear fuel recycling operations. The project aims at achieving near-zero emissions of radionuclides by capturing them from the off-gas of recycling operations, allowing for the development of advanced fuel cycles.	Document	FCR&D	FY2013
Innovative Elution Processes for Recovering Uranium and Transition Metals from Amidoxime-Based Sorbents	University of Idaho	$399,864	Reasearchers will develop a new two-step elution process to achieve total recovery of uranium and effective recycling of the sorbent. The extraction process would selectively remove uranium from the sorbent with little or no damage. The process would then remove transition metals and regenerate the sorbent for repeated use, making uranium extraction from seawater economically viable.	Document	FCR&D	FY2013
Performance of a Steel/Oxide Composite Waste Form for Combined Waste Streams from Advanced Electrochemical Processes over Geologic Time Scales	University of Illinois at Chicago	$700,000	Reasearchers will develop and validate a mechanistically-based corrosion model for cermet-type waste forms, creating a testing protocol and modeling approach for predicting long-term performance. The study will apply novel electrochemical testing and modeling methods to the behavior of metal/oxide phase boundaries to evaluate waste form performance.	Document	FCR&D	FY2013
Enhancement of the Extraction of Uranium from Seawater	University of Maryland, College Park	$400,000	Reasearchers will develop and optimize novel adsorbents for uranium recovery from seawater. The team will use radiation-induced grafting of organic phosphates onto polymers. The experiments will use ocean water, with mechanistic analysis, to provide a solid basis for large-scale demonstration of the performance of the new adsorbents in ocean environments.	Document	FCR&D	FY2013
Improving the Understanding of the Coupled Thermal-Mechanical-Hydrologic Behavior of Consolidating Granular Salt	University of New Mexico	$800,000	Reasearchers will increase the understanding of granular salt seal materials for shafts, drifts and boreholes. By coupling thermal, mechanical and hydrological responses, the study will result in greater confidence in granular salt consolidation as a principal strategy for closure and isolation of long-term waste repositories.	Document	FCR&D	FY2013
Fission Fragment Yield Data in Support of Advanced Reactor Technology	University of New Mexico	$399,816	Reasearchers will produce a highly accurate data set for thermal fission. These precision data are necessary for high-accuracy simulations of nuclear criticality, transmutation rates, radiation effects and heating as well as for nuclear fuel, material accounting and identification needs.	Document	FCR&D	FY2013
Molecular dynamics-based simulations of bulk/interfacial structures and diffusion behaviors in nuclear waste glasses	University of North Texas	$700,000	Reasearchers will generate accurate atomic structural models for use in Monte Carlo simulations of the dissolution of nuclear waste glasses. Large-scale molecular dynamics-based computer simulations will be used to investigate self-diffusion behaviors, interfacial structure, and other structures formed during dissolution of these glasses.	Document	FCR&D	FY2013
U3Si2 Fabrication and Testing for Implementation into the BISON Fuel Performance Code	University of South Carolina	$800,000	Reasearchers will fabricate, test and model a high uranium density, advanced nuclear fuel that operates at a much lower temperature and stores less energy. The work will deliver key research data on creep and grain growth, improving economics, through possible power uprates, and advancing accident tolerant fuels research.	Document	FCR&D	FY2013
Structural Health Monitoring of Nuclear Spent Fuel Storage Facilities	University of South Carolina	$738,618	Reasearchers will develop a nuclear structural health monitoring system based on a sensing technology that monitors material degradation and aging for dry cask storage systems. The low-cost, low-profile sensors will perform on-demand monitoring of the structural integrity of individual components as well as the entire system.	Document	FCR&D	FY2013
ORIGEN-based Nuclear Fuel Depletion Module for Fuel Cycle Assessment	University of Tennessee at Knoxville	$755,181	Reasearchers will develop a flexible reactor analysis module for the CYCLUS fuel cycle simulator based on established tools for reactor fuel depletion and decay. They will use ORIGEN, a mature and experimentally validated code, affording greater flexibility and allowing for accurate evaluations of impacts of both present and future fuel cycle options.	Document	FCR&D	FY2013
Cost and System Analysis of Innovative Fuel Resources Concepts	University of Texas at Austin	$295,960	_This project will develop and test braided polymer fiber adsorbents that surpass the sorption capacity, selectivity and durability of the best existing technology to recover uranium from seawater.	Document	FCR&D	FY2013
Risk Assessment of Structural Integrity of Transportation Casks	University of Utah	$789,296	Reasearchers will assess the loss of structural integrity of transportation casks and fuel cladding after extended storage. This risk assessment will conduct experimental tests and simulations to evaluate the structural performance of fuel, fuel assemblies and cask components when subjected to vibration and impact loads during transport.	Document	FCR&D	FY2013
Market-Based and System-Wide Fuel Cycle Optimization	University of Wisconsin, Madison	$612,731	Reasearchers will create market and economic optimizers to improve calculations for the CYCLUS fuel cycle simulator. The team will leverage existing optimization software frameworks within the simulator to resolve top level policy questions. The optimizations will allow CYCLUS to move beyond static material compositions, providing a holistic view of the fuel cycle system.		FCR&D	FY2013
Optical Fiber Based System for Multiple Thermophysical Properties for Glove Box, Hot Cell and In-Pile Applications	Utah State University	$799,975	Reasearchers will use a small pressure vessel to develop a robust technique for the measurement of multiple thermophysical properties at very high temperatures. The technique will lead to a system design moving toward the eventual measurement of irradiated fuels in a glovebox and/or hot cell with all sensors and electronics outside of the glovebox and/or hot cell.	Document	FCR&D	FY2013
Development of a Nano-Modified Concrete for Next Generation of Storage Systems	Vanderbilt University	$796,268	Reasearchers will use nano-sized and nano-structured particles based on enhanced reactivity to develop a superior concrete for the long-term storage of used nuclear fuel. The project will use state-of-the-art experimental chemical and mechanical characterizations and computation analysis to assess the performance of nano-modified concretes.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Thorium Fuel Cycle Options	Vanderbilt University	$797,995	Reasearchers will develop six fuel cycle data packages for multi-stage, thermal fuel cycles which incorporate thorium. These new fuel cycle data packages will provide the opportunity to examine fuel cycle options beyond those which have traditionally been considered. A thorium fuel cycle database will also be assembled as a basis for thorium literature for future evaluations of the thorium fuel cycle.	Document	FCR&D	FY2013
Enhanced Shielding Performance of HLW Storage Packages via Multi-Component Coatings	Virginia Polytechnic Institute and State University	$796,947	Reasearchers will develop a multi-layer composite that will enhance long-term storage and facilitate safe transport of storage packages. This novel multi-layer, multi-component coating would create an outer shield material that is resistant to the corrosion, radiation, diffusion and thermal cycling processes that affect fuel packages during long term storage.	Document	FCR&D	FY2013
Managing Zirconium Chemistry and Phase Compatibility in Combined Process Separations for Minor Actinide Partitioning	Washington State University	$700,000	Reasearchers will address unique challenges for combining TRUEX and TALSPEAK processes for partitioning of lanthanides and minor actinides. The project will develop improved information on the thermodynamics of fission product zirconium and develop a framework for an organic phase solvation model. Combined process development could streamline separations processes.	Document	FCR&D	FY2013
Advances in the Recovery of Uranium from Seawater: Studies Under Real Ocean Conditions	Woods Hole Oceanographic Institution	$398,882	Reasearchers will provide infrastructure and expertise for marine testing of currently available adsorbents in real ocean conditions. The team will move adsorbent research from the lab to field testing in order to quantify sorptive properties and uranium uptake. The project will provide valuable field data that will show the potential of large scale applications of these technologies.	Document	FCR&D	FY2013
NEUP Project 20-19172: Irradiation of Sensors and Adhesive Couplants for Application in LWR Primary Loop Piping and Components		$497,881	Reasearchers paln to attach ultrasonic transducers to substrates using various adhesive couplants that will be irradiated at elevated temperature to simulate LWR primary loop conditions at the PULSTAR reactor at North Carolina State University. Ultrasonic data will be taken in-situ. Subsequently, the sensors and couplant interfaces will be characterized using the LAMDA facility at ORNL. The results will be used to benefit a parallel EPRI project on online monitoring of cracks in LWR primary loop piping._	Document	R&D NSUF	FY2013
NEUP Project 20-19404: Extension of MSTDB to Provide a High-Quality, Validated Thermochemical Database for Predicting/Simulating Corrosion in Molten Salt Reactor SystemsUniversity of South Carolina		$600,000	Reasearchers will generate a validated, consistent database of initial fuel compositions and potential corrossion products of fluoride and chloride salts, allowing for important phenomena predictions in molten salt reactors to guide confident decisions. The database will be integral to the currently being developed Molten Salt Thermochemical Database (MSTDB), structured to allow use by commercial and open source codes._	Document	NEAMS	FY2013
Lower Length Scale Characterization and Validation of Formation and Stability of Helium Bubbles in Nano-structured Ferritic Alloys under Irradiation	Clemson University	$399,870	Reasearchers will provide a fundamental knowledge about the formation and stability of ultra-fine helium bubbles within 14YWT after neutron/ion irradiation for further design of new advanced structural materials with a characteristic high density nanoparticles feature which can increase the mechanical strength, hardness, irradiation resistance and the operational temperature range of materials.	Document	NEAMS	FY2013
Three-Dimensional Fuel Pin Model Validation by Prediction of Hydrogen Distribution in Cladding and Comparison with Experiment	Pennsylvania State University	$800,000	Reasearchers will validate important three-dimensional aspects of the fuel pin modeling by using specialized numerical modeling techniques coupled with laboratory experiments to validate existing models for predicting fuel performance in light water reactors.	Document	NEAMS	FY2013
Collocation-Based Surrogate Models for Uncertainty Quantification and Validation of Coupled, Multiphysics Fuel Performance Simulation Tools	University of Michigan	$596,835	Reasearchers will provide the necessary high fidelity, coupled, multiphysics fuel performance simulator for computational modeling and develop surrogates which will accelerate and focus the validation of the coupled codes. This will be achieved by utilizing the high fidelity coupled fuel performance, thermal-hydraulics and neutronics codes BISON/STAR-CCM+/MPACT and an innovative collocation-based surrogate methodology.	Document	NEAMS	FY2013
Multi-Resolution In-Situ Testing and Mutliscale Simulation for Creep Damage Fatigue Damage Analysis of Alloy 617	Arizona State University	$800,000	This project will develop novel testing and experimentally validated prediction methodologies for micro-structural damage mechanisms of structural materials for advanced reactor systems. The investigations will focus on the characterization and testing of specific metal alloys, but the proposed testing and life-prediction methodologies are applicable to other structural materials as well.	Document	RCRD&D	FY2013
Novel High Temperature and Radiation Resistant Infrared Glasses and Optical Fibers for Sensing in Advanced Small Modular Reactors	Clemson University	$800,000	Clemson University, in partnership with the Iowa State University and the Pacific Northwest National Laboratory, will develop novel optical materials with improved heat and radiation exposure resistance in order to enable in-vessel fiber optic sensing for advanced Small Modular Reactors.	Document	RCRD&D	FY2013
Validation Data Acquisition in HTTF during PCC Events	George Washington University	$800,000	Reasearchers at the George Washington University and Oregon State University will collaborate with NASA Langley Research Center to measure flow velocities in a high temperature test facility. This work supports the development of very-high temperature reactors with passive safety systems.	Document	RCRD&D	FY2013
Advanced High Temperature Inspection Capabilities for Small Modular Reactors	Iowa State University	$790,822	The objective of this project is to develop non-destructive evaluation techniques for advanced small modular reactors. The research will provide key enabling inspection technologies needed to support the design and the reactor component performance validation process for advanced small modular reactors.	Document	RCRD&D	FY2013
Experimental and Computational Investigations of Plenum-to-Plenum Heat Transfer under Natural Circulation in a Prismatic Very High Temperature Reactor	Missouri University of Science and Technology	$799,999	Reasearchers will perform experimental and computational investigations to study heat transfer and natural circulation phenomena in very-high temperature reactors. The study will assist in the ability to predict and analyze passive safety systems.	Document	RCRD&D	FY2013
New Mechanistic Models of Creep-Fatigue Crack Growth Interactions for Advanced High Temperature Reactor Components	Oregon State University	$790,790	Reasearchers will create and validate a robust, multi-scale, numerical model to predict material degradation in nickel-based reactor alloys. If successful, this project will provide better numerical tools for reactor designers and greatly improve their capability to design against material failures for reactor alloys in the long term.	Document	RCRD&D	FY2013
Self-Powered Wireless Dual-mode Langasite Sensor for Pressure/Temperature Monitoring of Nuclear Reactors	State University of New York, Stony Brook	$800,000	This research will develop a novel self-powered wireless hybrid sensor that can accurately monitor both pressure and temperature using a single device without requiring external electricity, even in extreme harsh environments.	Document	RCRD&D	FY2013
Compact Heat Exchanger Design and Testing for Advanced Nuclear Reactors and Advanced Power Cycles	The Ohio State University	$800,000	The goal of this project is to investigate optimal heat exchanger designs for advanced reactors. The research will study the optimization of printed circuit heat exchangers for specific fluids under a variety of conditions as well as perform numerical modeling. Experiments will focus on thermal performance and heat stress during extreme conditions.	Document	RCRD&D	FY2013
Fundamental Understanding of Creep-Fatigue Interactions in 9Cr-1MoV Steel Welds	The Ohio State University	$798,000	This project will advance the state of knowledge and fundamental understanding of deforming materials and welds under loading conditions. Specifically, new integrated testing procedures will be evaluated and applied for conditions that are most detrimental to material stability leading to improved predictions of life expectancy for reactor steels and welds.	Document	RCRD&D	FY2013
Advanced Mechanistic 3D Spatial Modeling and Analysis Methods to Accurately Represent Nuclear Facility External Event Scenarios	The Ohio State University	$800,000	Reasearchers will develop three-dimensional characterization uncertainty analysis for commercial power plants. The project will involve combining experts from the fields of seismic structural modeling and advanced methods of risk assessment. This effort is expected to result in next generation tools that can be used for assessment of seismic risks.	Document	RCRD&D	FY2013
Tritium Mitigation/Control for Advanced Reactor Systems	The Ohio State University	$400,000	Reasearchers will develop a fluoride salt cooled high-temperature reactor featuring a specialized system to control tritium production. If successful, this will result in a significant reduction in size and cost in comparison to other reactor designs.	Document	RCRD&D	FY2013
A Pebble-Bed Breed and Burn Reactor	University of California, Berkeley	$400,000	Reasearchers will assess the feasibility of designing a type of metal cooled reactor able to establish and maintain operation when fueled with depleted uranium. If successful, this reactor will offer at least a 30-fold increase in the uranium ore utilization versus that achieved in contemporary light water reactors without the need for fuel reprocessing and recycling.	Document	RCRD&D	FY2013
Investigation of Thermal Aging Effects on the Evolution of Microstructure and Mechanical Properties of Cast Duplex Stainless Steels	University of Maryland, College Park	$799,966	This research will provide a better understanding of the microstructural evolution and simultaneous change in mechanical response during aging. The results of the research will provide data that can be used to estimate degraded mechanical properties for an 80-year service life of light water reactors.	Document	RCRD&D	FY2013
Model validation using CFD-grade experimental database for NGNP Reactor Cavity Cooling Systems with water and air	University of Michigan	$799,348	Reasearchers will use advanced innovative instrumentation to build a high-resolution experimental database and to use the novel experimental data to assess and further develop the predictive capabilities of computer codes for thermal hydraulics and computational fluid dynamics. The improved models developed by this project will also have the direct benefit of improving the predictive capability of the passive systems of third generation light water reactors and small modular reactor systems.	Document	RCRD&D	FY2013
Long-Term Prediction of Emissivity of Structural Material for High Temperature Reactor Systems	University of Missouri	$799,117	Reasearchers will study specific types of emissivity driven cooling from a variety of materials that are relevant to nuclear reactors. The research will provide a basis for numerical modeling to support reactor development.	Document	RCRD&D	FY2013
Advanced I&C for Fault-Tolerant Supervisory Control of Small Modular Reactors	University of Pittsburgh	$800,000	The purpose of this research is to develop advanced instrumentation and control techniques for supervisory control of advanced small modular reactors. This research supports the operational goals of small modular reactor concepts through the development of improved oversight and surveillance techniques.	Document	RCRD&D	FY2013
Corrosion of Structural Materials for Advanced Supercritical Carbon-Dioxide Brayton Cycle	University of Wisconsin-Madison	$798,672	Reasearchers will study a variety of materials for corrosion resistance under conditions that improve power conversion. In addition to studying the corrosion resistance of the materials, researchers will study the effect of additives to mitigate corrosion. Development of corrosion theories and modeling aimed at prediction of long-term corrosion will be the underlying theme throughout the project.	Document	RCRD&D	FY2013
Component and Technology Development for Advanced Liquid Metal Reactors	University of Wisconsin-Madison	$798,920	In support of liquid metal cooled reactors, the University of Wisconsin, Madison will evaluate advanced alloys and ceramics that come in contact with liquid metals. Additionally, a robust oxygen sensor and for use in liquid metals will be developed in order to better evaluate corrosion profiles in support of diagnostic testing.	Document	RCRD&D	FY2013
A New Paradigm for Understanding Multi-phase Ceramic Waste Form Performance	Clemson University	$800,000	Researchers will use advanced characterization tools to develop 3-D microstructural data that can be incorporated into computer-based simulations in order to predict the performance of waste forms. Materials system modeling will incorporate elemental release and the interconnected microstructural network of phases to better understand performance and degradation, which will accelerate waste form acceptance in repository settings.	Document	FCR&D	FY2014
Controlling Hexavalent Americium: A Centerpiece to a Compact Nuclear Fuel Cycle	Colorado School of Mines	$800,000	Researchers will develop and exploit the fundamental chemistry of Americium to enable an industrially viable means to co-recover the major and minor actinide elements from used nuclear fuel. The results would be a significant step forward in the development of aqueous separations approaches designed to recover the U-Am actinides based on the availability of the hexavalent oxidation state.	Document	FCR&D	FY2014
Zeolite Membranes for Krypton/Xenon Separation from Spent Nuclear Fuel Reprocessing Off-Gas	Georgia Institute of Technology	$400,000	Researchers will develop a high-performance, lower-cost zeolitic membrane process for Kr/Xe separations during spent nuclear fuel processing. Current separation methods are not considered economical and a membrane process would have relatively lower cost, equipment size, and ambient operating temperature. The process would form a sound basis for further development of this transformative separation technology for the nuclear fuel cycle.	Document	FCR&D	FY2014
Optimizing Polymer-Grafted Amidoxime-based Adsorbents for Uranium Uptake from Seawater	Georgia Institute of Technology	$399,999	Researchers will work to increase the adsorbent capacity and selectivity toward uranium by optimizing the adsorbent morphology, synthesis variables, and conditioning parameters and by investigating the rate-limiting variables through transport and reaction modeling. A novel adsorption/partition concept that has the potential to substantially increase the adsorbent capacity will be tested, making uranium from seawater extraction more economically viable.	Document	FCR&D	FY2014
Extraction of Uranium from Seawater: Design and Testing of a Symbiotic System	Massachusetts Institute of Technology	$400,000	Researchers will develop a seawater uranium extraction system that will work symbiotically with an offshore windmill by utilizing the structure, mooring and power of the windmill, while increasing the energy harvested by the installation. Uranium will be extracted by an adsorbent polymer belt, which will be cycled through the seawater and an elution plant located at the base of the windmill tower. Increasing the frequency of harvesting could overcome current economic barriers to seawater uranium extraction.	Document	FCR&D	FY2014
Imaging a Dry Storage Cask with Cosmic Ray Muons	Oregon State University	$799,871	Researchers will develop an imaging system to monitor the content of a dry storage cask with cosmic ray muons. A very large amount of plutonium under nuclear safeguards is contained in used fuel assemblies stored in dry storage casks. Muon imaging will allow a cost effective and reliable way to evaluate dry storage cask content and integrity before transport.	Document	FCR&D	FY2014
Apatite and sodalite based glass-bonded waste forms for immobilization of 129I and mixed halide radioactive wastes	Rutgers University	$800,000	Researchers will develop advanced and chemically durable waste forms for immobilizing 129I (aqueous based reprocessing of fuel) and mixed-halide wastes (molten-salt processing of fuel) by low temperature synthesis. Halide-containing sodalite and calcium phosphate-based apatite minerals will be synthesized, consolidated and tested for chemical durability. The project will provide needed baseline data for the development of advanced waste forms for immobilization of iodine and mixed-halide wastes.	Document	FCR&D	FY2014
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$350,000	Researchers will develop modeling tools supported by experiments for off-gas capture from future nuclear-fuel recycling facilities. Target species include tritium, iodine, krypton, and xenon. The models are intended to provide path forward recommendations to develop off-gas treatment adsorption processes. The project will contribute to the evaluation of options for environmentally acceptable recycle systems.	Document	FCR&D	FY2014
Development of high performance ODS alloys	Texas A&M University	$800,000	Researchers will study swelling, radiation hardening and changes in mechanical properties of ODS alloys to develop two sets of advanced ODS alloys. Two sets of first-round candidate alloys that have already undergone extensive development and testing will evaluate irradiation performance. The study will meet the need for high strength, radiation-tolerant cladding and core components that have enhanced resistance to void swelling.	Document	FCR&D	FY2014
Rare Earth Electrochemical Property Measurements and Phase Diagram Development in a Complex Molten Salt Mixture for Molten Salt Recycle	The Ohio State University	$800,000	Researchers will investigate rare earth (RE) properties in complex molten salt mixtures. In a molten salt recycle approach, the RE drawdown by electrolysis is a key step in which REs are separated from salt containing other fission products. Investigation of RE electrolysis must consider the electrochemical properties of the REs. We propose to conduct studies of detailed experiments and corresponding models to provide the physical properties and phase diagrams required to predict the performance of RE drawdown for processing complex molten salts.	Document	FCR&D	FY2014
Studies of Lanthanide Transport in Metallic Nuclear Fuels	The Ohio State University	$800,000	Researchers will study the redistribution of lanthanides and migration of lanthanides to the fuel surface. The mechanisms of lanthanide transport in metallic fuel based on the novel discovery of a Ôliquid-likeÕ transport mechanism will be studied analytically and experimentally. The project will develop a fundamental understanding of lanthanide fission product migration and redistribution in advanced metallic nuclear fuels, and theory and data to mitigate fuel-cladding chemical interactions.	Document	FCR&D	FY2014
Computational and Experimental Studies of Microstructure-Scale Porosity in Metallic Fuels for Improved Gas Swelling Behavior	University of Arkansas	$796,823	Researchers will study the microstructure of metallic uranium alloy fuels, and their resistance to densification, to minimize in-pile irradiation swelling through bimodal pore size distribution. The project will develop a predictive approach to design metallic fuel microstructures for optimal swelling resistance and fission gas retention.	Document	FCR&D	FY2014
Improved Hybrid Modeling of Spent Fuel Storage Facilities	University of California, Berkeley	$645,393	Researchers will develop a variance reduction method for computational transport that will improve the ability to design and operate monitoring systems for interim used fuel installations through enhanced modeling and simulation. This new tool will demonstrate that modeling calculations can be done more accurately in less time than with current tools and will perform studies characterizing how changes in material, cask configurations, and number of casks could impact monitoring systems.	Document	FCR&D	FY2014
Selective ligands for uranyl via combinatorial peptoid libraries: A synthetic, structural, thermodynamic and computational study	University of California, Berkeley	$400,000	Researchers will study how donor ligands bind to the uranyl ion, UO22+, with the longer-term goal of using this information to tackle selective recognition of uranyl in aqueous solution. The study will impact underlying approaches to controlling the behavior of uranium in these systems. The actinide separation technology could be used in several areas including uranium extraction from seawater, nuclear waste remediation and nuclear materials.	Document	FCR&D	FY2014
Combining Experiments and Simulations of Extraction Kinetics and Thermodynamics in Advanced Separation Processes for Used Nuclear Fuel	University of California, Irvine	$799,938	Researchers will study how the kinetics and thermodynamics of metal ion extraction in advanced separation processes for used nuclear fuel can be described by molecular dynamic (MD) simulations and how the simulations can be validated by experimental data. The project would have broad impacts on several separations processes including advanced TALSPEAK, ALSEP and GANEX by increasing the confidence and accuracy of computer modeling of metal ion extraction._	Document	FCR&D	FY2014
Effect of Metallic Li on the Behavior of Metals in Molten Salts	University of Nevada, Reno	$458,250	Researchers will identify the effect of metallic lithium on materials that are used in molten salt recycling. The study will try to understand how the presence of Li(0) in molten salts affects the degradation of alloys. Studying these changes will help accurately predict container material behavior and longevity.	Document	FCR&D	FY2014
Assessment of Corrosion Resistance of Promising Accident Tolerant Fuel Cladding under Reactor Conditions	University of Notre Dame	$800,000	Researchers will assess the corrosion behavior of accident tolerant fuel candidate iron-based alloys under normal LWR operating conditions consisting of high temperature, relevant water chemistry and irradiation. The assessment will produce data about possible irradiation-accelerated corrosion rates of iron-based alloys, and the mechanisms by which such corrosion rates are accelerated. The project will advance the selection of appropriate replacements for Zircaloy cladding.	Document	FCR&D	FY2014
Functionalized Porous Organic Polymers as Uranium Nano-Traps for Efficient Recovery of Uranium from Seawaterr	University of South Florida	$399,000	Researchers will develop functionalized porous organic polymers, or Ônano-trapsÕ for extraction of uranium from seawater. This technique allows for increased surface area and custom-designed pore size and chemistry to fit specific parameters. The adsorbent materials have high efficiency and effectiveness for uranium recovery from seawater, providing a potential supply for nuclear fuel.	Document	FCR&D	FY2014
Enhanced Accident-Tolerant Fuel Performance and Reliability for Aggressive iPWR/SMR Operation	University of Tennessee	$799,967	To develop a process that evaluates operational and safety performance of reactor-and-fuel combinations by integrating whole-core 3D neutronics with MOOSE/BISON fuel performance assessments via explicit time and space dependent fuel rod operational power histories. The project will be valuable in analyzing and evaluating accident tolerant fuel concepts and furthering the understanding of reactor physics and fuel performance aspects of key accident tolerant fuel concepts.	Document	FCR&D	FY2014
Nuclear Technology R&D Strategies in an Era of Energy Price Uncertainty	University of Texas, Austin	$799,112	Researchers will identify nuclear technology options that are competitive over a wide range of plausible future business environments. No single nuclear technology or business practice will be the best choice across all or even most future conditions. The study will focus on hybrid nuclear-fossil technologies, energy storage and conversion, which will result in an identification of nuclear strategies that can succeed under future market conditions.	Document	FCR&D	FY2014
Development and Optimization of Voltammetric Methods for Real Time Analysis of Electrorefiner Salt with High Concentrations of Actinides and Fission Products	University of Utah	$621,612	Researchers will develop an advanced voltammetry method to pursue the objective of real time monitoring of actinide concentrations in electrorefiner salt. This will include experimental measurement of key parameters such as activity coefficients and exchange current density. It will also involve simulation of voltammetry processes based on first principles. The project will allow for real time measurements that could support the commercialization of pyroprocessing.	Document	FCR&D	FY2014
Development of Self-Healing Zirconium-Silicide Coatings for Improved Performance of Zirconium-Alloy Fuel Cladding	University of Wisconsin, Madison	$798,621	Researchers will study the deposition of self-healing zirconium-silicide coatings on zirconium-alloy fuel cladding material to improve corrosion resistance under normal and accident conditions. Under these conditions, Zr-Si coating evolves into a highly protective functionally-graded multilayered system. The study will lead to improved performance of zirconium-alloy fuels._	Document	FCR&D	FY2014
Thermal Conductivity in Metallic Fuels	Virginia Polytechnic Institute and State University	$799,837	Researchers will calculate the thermal conductivity of metallic uranium and neptunium alloys, including the effects of noble gasses, using density functional theory. The experiments will validate the calculated effective thermal conductivity using the MARMOT code and by helping determine DFT simulation parameters. The study works to improve fuel lifetime by understanding its thermal behavior.	Document	FCR&D	FY2014
SiC-ODS Alloy Gradient Nanocomposites as Novel Cladding Materials	Virginia Polytechnic Institute and State University	$799,998	Researchers will combine nuclear nanomaterial design, processing, testing, and characterization efforts to develop revolutionary materials that can withstand neutron irradiation for long period of time using nanostructured SiC and oxide dispersion strengthened steel. The ultimate objective is to offer new cladding materials with increased corrosion resistance, strength, and creep resistance in both steady state and accident conditions.	Document	FCR&D	FY2014
Experimental Breeder Reactor II Benchmark Evaluation	Idaho State University	$400,000	Researchers will develop a benchmark evaluation of the Experimental Breeder Reactor II (EBR-II). During nearly 30 years of operation numerous experiments were conducted at EBR-II. The most significant of these experiments were conducted in 1986 demonstrating inherent safety features in loss of flow without reactor scram and loss of heat sink without reactor scram. Benchmark evaluation will be valuable for the reactor design efforts in the United States and South Korea.	Document	MSNE	FY2014
Integral full core multi-physics PWR benchmark with measured data	Massachusetts Institute of Technology	$400,000	Researchers will introduce BEAVRS, a new multi-cycle full-core Pressurized Water Reactor (PWR) depletion benchmark based on two operational cycles of a commercial nuclear power plant. This project aims at addressing the uncertainty quantification of the measured data and on making this benchmark a true non-proprietary international benchmark for the validation of high-fidelity multi-physics computational tools.	Document	MSNE	FY2014
Benchmark Evaluation of PROTEUS Gas-Cooled Reactor Experiments	University of Florida	$400,000	Researchers will create International Reactor Physics Experiment Evaluation Project (IRPhEP) benchmarks using data from 1970s experiments of the neutronics of gas-cooled fast reactor (GCFR) designs investigated in the PROTEUS reactor. The GCFR-PROTEUS experiments fill a gap in current integral benchmark data. These experiments can provide validation of computational models and nuclear data for next generation reactors.	Document	MSNE	FY2014
An Investigation To Establish Multiphysical Property Dataset Of Nuclear Materials Based On In-Situ Observations And Measurements	Purdue University	$800,000	Researchers will create an in-situ measurement based experimental approach to develop experimental validation dataset for NEAMS based code validation. Particular emphasis is on supplying data set for multiphysics simulations in extreme conditions as a function of material microstructure.	Document	NEAMS	FY2014
Experimental Validation of UO2 Microstructural Evolutions for NEAMS tool MARMOT	University of Florida	$798,000	Researchers will experimentally validate MARMOT for predicting the microstructural evolutions of UO2 oxide fuel under the driving forces of high temperatures and large temperature gradient in reactors. By performing the experiments and simulations simultaneously using precisely defined initial conditions, the experiment data will provide direct benchmarking of the MARMOT code.	Document	NEAMS	FY2014
High-resolution time-resolved experiments on mixing and entrainment of buoyant jets in stratified environments	University of Michigan	$799,983	Researchers will study high spatial and time-resolution experimental data of the fluid dynamics phenomena of flow jets interacting with a stratified layer. The issue plays an important role in the safety of several reactor designs, including sodium-cooled reactors. The data addresses the NEAMS needs for the validation of high fidelity computational fluid dynamics methodologies.	Document	NEAMS	FY2014
Fundamental study of key issues related to advanced S-CO2 Brayton Cycle: prototypic HX development and Cavitation	Georgia Institute of Technology	$799,000	Researchers will study scientific and operational issues pertinent to compact heat exchanger systems and turbo-machinery. The project will work to resolve issues with the fabrication of diffusion bonded compact heat exchangers, alternate heat exchange technology for recuperators, and resolution of issues with cavitation and fluid instabilities.	Document	RCRD&D	FY2014
Advanced Models for Nondestructive Evaluation of Aging Nuclear Power Plant Cables	Iowa State University	$787,291	Researchers will develop advanced models that relate environmentally induced microstructural and chemical changes in cable insulation polymers to their macroscopic electrical parameters. These parameters will be measured and modeled over a wide range of the electromagnetic spectrum, covering several potential nondestructive evaluation techniques, enabling identification of the most sensitive techniques for future development.	Document	RCRD&D	FY2014
Development of Novel Functionally Graded Transition Joints for Improving the Creep Strength of Dissimilar Metal Welds in Nuclear Applications	Lehigh University	$800,000	Researchers will develop graded transition joints and improved creep life models for increasing the life of dissimilar metal welds (DMWs) in nuclear reactors. The research represents the first application of functionally graded material concepts for solving the problem of DMW failures through an integrated approach of additive manufacturing, modeling, microstructural characterization, and advanced strain-sensing techniques.	Document	RCRD&D	FY2014
Feasibility Assessment of a Micro Modular Reactor (MMR)	North Carolina State University	$400,000	Researchers will develop an innovative compact reactor concept that integrates power production, power conversion and electricity generation in a single unit: the Micro Modular Reactor (MMR). It is designed to be absolutely melt-down proof (MDP) under all circumstances including complete loss of coolant scenarios with no possible release of radioactive material, to have a cycle length of greater than 10 years, and to be highly proliferation resistant.	Document	RCRD&D	FY2014
Scaling Studies for Advanced Gas Reactor Concepts	Oregon State University	$681,834	Researchers will expand the utilization of the Oregon State University High Temperature Test Facility (HTTF) to validate a broader range of advanced high temperature reactors and events. The facility will be revised to add a detailed scaling analysis of additional gas reactor concepts including advanced gas-cooled, molten salt, and sodium cooled reactors.	Document	RCRD&D	FY2014
Fluid Stratification Separate Effects Analysis, Testing and Benchmarking	Oregon State University	$800,000	Researchers will study fluid stratification in high temperature gas reactors. Coolant stratification is the result of incomplete mixing of one or more fluids, leading to a density gradient, which may or may not dissipate under diffusive or convective effects. This combined analytical and experimental project seeks to investigate stratification driven by diffusive and convective mechanisms and is expected to yield insight into this phenomenon.	Document	RCRD&D	FY2014
Probabilistic Economic Valuation of Safety Margin Management Analysis	Oregon State University	$795,364	Researchers will use RAVEN and develop a companion software package to facilitate economic analysis of safety margins. The project is a proof of concept that will use techniques to examine the cost of improving safety margins vs. the risk of accidents from not improving safety margins. This analysis can be used to evaluate the economic viability of various plant upgrades.	Document	RCRD&D	FY2014
Novel Dissimilar Joints Between Alloy 800H and 2.25%Cr and 1%Mo Steel	Pennsylvania State University	$800,000	Researchers will fabricate and test dissimilar metal joints between a nickel base alloy and a steel with gradual variations of chemical composition, microstructure and properties in a manner that reduces abrupt thermal expansion mismatch and the resulting residual stresses. Data on structure and properties will serve as valuable inputs for the initiation of an ASME code case.	Document	RCRD&D	FY2014
Multi-Phase Model Development to Assess RCIC System Capabilities under Severe Accident Conditions	Texas A&M University	$564,246	Researchers will develop physics-based models of the Reactor Core Isolation Cooling (RCIC) System and incorporating them into a multi-phase code for validation. The project will tackle the current major challenges in RCIC System analysis and enable evaluation of two-phase thermodynamic aspects.	Document	RCRD&D	FY2014
Experimental Investigation and CFD Analysis of Steam Ingress Accidents in HTGRs	The Ohio State University	$800,000	Researchers will study the steam ingress scenario for HTGRs. The study will investigate thermal-hydraulic behavior and graphite oxidation of stream ingress phenomena to validate predictive CFD models. This work will resolve concerns about possible steam generator tube ruptures in a HTGR He-Steam Rankine cycle.	Document	RCRD&D	FY2014
Coiled Tube Gas Heaters For Nuclear Gas-Brayton Power Conversion	University of California, Berkeley	$800,000	Researchers will develop heat exchangers for Brayton-cycle power conversion in reactors using sodium, NaK, or salt as intermediate coolants. The proposed coiled tube gas heaters (CTGHs) are expected to have excellent power density, thermal shock/creep, in-service inspection, and reparability characteristics.	Document	RCRD&D	FY2014
Fundamental Studies of Irradiation-Induced Modifications in Microstructural Evolution and Mechanical Properties of Advanced Alloys	University of Illinois, Urbana-Champaign	$800,000	Researchers will develop and test a mechanism for predicting neutron irradiation performance for optimized Grade 92 and Alloy 709 for applications in advanced reactor systems. The work will employ ion irradiations and available information from neutron irradiations of related alloys to develop a basis for predicting the neutron irradiation performance of the optimized alloys.	Document	RCRD&D	FY2014
Integrated Computational and Experimental Study of Radiation Damage Effects in Grade 92 Steel and Alloy 709	University of Tennessee	$800,000	Researchers will develop a mechanistic understanding and predictive models of irradiation-induced microstructural evolution and resulting mechanical properties in optimized ferritic-martensitic Grade 92 steel and austenitic alloy 709 using multiscale simulations coupled with rigorous experimental validation. The project will provide insights into the correlation between ion irradiation and fast neutron damage.	Document	RCRD&D	FY2014
Meta-Level Design Guidance and Operator Performance Measures for Hybrid Control Rooms	Vanderbilt University	$799,869	Researchers will apply human factors engineering methods and relevant expertise from non-nuclear high-risk high-consequence domains toward the measurement of operator performance in analog, digital, and hybrid main control rooms. Performance measures will be developed for evaluating the situation awareness and decision-making proficiencies to support the transition to digital or hybrid control room displays.	Document	RCRD&D	FY2014

FY 2019 Research and Development Awards

DOE is awarding more than $28.5 million through its Nuclear Energy University Program (NEUP) to support 40 university-led nuclear energy research and development projects in 23 states. NEUP seeks to maintain U.S. leadership in nuclear research across the country by providing top science and engineering faculty and their students with opportunities to develop innovative technologies and solutions for civil nuclear capabilities.

A complete list of R&D projects with their associated abstracts is available below.

Title	Institution	Estimated Funding*	Project Description	Abstract	Project Type	Fiscal Year
Neutron Damage and MAX Phase Ternary Compounds	Drexel University			Document	IIR	FY2009
Atomistic Calculations of the Effect of Minor Actinides on Thermodynamic and Kinetic Properties of UO2+x	Georgia Institute of Technology			Document	IIR	FY2009
Maximum Fuel Utilization in Fast Reactors without Chemical Reprocessing	University of California, Berkeley			Document	IIR	FY2009
Developing a High Thermal Conductivity Fuel with Silicon Carbide Additives	University of Florida			Document	IIR	FY2009
Fabrication of Tungsten-Rhenium Cladding Materials via Spark Plasma Sintering for Ultra High Temperature Reactor Applications	University of Idaho			Document	IIR	FY2009
Ionic Liquid and Supercritical Fluid Hyphenated Techniques for Dissolution and Separation of Lanthanides, Actinides, and Fission Products	University of Idaho			Document	IIR	FY2009
Improved Fission Neutron Data Base for Active Interrogation of Actinides	University of Michigan			Document	IIR	FY2009
Utilization of Methacrylates and Polymer Matrices for the Synthesis of Ion Specific Resins	University of Nevada, Las Vegas			Document	IIR	FY2009
Improved LWR Cladding Performance by EPD Surface Modification Technique	University of Wisconsin, Madison			Document	IIR	FY2009
Advanced Models of LWR Pressure Vessel Embrittlement for Low Flux-High Fluence Conditions	University of California, Santa Barbara			Document	LWRS	FY2009
Irradiation Creep in Graphite	Boise State University			Document	NGNP	FY2009
Modeling the Stress Strain Relationships and Predicting Failure Probabilities For Graphite Core Components	Cleveland State University			Document	NGNP	FY2009
TRISO-Coated Fuel Durability Under Extreme Conditions	Colorado School of Mines			Document	NGNP	FY2009
An Innovative and Advanced Coupled Neutron Transport and Thermal Hydraulic Method (Tool) for the Design, Analysis and Optimization of VHTR/NGNP Prismatic Reactors	Georgia Institute of Technology			Document	NGNP	FY2009
Removal of 14C from Irradiated Graphite for Graphite Recycle and Waste Volume Reduction	Idaho State University			Document	NGNP	FY2009
Millimeter-Wave Thermal Analysis Development and Application to Gen IV Reactor Materials	Massachusetts Institute of Technology			Document	NGNP	FY2009
Accurate Development of Thermal Neutron Scattering Cross Section Libraries	North Carolina State University			Document	NGNP	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
Understanding Creep Mechanisms in Graphite with Experiments, Multiscale Simulations, and Modeling	North Carolina State University			Document	NGNP	FY2009
Simulations of the Thermodynamic and Diffusion Properties of Actinide Oxide Fuel Materials	University of Michigan			Document	AFCI	FY2009
Verification & Validation of High-Order Short-Characteristics-Based Deterministic Transport Methodology on Unstructured Grids	North Carolina State University			Document	NGNP	FY2009
Adsorptive Separation and Sequestration of Krypton, I and C14 on Diamond Nanoparticles	University of Missouri, Columbia			Document	AFCI	FY2009
Microscale Heat Conduction Models and Doppler Feedback	North Carolina State University			Document	NGNP	FY2009
Fundamental Understanding of Ambient and High-Temperature Plasticity Phenomena in Structural Materials in Advanced Reactors	Georgia Institute of Technology			Document	AFCI	FY2009
Development of Alternative Technetium Waste Forms	University of Nevada, Las Vegas			Document	AFCI	FY2009
Optimizing Neutron Thermal Scattering Effects in Very High Temperature Reactors	North Carolina State University			Document	NGNP	FY2009
Advanced Elastic/Inelastic Nuclear Data Development Project	Idaho State University			Document	AFCI	FY2009
Heterogeneous Recycling in Fast Reactors	Massachusetts Institute of Technology			Document	AFCI	FY2009
Quantification of UV-Visible and Laser Spectroscopic Techniques for Materials Accountability and Process Control	University of Nevada, Las Vegas			Document	AFCI	FY2009
Multiaxial Creep-Fatigue and CreepRatcheting Failures of Grade 91 and Haynes 230 Alloys Toward Addressing Design Issues of Gen IV Nuclear Power Plants	North Carolina State University			Document	NGNP	FY2009
Thermodynamic Development of Corrosion Rate Modeling in Iron Phosphate Glasses	Missouri University of Science and Technology			Document	AFCI	FY2009
Development of Subspace-Based Hybrid Monte Carlo-Deterministic Algorithms for Reactor Physics Calculations	North Carolina State University			Document	AFCI	FY2009
High-Fidelity Space-Time Adaptive Multiphysics Simulations in Nuclear Engineering	University of Nevada, Reno			Document	AFCI	FY2009
Improvements to Nuclear Data and Its Uncertainties by Theoretical Modeling	Rensselaer Polytechnic Institute			Document	AFCI	FY2009
Investigation of Countercurrent Helium-air Flows in Air-ingress Accidents for VHTRs	Ohio State University			Document	NGNP	FY2009
Sharp Interface Tracking in Rotating Microflows of Solvent Extraction	State University of New York at Stony Brook			Document	AFCI	FY2009
Bulk Nanostructured FCC Steels with Enhanced Radiation Tolerance	Texas A&M University			Document	AFCI	FY2009
Simulations of Failure via Three-Dimensional Cracking in Fuel Cladding for Advanced Nuclear Fuels	University of Texas, Dallas			Document	AFCI	FY2009
Testing of Performance of Optical Fibers Under Irradiation in Intense Radiation Fields, When Subjected to Very High Temperatures	Ohio State University			Document	NGNP	FY2009
Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels	Texas A&M University			Document	AFCI	FY2009
SiC Schottky Diode Detectors for Measurement of Actinide Concentrations from Alpha Activities in Molten Salt Electrolyte	The Ohio State University			Document	AFCI	FY2009
Computational Design of Advanced Nuclear Fuels	University of California, Davis			Document	AFCI	FY2009
Advanced Mesh-Enabled Monte Carlo Capability for Multi-Physics Reactor Analysis	University of Wisconsin, Madison			Document	AFCI	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
A Distributed Fiber Optic Sensor Network for Online 3-D Temperature and Neutron Fluence Mapping in a VHTR Environment	Texas A&M University			Document	NGNP	FY2009
Ab Initio Enhanced Calphad Modeling of Actinide Rich Nuclear Fuels	University of Wisconsin, Madison			Document	AFCI	FY2009
Investigation on the Core Bypass Flow in a Very High Temperature Reactor	Texas A&M University			Document	NGNP	FY2009
Development of Diffusion Barrier Coatings and Deposition Technologies for Mitigating Fuel Cladding Chemical Interactions (FCCI)	University of Wisconsin, Madison			Document	AFCI	FY2009
CFD Model Development and Validation for High Temperature Gas Cooled Reactor Cavity Cooling System (RCCS) Applications	Texas A&M University			Document	NGNP	FY2009
Thermal Properties of LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin, Madison			Document	AFCI	FY2009
Study of Air ingress across the duct during the accident conditions	Texas A&M University			Document	NGNP	FY2009
Verification of the CENTRM Module for Adaptation of the SCALE Code to NGNP Prismatic and PBR Core Designs	University of Arizona			Document	NGNP	FY2009
Integral and Separate Effects Tests for Thermal Hydraulics Code Validation for Liquid-Salt Cooled Nuclear Reactors	University of California, Berkeley			Document	NGNP	FY2009
Mechanisms Governing the Creep Behavior of High Temperature Alloys for Generation IV Nuclear Energy Systems	University of Cincinnati			Document	NGNP	FY2009
ALD Produced B2O3, Al2O3 and TiO2 Coatings on Gd2O3 Burnable Poison Nanoparticles	University of Colorado, Boulder			Document	NGNP	FY2009
Experimental Study and Computational Simulations of Key Pebble Bed Thermomechanics Issues for Design and Safety	University of Idaho			Document	NGNP	FY2009
Prediction and Monitoring Systems of Creep-Fracture Behavior of 9Cr-1Mo Steels for Reactor Pressure Vessels	University of Idaho			Document	NGNP	FY2009
Understanding Fundamental Material Degradation Processes in High Temperature Aggressive Chemomechanical Environments	University of Illinois, Urbana-Champaign			Document	NGNP	FY2009
Multi-Scale Multi-physics Methods Development for the Calculation of Hot-Spots in the NGNP	University of Michigan			Document	NGNP	FY2009
Corrosion and Creep of Candidate Alloys in High Temperature Helium and Steam Environments for the NGNP	University of Michigan			Document	NGNP	FY2009
Creation of a Full-Core HTR Benchmark with the Fort St. Vrain Initial Core and Validation of the DHF Method with Helios for NGNP Configurations	University of Michigan			Document	NGNP	FY2009
Fission Product Sorptivity in Graphite	University of Missouri, Columbia			Document	NGNP	FY2009
Identifying and Understanding Environment-Induced Crack Propagation Behavior in Ni-Based Superalloy INCONEL 617	University of Nevada, Las Vegas			Document	NGNP	FY2009
Graphite Oxidation Simulation in HTR Accident Conditions	University of New Mexico			Document	NGNP	FY2009
Non Destructive Thermal Analysis and In Situ Investigation of Creep Mechanism of Graphite and Ceramic Composites using Phase-sensitive THz Imaging & Nonlinear Resonant Ultrasonic Spectroscopy	University of Rochester			Document	NGNP	FY2009
Tritium Sequestration in Gen IV NGNP Gas Stream via Proton Conducting Ceramic Pumps	University of South Carolina			Document	NGNP	FY2009
Materials, Turbomachinery and Heat Exchangers for Supercritical CO2 Systems	University of Wisconsin, Madison			Document	NGNP	FY2009
Experimental Studies of NGNP Reactor Cavity Cooling System with Water	University of Wisconsin, Madison			Document	NGNP	FY2009
Assessment of Embrittlement of VHTR Structural Alloys in Impure Helium Environments	University of Wisconsin, Madison			Document	NGNP	FY2009
Modeling Fission Product Sorption in Graphite Structures	University of Wisconsin, Madison			Document	NGNP	FY2009
Liquid Salt Heat Exchanger Technology for VHTR Based Applications	University of Wisconsin, Madison			Document	NGNP	FY2009
Effect of Post-Weld Heat Treatment on Creep Rupture Properties of Grade 91 Steel Heavy Section Welds	Utah State University			Document	NGNP	FY2009
Alpha Radiolysis of Nuclear Solvent Extraction Ligands used for An(III) and Ln(III) Separations	California State University, Long Beach	$1,390,252		Document	FCR&D	FY2010
Predictive Maturity of Multi-Scale Simulation Models for Fuel Performance	Clemson University	$614,690		Document	FCR&D	FY2010
Freeze-casting as a Novel Manufacturing Process for Fast Reactor Fuels	Drexel University	$1,149,327		Document	FCR&D	FY2010
Fuel Performance Experiments on the Atomistic Level, Studying Fuel Through Engineered Single Crystal UO2	Idaho State University	$650,000		Document	FCR&D	FY2010
Development of A Self Biased High Efficiency Solid-State Neutron Detector for MPACT Applications	Rensselaer Polytechnic Institute	$810,141		Document	FCR&D	FY2010
Development of a Innovative High Thermal Conductivity UO 2 Ceramic Composites Fuel Pellets with Carbon Nano-Tubes Using Spark Plasma Sintering	University of Florida	$894,042		Document	FCR&D	FY2010
Exploration and Modeling of Structural Changes in Waste Glass under Corrosion	Pennsylvania State University	$1,377,444		Document	FCR&D	FY2010
Evaluation of materials for interim storage of spent fuel for more than 100 years	University of Michigan	$931,603		Document	FCR&D	FY2010
Implementation of On-the-Fly Doppler Broadening in MCNP5 for Multiphysics Simulation of Nuclear Reactors	University of Michigan	$406,712		Document	FCR&D	FY2010
Methods and tools to allow molecular flow simulations to be coupled to higher level continuum descriptions of flows in porous/fractured media and aerosol/dust dynamics	University of Missouri-Columbi	$541,286		Document	FCR&D	FY2010
Characterization and Modeling of Materials for Kr-Xe Separations	University of Nevada-Las Vegas	$989,800		Document	FCR&D	FY2010
Modeling Solute Thermokinetics in LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin-Madison	$616,073		Document	FCR&D	FY2010
Advanced Aqueous Separation Systems for Actinide Partitioning: Develop Fundamental Understanding of An(III)/Ln(III) Separation	Washington State University	$1,451,784		Document	FCR&D	FY2010
Consistent Multigroup Theory Enabling Accurate Coarse-Group Simulation of GenIV Reactors	Georgia Institute of Technology	$1,046,277		Document	GEN IV	FY2010
Studies of Deteriorated Heat Transfer in Prismatic Cores Stemming from Irradiation-Induced Geometry Distortion	Idaho State University	$1,287,921		Document	GEN IV	FY2010
Carbide Coatings for Nickel Alloys, Graphite, and Carbon/Carbon Composites to be Used in Fluoride Salt Valves	Johns Hopkins University	$1,183,239		Document	GEN IV	FY2010
Design, Testing, and Modeling of the Direct Reactor Auxiliary Cooling System for AHTRs	Ohio State University	$1,366,627		Document	GEN IV	FY2010
Monitoring microstructural evolution of Alloy 617 with nonlinear acoustics for remaining useful life prediction; multiaxial creep-fatigue and creep-ratcheting	Pennsylvania State University	$1,000,000		Document	GEN IV	FY2010
Development and Validation of Multidimensional Models of Supercritical CO 2 Energy Conversion Systems for Nuclear Power Reactors	Rensselaer Polytechnic Institute	$475,005		Document	GEN IV	FY2010
Multiscale Concrete Modeling for Aging Degradation	Mississippi State University	$345,941		Document	LWRS	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term and Elevated Temperature Irradiation: Modeling and Experimental Investigation	University of California-Berkeley	$1,320,667		Document	GEN IV	FY2010
Development of an advanced computational fluid dynamics technology for the next-generation nuclear reactor system analysis and safety margin characterization code	North Carolina State University	$418,199		Document	LWRS	FY2010
Development of Barrier Layers for the Protection of Candidate Alloys in the VHTR	University of California-Santa Barbara	$995,232		Document	GEN IV	FY2010
Precursor Derived Nanostructured Si-C-X Materials for Nuclear Applications	University of Washington	$899,518		Document	MRIIR	FY2010
Investigation of a Novel NDE Method for Monitoring Thermo-Mechanical Damage and Microstructure Evolution in Ferritic-Martensitic Steels for Generation IV Nuclear Energy Systems	University of Cincinnati	$833,109		Document	GEN IV	FY2010
Development and Testing of an Open-Loop Oscillator for Small Reactivity Worth Samples	Idaho State University	$597,252		Document	MRIIR	FY2010
Fission Product Transport in TRISO Particle Layers under Operating and Off-Normal Conditions	University of Michigan	$966,581		Document	GEN IV	FY2010
Understanding the Irradiation Behavior of Zirconium Carbide	Pennsylvania State University	$870,613		Document	MRIIR	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term Irradiation at Elevated Temperature: Critical Experiments	University of Michigan	$1,181,379		Document	GEN IV	FY2010
Modeling investigation of the stability and irradiation-induced evolution of nanoscale precipitates in advanced structural materials	University of Tennessee-Knoxville	$380,653		Document	MRIIR	FY2010
Three-dimensional NDE of VHTR Core Components via Simulation-based Testing	University of Minnesota	$1,366,163		Document	GEN IV	FY2010
Investigation of Laser Shock Peening for Enhancing Fatigue and Stress Corrosion Cracking Resistance of Nuclear Energy Materials	University of Cincinnati	$1,242,019		Document	MRIIR	FY2010
Failure Predictions for VHTR Core Components using a Probabilistic Continuum Damage Mechanics Model	University of Minnesota	$854,542		Document	GEN IV	FY2010
Irradiation Accelerated Corrosion of Reactor Core Materials	University of Michigan	$798,943		Document	MRIIR	FY2010
Development of a Scanning Microscale Fast Neutron Irradiation Platform for Examining the Correlation Between Local Neutron Damage and Graphite Microstructure	University of Missouri-Columbia	$703,064		Document	GEN IV	FY2010
Study of Interfacial Interactions using Thin Film Surface Modification: Radiation and Oxidation Effects in Materials	University of Wisconsin-Madison	$538,032		Document	MRIIR	FY2010
Development of Thermal Transient Flow Rate Sensors for High Temperature, Irradiation, Corrosive Environment	University of Nevada-Las Vegas	$451,269		Document	GEN IV	FY2010
Novel Engineered Refractory Materials for Advanced Reactor Applications	North Carolina State University	$1,129,304		Document	MRIIR	FY2010
Novel Methods of Tritium Sequestration: High Temperature Gettering and Separation Membrane Materials Discovery for Nuclear Energy Systems	University of South Carolina	$1,366,626		Document	GEN IV	FY2010
Heat Transfer Salts for Nuclear Reactor Systems - Chemistry Control, Corrosion Mitigation, and Modeling	University of Wisconsin-Madison	$1,352,040		Document	GEN IV	FY2010
Pulsed Magnetic Welding for Advanced Core and Cladding Steels	University of Wisconsin-Madison	$525,206		Document	GEN IV	FY2010
Corrosion in Supercritical Carbon Dioxide: Materials, Environmental Purity, Surface Treatments, and Flow Issues	University of Wisconsin-Madison	$651,447		Document	GEN IV	FY2010
Quantification of Cation Sorption to Engineered Barrier Materials Under Extreme Conditions	Clemson University	$1,171,380		Document	FCR&D	FY2011
In-Pile Instrumentation Multi-Parameter System Utilizing Photonic Fibers and Nanovision	Idaho State University	$1,199,990		Document	FCR&D	FY2011
Development of Plasmonically Cloaked Nanoparticles	Idaho State University	$800,000		Document	FCR&D	FY2011
Fission Product Transmutation in Mixed Radiation Fields	Idaho State University	$800,000		Document	FCR&D	FY2011
Life Prediction of Spent Fuel Storage Canister Material	Massachusetts Institute of Technology	$899,826		Document	FCR&D	FY2011
Active Interrogation using Photofission Technique for Nuclear Materials Control and Accountability	Oregon State University	$900,000		Document	FCR&D	FY2011
Anisotropic Azimuthal Power and Temperature Distribution on Fuel Rod: Impact of Hydride Distribution	Pennsylvania State University	$631,956		Document	FCR&D	FY2011
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$1,000,000		Document	FCR&D	FY2011
Recovery of Uranium from Seawater: Preparation and Development of Polymer-Supported Extractants	City College of New York, Hunter	$363,716		Document	MSTR	FY2011
Microemulsions and Aggregation Formation in Extraction Processes for Used Nuclear Fuel: Thermodynamics and Structural Studies	University of California, Irvine	$1,000,000		Document	FCR&D	FY2011
One-Dimensional Nanostructures for Neutron Detection	North Carolina State University	$455,629		Document	MSTR	FY2011
Optimized Processing Fabrication Paths for Larger Heats of Nanostructured Ferritic Alloys	University of California, Santa Barbara	$1,000,000		Document	FCR&D	FY2011
Feasibility and Safety Assessment for Advanced Reactor Concepts Using Vented Fuel	Oregon State University	$600,000		Document	MSTR	FY2011
Basic Physics Data: Measurement of Neutron Multiplicity from Induced Fission	University of Michigan	$973,364		Document	FCR&D	FY2011
Development of an Efficient Meso-Scale Multi-Phase Flow Solver in Nuclear Applications	City College of New York	$505,858		Document	NEAMS	FY2011
High Temperature Transducers for Online Monitoring of Microstructure Evolution	Pennsylvania State University	$455,628		Document	MSTR	FY2011
Radionuclide Incorporation and Long Term Performance of Apatite Waste Forms	University of Michigan	$862,500		Document	FCR&D	FY2011
Multiscale Modeling and Uncertainty Quantification for Nuclear Fuel Performance	Colorado State University	$1,098,250		Document	NEAMS	FY2011
Laser-Arc Hybrid Welding of Thick Section Ni-base Alloys- Advanced Modeling and Experiments	Pennsylvania State University	$536,117		Document	MSTR	FY2011
Actinide Foil Production for MPACT Research	University of Nevada-Las Vegas	$156,897		Document	FCR&D	FY2011
Fundamental Studies of the Role of Grain Boundaries on Uniform Corrosion of Advanced Nuclear Reactor Materials	Drexel University	$1,098,250		Document	NEAMS	FY2011
Correlates of Sensitive Technologies	Texas A&M University	$509,467		Document	MSTR	FY2011
Enriched Boron-Doped Amorphous Selenium Based Position-Sensitive Solid-State Thermal Neutron Detector for MPACT Applications	University of South Carolina	$1,000,000		Document	FCR&D	FY2011
Phenomena-based Uncertainty Quantification in Predictive Coupled-Physics Reactor Simulations	Texas A&M University	$1,098,250		Document	NEAMS	FY2011
Improved Safety Margin Characterization of Risk from Loss of Offsite Power	Texas A&M University	$600,000		Document	MSTR	FY2011
Development of Advanced High Uranium Density Fuels for Light Water Reactors	University of Wisconsin-Madison	$1,000,000		Document	FCR&D	FY2011
Characterization of Modeling of Grain Boundary Chemistry Evolution in Ferritic Steels Under Irradiation	University of Michigan	$1,098,250		Document	NEAMS	FY2011
Diffusion, Thermal Properties and chemical Compatibilities of Select MAX Phases with Materials for Advanced Nuclear Systems	Drexel University	$535,927		Document	NEET	FY2011
A High Temperature-Tolerant and Radiation-Resistant In-Core Neutron Sensor for Advanced Reactors	The Ohio State University	$455,629		Document	MSTR	FY2011
Developing the User Experience for a Next Generation Nuclear Fuel Cycle Simulator	University of Wisconsin-Madison	$1,200,000		Document	FCR&D	FY2011
Development of Multiscale Materials Modeling Techniques and Coarse-Graining Strategies for Predicting Materials Degradation in Extreme Irradiation Environments	University of Tennessee, Knoxville	$750,000		Document	NEAMS	FY2011
A New Light Weight Structural Material for Nuclear Structures	North Carolina State University	$399,490		Document	NEET	FY2011
Pathway Aggregation in the Risk Assessment of Proliferation Resistance and Physical Protection (PR&PP) of Nuclear Energy Systems	The Ohio State University	$534,471		Document	MSTR	FY2011
Experimental Investigation of Convection and Heat Transfer in the Reactor Core for a VHTR	City College of New York	$1,118,856		Document	RCRD&D	FY2011
Preparation of High Purity, High Molecular-Weight Chitin from Ionic Liquids for Use as an Adsorbate for the Extraction of Uranium from Seawater	University of Alabama	$338,260		Document	MSTR	FY2011
Graphite Microstructural Characterization Using Time-Domain and Correlation-Based Ultrasonics	Johns Hopkins University	$1,199,997		Document	RCRD&D	FY2011
Selectivity in Ligand Binding to Uranyl Compounds: A Synthetic, Structural, Thermodynamic and Computational Study	University of California-Berkeley	$500,000		Document	MSTR	FY2011
Methodology Development for Passive Component Reliability Modeling in a Multi-Physics Simulation Environment	The Ohio State University	$533,457		Document	RCRD&D	FY2011
Development of Seismic Isolation Systems Using Periodic Materials	University of Houston	$538,154		Document	MSTR	FY2011
Pebble Fuel Handling and Reactivity Control for Salt-Cooled High Temperature Reactors	University of California, Berkeley	$612,721		Document	RCRD&D	FY2011
Innovative Elution Processes for Recovering Uranium from Seawater	University of Idaho	$400,000		Document	MSTR	FY2011
Self-Sustaining Thorium Boiling Water Reactors	University of California, Berkeley	$1,145,932		Document	RCRD&D	FY2011
Development of Austenitic ODS Strengthened Alloys for Very High Temperature Applications	University of Illinois-Urbana Champaign	$538,154		Document	MSTR	FY2011
High Fluency Low Flux Embrittlement Models of LWR Reactor Pressure Vessel Embrittlement and a Supporting Database from the UCSB ATR-2 Irradiation Experiment	University of California, Santa Barbara	$1,199,607		Document	RCRD&D	FY2011
Enhancement of the Extraction of the Uranium from Seawater	University of Maryland	$400,000		Document	MSTR	FY2011
A Research Program for Fission Product/Dust Transport in HTGR's	University of Missouri-Columbia	$1,157,367		Document	RCRD&D	FY2011
Transient Safety Analysis of Fast Spectrum TRU Burning LWR with Internal Blankets	University of Michigan	$599,475		Document	MSTR	FY2011
Development and Validation of a Lifecycle-based Prognostics Architecture with Test Bed Validation	University of Tennessee, Knoxville	$846,315		Document	RCRD&D	FY2011
Development of Novel Sorbents for Uranium Extraction from Seawater	University of North Carolina, Chapel Hill	$400,000		Document	MSTR	FY2011
In-situ Condition Monitoring of Components in Small Modular Reactors Using Process and Electrical Signature Analysis	University of Tennessee, Knoxville	$650,000		Document	RCRD&D	FY2011
Radiation Behavior of High-Entropy Alloys for Advanced Reactors	University of Tennessee, Knoxville	$538,159		Document	MSTR	FY2011
Technical Development for S-CO2 Advanced Energy Conversion	University of Wisconsin	$815,000		Document	RCRD&D	FY2011
Rapid Computer Aided Ligand Design and Screening of Precious Metal Extractants from TRUEX Raffinate with Experimental Validation	Washington State University	$500,000		Document	MSTR	FY2011
Ag Transport Through Non-Irradiated and Irradiated SiC	University of Wisconsin-Madison	$1,055,456		Document	RCRD&D	FY2011
Critical Heat Flux Phenomena at High Pressure and Low Mass Fluxes: Tests and Models	University of Wisconsin-Madison	$1,199,781		Document	RCRD&D	FY2011
Modeling and Test Validation of a Reactor Cavity Cooling System with Air	University of Wisconsin-Madison	$1,199,988		Document	RCRD&D	FY2011
Transient Mixed Convection Validation for NGNP	Utah State University	$635,860		Document	RCRD&D	FY2011
Alternative High-Performance Ceramic Waste Forms	Alfred University	$840,000	This project aims to advance fundamental understanding of the kinetics of structural evolution of crystalline ceramic waste forms. The structure/property relationships will be identified and will reveal new formulations, improved processing routes, and strategies for improved performance or ceramic waste forms.	Document	FCR&D	FY2012
Surface Layer Bulk Glass Interface Evolution with Aqueous Corrosion	Alfred University	$880,000	This project will investigate the links between the morphology, structure and chemistry of surface layer-bulk glass interface and the long-term corrosion-reaction kinetics using in-situ and ex-situ experiments. The understanding will result in improved models for long-term predictive behavior of high-level-waste (HLW) glasses under repository conditions.	Document	FCR&D	FY2012
Improved Accident Tolerance of Austenitic Stainless Steel Cladding through Colossal Supersaturation with Interstitial Solutes	Case Western Reserve University	$850,000	This project aims to develop new case-hardened austenitic stainless steels by saturating them with materials that improve their mechanical properties, corrosion resistance and radiation resistance. This project, if successful, will result in safer, longer-lasting, and more accident tolerant fuel claddings.	Document	FCR&D	FY2012
Optimization of Deep Borehole Systems for HLW Disposal	Massachusetts Institute of Technology	$850,000	Researchers aim to carry out a comprehensive evaluation of the deep borehole option for disposal of used nuclear fuel and high livel waste. The models developed will predict potential movement of water through natural and engineered barriers and release of radionuclides to the biosphere which will aide in site selection.	Document	FCR&D	FY2012
Scholarship for Nuclear Communications and Methods for Evaluation of Nuclear Project Acceptability	Massachusetts Institute of Technology	$800,000	Researchers will work to develop a model to characterize the factors affecting social acceptance of nuclear projects with potential stakeholders. The resultant model will strengthen the ability to design and implement large projects more efficiently, leading to higher rates of success of future nuclear projects.	Document	FCR&D	FY2012
Accurate Holdup Calculations with Predictive Modeling and Data Integration	North Carolina State University	$875,000	Researchers will develop and use state-of-the-art radiation transport codes to account accurately for the fissile material in a nuclear materials processing facility. An accurate estimation of the materials will allow for ensured radiological safety, security, waste management and efficient plant operation.	Document	FCR&D	FY2012
Novel Metal Sulfides to Achieve Effective Capture and Durable Consolidation of Radionuclides	Northwestern University	$760,000	Researchers will evaluate the effectiveness of chalcogenide based materials design novel metal sulfides to effectively capture and store of radioisotopes released during reprocessing of used nuclear fuel. This project will focus on understanding structure-property relationships to enable refined and direct synthesis approaches for improved and cost-efficient nuclear waste forms.	Document	FCR&D	FY2012
Nonlinear Ultrasonic Diagnosis and Prognosis of ASR Damage in Dry Cask Storage	Northwestern University	$885,000	Researchers aim to use nondestructive damage characterization methods to detect, manage and mitigate the degradation/damage mechanisms of dry cask storage systems for nuclear fuels. This project, if successful, will provide tools that will allow the prediction of the reliability and the safety of concrete structures in dry cask storage systems.	Document	FCR&D	FY2012
Prototype Demonstration of Gamma-Blind Tensioned Metastable Fluid Neutron/Multiplicity/Alpha Detector- Real Time Methods for Advanced Fuel Cycle Applications	Texas A&M University	$875,000	This project aims to create a prototype demonstration of a novel neutron/alpha detector based on a technology that is blind to gamma field used fuel. The prototype, if successful, will enhance instrumentation for monitoring real-time material balance during various stages of the nuclear cycle.	Document	FCR&D	FY2012
Testing of Sapphire Optical Fiber and Sensors in Intense Radiation Fields, when Subjected to Very High Temperatures	The Ohio State University	$885,000	The researchers on this project will investigate the performance of sapphire optical fibers and sensors in reactor environments. The project, if successful, will result in improved instrumentation to understand the behavior and predict performance of nuclear fuel systems at the microstructural level.	Document	FCR&D	FY2012
Concrete Materials with Ultra-High Damage Resistance and Self-Sensing Capacity for Extended Nuclear Fuel Storage Systems	University of California, Irvine	$800,000	Researchers aim to design a new class of multifunctional concrete materials. This project, if successful, will result in a novel multifunctional concrete material that possesses inherent degradation monitoring capability and is suitable for an extended storage system for the used nuclear fuel.	Document	FCR&D	FY2012
Development of Innovative Accident Tolerant High Thermal Conductivity UO2 Fuel Pellets with a Diamond Dopant	University of Florida	$800,000	Researchers will evaluate the use of diamond nanoparticles composite material in innovative accident tolerant fuel pellets. This could significantly improve both the thermal conductivity of fuel pellets and light water reactors' efficiency safety.	Document	FCR&D	FY2012
Probabilistic Multi-Hazard Assessment of Dry Cask Structures	University of Houston	$865,000	This project aims to investigate the performance of dry cask storage systems under multiple hazard systems (earthquake, tornados, combined with aging effects) using a probabilistic multi-hazard framework. This framework will be validated based on experimental research and will provide improved models for safety and reliability of spent nuclear fuels during storage and transportation.	Document	FCR&D	FY2012
Measurement of Irradiated Pyroprocessing Samples via Laser Induced Breakdown Spectroscopy	University of Idaho	$820,000	This project aims to use advanced characterization techniques to investigate microstructural changes and the micromechanisms related to irradiation induced damage in used nuclear fuels and waste forms. This project, if successful, will result in enhanced models to predict the structural and chemical response of used fuel and waster forms during interim storage and permanent disposal.	Document	FCR&D	FY2012
Elastic/Inelastic Measurement Project	University of Kentucky	$880,523	Researchers will measure nuclear data for elastic/inelastic scattered neutrons on coolants and structural materials. The data generated, will be useful for future R&D programs that will study innovative next generation LWR and future fast systems.	Document	FCR&D	FY2012
Electrochemical Corrosion Studies for Modeling Metallic Waste Form Release Rates	University of Nevada- Las Vegas	$790,000	This project aims to use advanced electrochemical methods to investigate the corrosion related degradation of metal alloys used for housing fission products. The data obtained from this study will allow for the prediction of the long-term behavior of the metallic host phase materials over geological time-scales.	Document	FCR&D	FY2012
Thermodynamic and Microstructural Mechanisms in the Corrosion of Advanced Ceramic Tc-bearing Waste Forms and Thermophysical Properties	University of Nevada- Las Vegas	$795,000	This project team will harvest thermodynamic and microstructural data on the evolution of ceramic based waste forms. The data will be used to advance the current state-of-the-art methodology used for isolation and stabilization of fission products and improve on nuclear fuel recycling processes.	Document	FCR&D	FY2012
Development and Experimental Benchmark of Simulations to Predict Used Nuclear Fuel Cladding Temperatures during Drying and Transfer Operations	University of Nevada- Reno	$745,000	Researchers will conduct experiments to investigate and develop advanced computational models of heat transfer in post-pool-storage drying operations. This project, if successful, will result in tools that can be used to design efficient drying processes to as to ensure suitability for dry-cask systems for long-term storage and transport.	Document	FCR&D	FY2012
Better Radiation Response and Accident Tolerance of Nanostructured Ceramic Fuel Materials?	University of Tennessee	$815,000	Researchers will use novel experimental methods to investigate the links between microstructure, phase stability and damage evolution in nanostructured ceramic fuel materials. The project will study fuel materials at temperatures and irradiation conditions relevant to operation and accidental scenarios.	Document	FCR&D	FY2012
Radiation and Thermal Effects on Used Nuclear Fuel and Nuclear Waste Forms	University of Tennesssee	$770,000	This project aims to investigate the structural and chemical response of used nuclear fuel and waste forms during interim storage and permanent disposal. If successful, this project will generate models that will allow the prediction of structural evolution and hence the radiological safety and security of nuclear fuel and waste forms.	Document	FCR&D	FY2012
Seismic Performance of Dry Casks Storage for Long-Term Exposure	University of Utah	$873,319	Researchers will evaluate the mechanical performance of dry-cask storage under seismic loading for mid-term operational periods. Simulations will include scenarios for freestanding, anchored, and vaulted casks. The experimental tests will also evaluate the dynamic seismic response of freestanding and anchored dry-cask storage prototypes, providing recommendations for optimal Interim Spent Fuel Storage Installations (ISFSIs) design.	Document	FCR&D	FY2012
Validation Experiments for Spent-Fuel Dry-Cask In-Basket Convection	Utah State University	$690,000	Researchers in this project aim to conduct experiments that generate data on natural convection through a fuel assembly. The data will be used to validate the computational models being developed for nuclear safety and design.	Document	FCR&D	FY2012
Re-Branding the Nuclear Fuel Cycle	Virginia Commonwealth University	$850,000	This project will create a comprehensive framework for the evaluation of alternative fuel cycle systems that will be used to identify and analyze key elements related to long-term management of nuclear fuels , with the ultimate goal to develop a communications strategy to reach stakeholders.	Document	FCR&D	FY2012
Advanced Characterization of Molecular Interactions in TALSPEAK-like Separations Systems	Washington State University	$875,000	Researchers will use advanced characterization techniques (experimental and computational) to improve understanding of the molecular level processes/interactions during separation processes for advanced fuel cycles. The understanding of these interactions will be used to develop more robust and streamlined separation processes for advanced fuel cycles.	Document	FCR&D	FY2012
Coupling of Nuclear Waste Form Corrosion and Radionuclide Transport in Presence of Relevant Repository Sediments	Washington State University	$885,000	Researchers will conduct experiments to understand the mechanisms responsible for the corrosion of nuclear waste forms in realistic chemical environments. The data generated from these experiments will enable increased reliability of the models used to predict the waste form performance in repository environments.	Document	FCR&D	FY2012
Stationary Liquid Fuel Fast Reactor (SLFFR) Concept for TRU Burning	Purdue University	$450,000	Reasearchers will investigate a new type of molten metallic fuel reactor concept that will consume hazardous transuranic waste. The liquid fuel alloy has several advantages over solid fuel fast reactors that are used for the same purpose.	Document	MSTR	FY2012
ABR for TRU Transmutation with Breed & Burn Thorium Blanket for Improved Economics and Resource Utilization	University of California- Berkeley	$450,000	The research team will use detailed neutronic analysis for a new Advanced Burner Reactor concept with low conversion ratio. The concept will use a new core shape to improve the utilization of neutrons to perform breed and burn.	Document	MSTR	FY2012
New Materials for High Temperature Thermoelecric Power Generation	University of California, Davis	$450,000	Reasearchers will work to develop nanostructured and other new materials to support the development of higher efficiency thermoelectric devices. These devices convert thermal energy to electricity with no moving parts. The new materials will operate at higher efficiencies and over a wider temperature range than those currently available--an important quality for future nuclear-powered deep space exploration.	Document	MSTR	FY2012
Microscopic Fuel Particles Produced by Self-Assembly of Actinide Nanoclusters on Carbon Nanomaterials	University of Notre Dame	$440,000	Reasearchers will develop the mechanisms, conditions and protocols to prepare uranium-carbon nanocomposite materials to make them more flexible. This could result in the generation of wholesale electricity, providing process heat, and providing power for households.	Document	MSTR	FY2012
High Hydrogen Content Graphene Hydride Compounds & High Cross-Section Cladding Coatings for Fast Neutron Detection	University of South Carolina	$430,000	This project will exploit recent breakthroughs to grow epitaxial graphene on commercial SiC wafers. This will allow researchers to develop a new detection method for fast neutrons. In addition, it will lead to better and more compact neutron detection system.	Document	MSTR	FY2012
Reducing Actinide Production Using Inert Matrix Fuels	University of Texas- Austin	$435,000	Reasearchers will perform a neutronic analysis, a thermal-hydraulic analysis and a simulation of fuel decay heat as a functionof fuel burnup, to determine if inert matrix fuel in coventional reactors will continue to be licensable. If successful, the inert matrix fuel mixtures will reduce harmful transuranic components in the fuel discharge streams at a level comparable to a fast reactcor burner.	Document	MSTR	FY2012
An Integrated Fuel Depletion Calculator for Fuel Cycle Options Analysis	University of Texas- Austin	$395,000	Reasearchers use new analysis techniques to better predict nuclear fuel behavior. The new model will allow improved fuel cycle for a larger number of users.	Document	MSTR	FY2012
Atomic-Scale to Meso-Scale Simulation Studies of Thermal Ageing and Irradiation Effects in Fe-Cr Alloys	Boston University	$874,997	Reasearchers will develop predictive, multi-scale simulation tools for iron-chromium alloys, which are expected to be key components of advanced steels envisioned as fuel cladding and structural components for Generation IV reactors. Such modeling is necessary to avoid resource intensive and costly thermal and neutron irradiation experiments to obtain required performance data.	Document	NEAMS	FY2012
Validation Data and Model Development for Fuel Assembly Response to Seismic Loads	George Washington University	$862,435	Reasearchers will conduct experiments that will provide comprehensive data characterizing the dynamics of the fluid and the structure in Pressurized Water Reactors (PWR) fuel assemblies under seismic loads (earthquakes and loss of coolant accidents). Completion of their project will greatly benefit the safety of existing and future nuclear reactors.	Document	NEAMS	FY2012
Uncertainty Quantification and Management for Multiscale Nuclear Materials Modeling	Georgia Institute of Technology	$743,444	Reasearchers will address the question of uncertainty propogation and error estimates associated with model prediction of material behavior under irradiation. Their work will facilitate a better understanding of the connection of various unit processes to collective responses in a multiscale model chain enabling the development of high strength and high ductility materials.	Document	NEAMS	FY2012
Fuel and Core Design Options to Overcome the Heavy Metal Loading Limit and Improve Performance and Safety of Liquid Salt Cooled Reactors	Georgia Insitute of Technology	$784,689	Reasearchers will examine new options for fuel and core designs in liquid salt cooled reactors where the current standard of TRISO type fuel has limitations due to loading characteristics. The research could enable new, more feasible fuel-core-reload options that will improve safety and performance parameters.	Document	RCRD&D	FY2012
Nonlinear Ultrasonic Techniques to Monitor Radiation Damage in RPV and Internal Components	Georgia Institute of Technology	$877,000	Reasearchers will explore new nondestructive materials evaluation and monitoring techniques utilizing nonlinear ultrasonic measurements . This technique will allow researchers to assess remaining useful life of select reactor components. Breakthroughs in this area will lead to the ability to characterize radiation damage in reactor pressure vessels and other components-leading to a clearer definition of reactor safety margins.	Document	RCRD&D	FY2012
Intergral Reactor Containment Condensation Model and Experimental Validation	Oregon State University	$871,119	Reasearchers will conduct experiments to enhance the safety and efficiency of small modular reactors (SMRs). This project will assess the impact of high-pressure steam condensation on steel containment vessels to be used for SMR deigns.	Document	RCRD&D	FY2012
Investigation of Natural Circulation Instability and Transients in Passively Safe Small Modular Reactors	Purdue University	$871,100	Reasearchers will perform scaled experiments to study the thermal-hydraulic instabilities that can occur in Small Modular Reactors (SMR) which rely on natural circulation cooling during normal operation and accident conditions. Their work will not only improve our understanding of general natural circulation instability but also lead to the development of stability criteria and predictability in the operation of SMRÃs.	Document	RCRD&D	FY2012
Thermoelectric-Driven Sustainable Sensing and Actuation Systems for Fault-Tolerant Nuclear Incidents	State University of New York, Stony Brook	$599,802	Reasearchers will examine the use of solid-state thermoelectric generators to produce electricity to sense and opeate during both normal and abnormal situations. This will provide indefinite monitoring of key components during power outages or station blackouts.	Document	RCRD&D	FY2012
Experimental and CFD Studies of Coolant Flow Mixing within Scaled Models of the Upper and Lower Plenums of NGNP Gas-Cooled Reactors	Texas A&M University	$713,051	Reasearchers will model the internal coolant flow of a prismatic core very high temperature reactor (VHTR) by using large eddy simulation tools. This method will enable more accurate prediction of flow field characteristics and better evaluation of VHTR behavior under operational and accidental conditions.	Document	RCRD&D	FY2012
Demonstrating Hybrid Heat Transport and Energy Conversion System Performance Characterization Using Intelligent Control Systems	University of Idaho	$877,000	Reasearchers will demonstrate an intelligent control systems in a hybrid energy conversion loop for a next generation nuclear power plant. Hybrid energy systems are a method of optimizing the use of natural resources for energy production. Hybrid systems present an opportunity to develop domestic energy sources to improve energy security.	Document	RCRD&D	FY2012
Advanced Reactor-Intermediate Heat Exchanger (IHX) Coupling: Theoretical Modeling and Experimental Validation	University of Idaho	$869,997	Reasearchers will model the behavior of the Advanced Reactor Intermediate Heat Exchanger Chemical Process system and develop advanced control techniques that take into account abnormal scenarios. The data and information obtained will assist in the development of intelligent control systems for next generation nuclear reactor systems.	Document	RCRD&D	FY2012
Irradiation Performance of Fe-Cr Base Alloys	University of Illinois- Urbana Champaign	$876,332	Reasearchers will perform post-radiation analysis and develop tools for future development and application of the Fe-Cr class of alloys. The results of this research will lead to better modeling of performance and development of an alloy designated as the primary choice for reactor fuel cladding and structural applications in advanced systems.	Document	RCRD&D	FY2012
Accelerated Irradiations for High Dose Microstructures in Fast Reactor Alloys	University of Michigan	$831,876	Reasearchers will determine the extent to which high dose rate irradiation can be used as an irradiation damage tool to understand microstructure evolution at high doses and temperatures relevant to advanced fast reactors. The project will provide fundamental understanding of the effectiveness of this process and thus of microstructure development in irradiated materials.	Document	RCRD&D	FY2012
Mitigating IASCC of Reactor Core Internals by Post-Irradiation Annealing Advanced Mitigation Strategies	University of Michigan	$876,985	Reasearchers will determine the optimum Post-irradiation annealing (PIA)-driven mitigation strategy to extend the potential lifetime of light water reactors. Samples that have already been irradiated in a light water reactor will be used to test PIA treatments to understand IASCC initiation and propoagation, annealing kinetics, the role of microstructure features in irradation hardening and localized deformation, and the optimum mitigation strategy based on PIA.	Document	RCRD&D	FY2012
Experimentally Validated Numerical Models for Effects of Non-Isothermal Turbulent Mixing on Wall Stresses in High Temperature Reactors	University of Pittsburgh	$876,422	Reasearchers will develop a comprehensive experimentally validated computational framework for the turbulent mixing in the lower plenum of a very high temperature reactor (VHTR). Through CFD modeling and experimental validation, the results from this project will lay the groundwork for future stress analysis, failure and fatigue studies, and uncertainty quantification for the VHTR system.	Document	RCRD&D	FY2012
Role of Defects in Swelling and Creep of Irradiated SiC	University of Wisconsin- Madison	$875,350	Reasearchers will study mechanisms controlling both radiation swelling and radiation creep in silicon carbide. These two effects are crucial to understanding the issues associated with the brittle silicon carbide composite. Success in this project will ground progress in the adoption of silicon carbide for reactor solutions, particularly as fuel cladding.	Document	RCRD&D	FY2012
Advanced Supercritical Carbon Dioxide Brayton Cycle Development	University of Wisconsin, Madison	$877,000	Reasearchers will investigate the benefits of utilizing advanced Brayton cycles with supercritical carbon dioxide in new reactor systems and components. Benefits of this research include improvement of analysis and performance of components currently utilizing these cycles as well as the potential for a large scale advanced CO2 power system.	Document	RCRD&D	FY2012
Mechanical Behavior of UO2 at Sub-grain Length Scales: Quantification of Elastic, Plastic and Creep Properties via Microscale Testing	Arizona State University	$800,000	Reasearchers will develop techniques to measure properties at sub-grain scales using depleted Uranium Oxide samples. The project will provide a framework to measure sub-grain scale mechanical properties, as well as provide experimental data to improve the understanding of advanced oxide fuels.	Document	FCR&D	FY2013
The Impacts of Pore-Scale Physical and Chemical Heterogeneities on the Transport of Radionuclide-Carrying Colloids	Colorado School of Mines	$800,000	Reasearchers will identify the dominant transport mechanisms to develop models that predict radionuclide distribution in porous materials. Experimental and computational models will be created that couple pore-scale geometric and interfacial structures. Simulators such as these are a necessary step towards fully predictive models for field-scale applications in the future.	Document	FCR&D	FY2013
Recovery of Uranium from Seawater: Polymer-Supported Aminophosphinates as Selective Extractants	Hunter College, CUNY	$399,999	Reasearchers will prepare a polymer-supported extractant for the recovery of uranium from seawater. The project will focus on primary amines that could provide a 3-fold increase in uranium capture capacity than current methods.	Document	FCR&D	FY2013
In-pile Thermal Conductivity Characterization with Single-laser Heating/Time Resolved Raman	Iowa State University	$800,000	Reasearchers will develop a time-resolved Raman-based thermal conductivity measurement system to improve remote in-pile thermal conductivity measurement. These measurements will provide new insights into the behavior of materials exposed to extreme radiation and temperature environments. Understanding the behavior of materials at the microstructural level will support optimized fuel designs.	Document	FCR&D	FY2013
Organic Speciation and Interactions in ALSEP - One Step Partitioning Process of Minor Actinides, Lanthanides, and Fission Products	Oregon State University	$600,000	Reasearchers will investigate the Actinide-Lanthanide Separation (ALSEP) process organic phase prior to aqueous phase separation and after aqueous separation phases of bare and metal-loaded acids. Quantifying these effects can be used to determine how an engineering scale process will perform and generate an accurate chemical model for the system.	Document	FCR&D	FY2013
Glass Composition and Solution Speciation Effects on Stage III Dissolution	Pennsylvania State University	$700,000	Reasearchers will study the chemical and structural triggers of long-term vitrified nuclear waste form behavior. They will study a range of waste glass compositions in corrosive environments. The study will improve understanding of the long-term residual rate and may provide new options for environmental control of glass dissolution rates.	Document	FCR&D	FY2013
Correlating Thermal, Mechanical, and Electrical Coupling Based Multiphysics Behavior of Nuclear Materials Through In-Situ Measurements	Purdue University	$800,000	Reasearchers will use in-situ experimental techniques to monitor the influence of extreme conditions on fuel cladding. The project will establish an in-situ experimental setup that can predict change in thermal properties and their correlation with mechanical properties and correlate such changes to changes in microstructural and chemical features.	Document	FCR&D	FY2013
Creation of a Geant4 Muon Tomography Package for Imaging of Nuclear Fuel in Dry Cask Storage	Purdue University	$440,000	Reasearchers will develop a simulation and analysis package to aid in the non-destructive assessment of sealed used nuclear fuel dry casks using cosmic ray muons. Cosmic ray muon tomography allows for non-destructive assessment that can independently verify and identify weapons grade material sealed within dense dry casks.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Two-stage Fast Reactor Fuel Cycle Options for Optimum Resource Utilization and Waste Management	Purdue University	$400,000	Reasearchers will evaluate the two different two-stage fast reactor fuel cycle options that will offer efficient use of uranium resources and the ability to burn actinides and long-live fission products. Evaluation of these fast fuel cycle options will serve as a useful complement to the options currently being considered in the Fuel Cycle Options Campaign.	Document	FCR&D	FY2013
Mixed Metal Phosphonate-Phosphate Resins for Separation of Lanthanides from Actinides	Texas A&M University	$650,000	Reasearchers will use ion exchangers to cleanly separate lanthanides and curium from reusable actinides. The study will assist in the development of an inexpensive, simple way in which to separate lanthanides from actinides found in used nuclear fuel rods and to recover a large portion of the usable fuel.	Document	FCR&D	FY2013
Safeguards in Pyroprocessing: an Integrated Model Development and Measurement Data Analysis	The Ohio State University	$626,151	Reasearchers will develop a comprehensive and effective safeguards approach for a pyroprocessing facility to support safeguards for future fuel cycles in the United States. The new approach and design will focus directly on the special nuclear materials in the electrorefiner where actinides are separated from fission products through electrochemical process.	Document	FCR&D	FY2013
Using Ionic Liquids for the Development of Renewable Biopolymer-Based Adsorbents for the Extraction of Uranium from Seawater and Testing Under Marine Conditions	University of Alabama	$400,000	Reasearchers will explore the fundamental engineering parameters for a renewable high-performance adsorbent for the extraction of uranium from sweater based on a recently proven ionic liquid (IL)-chitin platform. The project will use the platform to develop a versatile, modifiable adsorbent and characterize its performance and degradation in marine conditions.	Document	FCR&D	FY2013
Developing Ultra-Small Scale Mechanical Testing Methods and Microstructural Investigation Procedures for Irradiated Materials.	University of California, Berkeley	$800,000	Reasearchers will develop new small-scale mechanical testing techniques to allow for the estimation or direct measurement of bulk properties. The combined experiments and modeling will significantly enhance the statistics and information that can be obtained on small radioactive archived samples, as well as new ion beam irradiated specimens.	Document	FCR&D	FY2013
Improved Delayed-Neutron Spectroscopy Using Trapped Ions	University of California, Berkeley	$400,000	Reasearchers will develop innovative spectroscopy techniques to measure the decay of fission fragments. The resulting data from these new techniques will be used to better understand reactor kinetics under accident conditions and failure scenarios.	Document	FCR&D	FY2013
Thermally and Chemically Responsive Nanoporous Materials for Efficient Capture of Fission Product Gases	University of California, Davis	$750,000	Reasearchers will create new nanoporous materials that will be highly effective at capturing fission product gases. These materials would be relevant to both reactor fuels applications and reprocessing operations. Tests will be performed in carbon based and nitride based nanostructures, with the most promising materials from the modeling perspective undergoing further testing.	Document	FCR&D	FY2013
Multiphase Nanocrystalline Ceramic Concept for Nuclear Fuel	University of California, Irvine	$800,000	Researchers will study the use of nanoparticles and nanostructured ceramics to create new materials that can extend the service life and increase efficiency for nuclear fuel. Multiphase nanocrystalline ceramics will be used to design simulated nuclear fuel that can provide added plasticity, better radiation tolerance and improved thermal conductivity.	Document	FCR&D	FY2013
Development of Novel Porous Sorbents for Extraction of Uranium from Seawater	University of Chicago	$400,000	Reasearchers will develop a highly porous sorbent for the extraction of uranium from seawater. Previous research has established sorbent performance. This project will use past foundational studies to design and investigate a new nanocomposites that will be processed into tacks or braids for field tests in seawater tests. The technology may also be used for other metals.	Document	FCR&D	FY2013
Microwave Readout Techniques for Very Large Arrays of Nuclear Sensors	University of Colorado, Boulder	$799,937	Reasearchers will develop a powerful readout technique based on microwave transmission and reflection. The technique will enable very large arrays of diverse sensor types for nuclear materials quantification and tracking. It will provide more accurate data on material composition and quantity.	Document	FCR&D	FY2013
BiI3 Gamma-Ray Spectrometers for Reliable Room-Temperature Nuclear Materials Safeguarding	University of Florida	$799,999	Reasearchers will develop gamma-ray spectrometers based on BiI3 single crystals for MPACT applications such as burnup validation quantification, improved assay of plutonium, determination of uranium enrichment and overall monitoring spent fuel within the fuel cycle. The project will improve energy resolution, efficiency and environmental performance with this new gamma-ray detector.	Document	FCR&D	FY2013
Innovative Coating of Nanostructured Vanadium Carbide on the F/M Cladding Tube Inner Surface for Mitigating the Fuel Cladding Chemical Interactions	University of Florida	$760,276	Researchers will develop barrier coatings on the inner surface of fuel cladding tubes to improve performance of materials at elevated temperatures and high neutron exposures in fast reactors. The project will develop and test a low temperature coating process of nanostructured vanadium carbide that will provide a benchmark for use in future studies.	Document	FCR&D	FY2013
Doubling the Life of Concrete Structures	University of Idaho	$800,000	Reasearchers will use nanoscale techniques to develop methods for doubling the service life of concrete structures. They will study the effect of temperature load and temperature cycling (freezing and thawing) on the durability of concrete with nanoscale viscosity modifiers. The project will benefit from non-destructive evaluation of concrete performance through electrochemical techniques.	Document	FCR&D	FY2013
Off-Gas Treatment: Evaluation of Nano-structured Sorbents for Selective Removal of Contaminants	University of Idaho	$785,910	Reasearchers will evaluate nanostructured sorbent materials for their effectiveness in removing and immobilizing radionuclides for the off-gas treatment from used nuclear fuel recycling operations. The project aims at achieving near-zero emissions of radionuclides by capturing them from the off-gas of recycling operations, allowing for the development of advanced fuel cycles.	Document	FCR&D	FY2013
Innovative Elution Processes for Recovering Uranium and Transition Metals from Amidoxime-Based Sorbents	University of Idaho	$399,864	Reasearchers will develop a new two-step elution process to achieve total recovery of uranium and effective recycling of the sorbent. The extraction process would selectively remove uranium from the sorbent with little or no damage. The process would then remove transition metals and regenerate the sorbent for repeated use, making uranium extraction from seawater economically viable.	Document	FCR&D	FY2013
Performance of a Steel/Oxide Composite Waste Form for Combined Waste Streams from Advanced Electrochemical Processes over Geologic Time Scales	University of Illinois at Chicago	$700,000	Reasearchers will develop and validate a mechanistically-based corrosion model for cermet-type waste forms, creating a testing protocol and modeling approach for predicting long-term performance. The study will apply novel electrochemical testing and modeling methods to the behavior of metal/oxide phase boundaries to evaluate waste form performance.	Document	FCR&D	FY2013
Enhancement of the Extraction of Uranium from Seawater	University of Maryland, College Park	$400,000	Reasearchers will develop and optimize novel adsorbents for uranium recovery from seawater. The team will use radiation-induced grafting of organic phosphates onto polymers. The experiments will use ocean water, with mechanistic analysis, to provide a solid basis for large-scale demonstration of the performance of the new adsorbents in ocean environments.	Document	FCR&D	FY2013
Improving the Understanding of the Coupled Thermal-Mechanical-Hydrologic Behavior of Consolidating Granular Salt	University of New Mexico	$800,000	Reasearchers will increase the understanding of granular salt seal materials for shafts, drifts and boreholes. By coupling thermal, mechanical and hydrological responses, the study will result in greater confidence in granular salt consolidation as a principal strategy for closure and isolation of long-term waste repositories.	Document	FCR&D	FY2013
Fission Fragment Yield Data in Support of Advanced Reactor Technology	University of New Mexico	$399,816	Reasearchers will produce a highly accurate data set for thermal fission. These precision data are necessary for high-accuracy simulations of nuclear criticality, transmutation rates, radiation effects and heating as well as for nuclear fuel, material accounting and identification needs.	Document	FCR&D	FY2013
Molecular dynamics-based simulations of bulk/interfacial structures and diffusion behaviors in nuclear waste glasses	University of North Texas	$700,000	Reasearchers will generate accurate atomic structural models for use in Monte Carlo simulations of the dissolution of nuclear waste glasses. Large-scale molecular dynamics-based computer simulations will be used to investigate self-diffusion behaviors, interfacial structure, and other structures formed during dissolution of these glasses.	Document	FCR&D	FY2013
U3Si2 Fabrication and Testing for Implementation into the BISON Fuel Performance Code	University of South Carolina	$800,000	Reasearchers will fabricate, test and model a high uranium density, advanced nuclear fuel that operates at a much lower temperature and stores less energy. The work will deliver key research data on creep and grain growth, improving economics, through possible power uprates, and advancing accident tolerant fuels research.	Document	FCR&D	FY2013
Structural Health Monitoring of Nuclear Spent Fuel Storage Facilities	University of South Carolina	$738,618	Reasearchers will develop a nuclear structural health monitoring system based on a sensing technology that monitors material degradation and aging for dry cask storage systems. The low-cost, low-profile sensors will perform on-demand monitoring of the structural integrity of individual components as well as the entire system.	Document	FCR&D	FY2013
ORIGEN-based Nuclear Fuel Depletion Module for Fuel Cycle Assessment	University of Tennessee at Knoxville	$755,181	Reasearchers will develop a flexible reactor analysis module for the CYCLUS fuel cycle simulator based on established tools for reactor fuel depletion and decay. They will use ORIGEN, a mature and experimentally validated code, affording greater flexibility and allowing for accurate evaluations of impacts of both present and future fuel cycle options.	Document	FCR&D	FY2013
Cost and System Analysis of Innovative Fuel Resources Concepts	University of Texas at Austin	$295,960	_This project will develop and test braided polymer fiber adsorbents that surpass the sorption capacity, selectivity and durability of the best existing technology to recover uranium from seawater.	Document	FCR&D	FY2013
Risk Assessment of Structural Integrity of Transportation Casks	University of Utah	$789,296	Reasearchers will assess the loss of structural integrity of transportation casks and fuel cladding after extended storage. This risk assessment will conduct experimental tests and simulations to evaluate the structural performance of fuel, fuel assemblies and cask components when subjected to vibration and impact loads during transport.	Document	FCR&D	FY2013
Market-Based and System-Wide Fuel Cycle Optimization	University of Wisconsin, Madison	$612,731	Reasearchers will create market and economic optimizers to improve calculations for the CYCLUS fuel cycle simulator. The team will leverage existing optimization software frameworks within the simulator to resolve top level policy questions. The optimizations will allow CYCLUS to move beyond static material compositions, providing a holistic view of the fuel cycle system.		FCR&D	FY2013
Optical Fiber Based System for Multiple Thermophysical Properties for Glove Box, Hot Cell and In-Pile Applications	Utah State University	$799,975	Reasearchers will use a small pressure vessel to develop a robust technique for the measurement of multiple thermophysical properties at very high temperatures. The technique will lead to a system design moving toward the eventual measurement of irradiated fuels in a glovebox and/or hot cell with all sensors and electronics outside of the glovebox and/or hot cell.	Document	FCR&D	FY2013
Development of a Nano-Modified Concrete for Next Generation of Storage Systems	Vanderbilt University	$796,268	Reasearchers will use nano-sized and nano-structured particles based on enhanced reactivity to develop a superior concrete for the long-term storage of used nuclear fuel. The project will use state-of-the-art experimental chemical and mechanical characterizations and computation analysis to assess the performance of nano-modified concretes.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Thorium Fuel Cycle Options	Vanderbilt University	$797,995	Reasearchers will develop six fuel cycle data packages for multi-stage, thermal fuel cycles which incorporate thorium. These new fuel cycle data packages will provide the opportunity to examine fuel cycle options beyond those which have traditionally been considered. A thorium fuel cycle database will also be assembled as a basis for thorium literature for future evaluations of the thorium fuel cycle.	Document	FCR&D	FY2013
Enhanced Shielding Performance of HLW Storage Packages via Multi-Component Coatings	Virginia Polytechnic Institute and State University	$796,947	Reasearchers will develop a multi-layer composite that will enhance long-term storage and facilitate safe transport of storage packages. This novel multi-layer, multi-component coating would create an outer shield material that is resistant to the corrosion, radiation, diffusion and thermal cycling processes that affect fuel packages during long term storage.	Document	FCR&D	FY2013
Managing Zirconium Chemistry and Phase Compatibility in Combined Process Separations for Minor Actinide Partitioning	Washington State University	$700,000	Reasearchers will address unique challenges for combining TRUEX and TALSPEAK processes for partitioning of lanthanides and minor actinides. The project will develop improved information on the thermodynamics of fission product zirconium and develop a framework for an organic phase solvation model. Combined process development could streamline separations processes.	Document	FCR&D	FY2013
Advances in the Recovery of Uranium from Seawater: Studies Under Real Ocean Conditions	Woods Hole Oceanographic Institution	$398,882	Reasearchers will provide infrastructure and expertise for marine testing of currently available adsorbents in real ocean conditions. The team will move adsorbent research from the lab to field testing in order to quantify sorptive properties and uranium uptake. The project will provide valuable field data that will show the potential of large scale applications of these technologies.	Document	FCR&D	FY2013
NEUP Project 20-19172: Irradiation of Sensors and Adhesive Couplants for Application in LWR Primary Loop Piping and Components		$497,881	Reasearchers paln to attach ultrasonic transducers to substrates using various adhesive couplants that will be irradiated at elevated temperature to simulate LWR primary loop conditions at the PULSTAR reactor at North Carolina State University. Ultrasonic data will be taken in-situ. Subsequently, the sensors and couplant interfaces will be characterized using the LAMDA facility at ORNL. The results will be used to benefit a parallel EPRI project on online monitoring of cracks in LWR primary loop piping._	Document	R&D NSUF	FY2013
NEUP Project 20-19404: Extension of MSTDB to Provide a High-Quality, Validated Thermochemical Database for Predicting/Simulating Corrosion in Molten Salt Reactor SystemsUniversity of South Carolina		$600,000	Reasearchers will generate a validated, consistent database of initial fuel compositions and potential corrossion products of fluoride and chloride salts, allowing for important phenomena predictions in molten salt reactors to guide confident decisions. The database will be integral to the currently being developed Molten Salt Thermochemical Database (MSTDB), structured to allow use by commercial and open source codes._	Document	NEAMS	FY2013
Lower Length Scale Characterization and Validation of Formation and Stability of Helium Bubbles in Nano-structured Ferritic Alloys under Irradiation	Clemson University	$399,870	Reasearchers will provide a fundamental knowledge about the formation and stability of ultra-fine helium bubbles within 14YWT after neutron/ion irradiation for further design of new advanced structural materials with a characteristic high density nanoparticles feature which can increase the mechanical strength, hardness, irradiation resistance and the operational temperature range of materials.	Document	NEAMS	FY2013
Three-Dimensional Fuel Pin Model Validation by Prediction of Hydrogen Distribution in Cladding and Comparison with Experiment	Pennsylvania State University	$800,000	Reasearchers will validate important three-dimensional aspects of the fuel pin modeling by using specialized numerical modeling techniques coupled with laboratory experiments to validate existing models for predicting fuel performance in light water reactors.	Document	NEAMS	FY2013
Collocation-Based Surrogate Models for Uncertainty Quantification and Validation of Coupled, Multiphysics Fuel Performance Simulation Tools	University of Michigan	$596,835	Reasearchers will provide the necessary high fidelity, coupled, multiphysics fuel performance simulator for computational modeling and develop surrogates which will accelerate and focus the validation of the coupled codes. This will be achieved by utilizing the high fidelity coupled fuel performance, thermal-hydraulics and neutronics codes BISON/STAR-CCM+/MPACT and an innovative collocation-based surrogate methodology.	Document	NEAMS	FY2013
Multi-Resolution In-Situ Testing and Mutliscale Simulation for Creep Damage Fatigue Damage Analysis of Alloy 617	Arizona State University	$800,000	This project will develop novel testing and experimentally validated prediction methodologies for micro-structural damage mechanisms of structural materials for advanced reactor systems. The investigations will focus on the characterization and testing of specific metal alloys, but the proposed testing and life-prediction methodologies are applicable to other structural materials as well.	Document	RCRD&D	FY2013
Novel High Temperature and Radiation Resistant Infrared Glasses and Optical Fibers for Sensing in Advanced Small Modular Reactors	Clemson University	$800,000	Clemson University, in partnership with the Iowa State University and the Pacific Northwest National Laboratory, will develop novel optical materials with improved heat and radiation exposure resistance in order to enable in-vessel fiber optic sensing for advanced Small Modular Reactors.	Document	RCRD&D	FY2013
Validation Data Acquisition in HTTF during PCC Events	George Washington University	$800,000	Reasearchers at the George Washington University and Oregon State University will collaborate with NASA Langley Research Center to measure flow velocities in a high temperature test facility. This work supports the development of very-high temperature reactors with passive safety systems.	Document	RCRD&D	FY2013
Advanced High Temperature Inspection Capabilities for Small Modular Reactors	Iowa State University	$790,822	The objective of this project is to develop non-destructive evaluation techniques for advanced small modular reactors. The research will provide key enabling inspection technologies needed to support the design and the reactor component performance validation process for advanced small modular reactors.	Document	RCRD&D	FY2013
Experimental and Computational Investigations of Plenum-to-Plenum Heat Transfer under Natural Circulation in a Prismatic Very High Temperature Reactor	Missouri University of Science and Technology	$799,999	Reasearchers will perform experimental and computational investigations to study heat transfer and natural circulation phenomena in very-high temperature reactors. The study will assist in the ability to predict and analyze passive safety systems.	Document	RCRD&D	FY2013
New Mechanistic Models of Creep-Fatigue Crack Growth Interactions for Advanced High Temperature Reactor Components	Oregon State University	$790,790	Reasearchers will create and validate a robust, multi-scale, numerical model to predict material degradation in nickel-based reactor alloys. If successful, this project will provide better numerical tools for reactor designers and greatly improve their capability to design against material failures for reactor alloys in the long term.	Document	RCRD&D	FY2013
Self-Powered Wireless Dual-mode Langasite Sensor for Pressure/Temperature Monitoring of Nuclear Reactors	State University of New York, Stony Brook	$800,000	This research will develop a novel self-powered wireless hybrid sensor that can accurately monitor both pressure and temperature using a single device without requiring external electricity, even in extreme harsh environments.	Document	RCRD&D	FY2013
Compact Heat Exchanger Design and Testing for Advanced Nuclear Reactors and Advanced Power Cycles	The Ohio State University	$800,000	The goal of this project is to investigate optimal heat exchanger designs for advanced reactors. The research will study the optimization of printed circuit heat exchangers for specific fluids under a variety of conditions as well as perform numerical modeling. Experiments will focus on thermal performance and heat stress during extreme conditions.	Document	RCRD&D	FY2013
Fundamental Understanding of Creep-Fatigue Interactions in 9Cr-1MoV Steel Welds	The Ohio State University	$798,000	This project will advance the state of knowledge and fundamental understanding of deforming materials and welds under loading conditions. Specifically, new integrated testing procedures will be evaluated and applied for conditions that are most detrimental to material stability leading to improved predictions of life expectancy for reactor steels and welds.	Document	RCRD&D	FY2013
Advanced Mechanistic 3D Spatial Modeling and Analysis Methods to Accurately Represent Nuclear Facility External Event Scenarios	The Ohio State University	$800,000	Reasearchers will develop three-dimensional characterization uncertainty analysis for commercial power plants. The project will involve combining experts from the fields of seismic structural modeling and advanced methods of risk assessment. This effort is expected to result in next generation tools that can be used for assessment of seismic risks.	Document	RCRD&D	FY2013
Tritium Mitigation/Control for Advanced Reactor Systems	The Ohio State University	$400,000	Reasearchers will develop a fluoride salt cooled high-temperature reactor featuring a specialized system to control tritium production. If successful, this will result in a significant reduction in size and cost in comparison to other reactor designs.	Document	RCRD&D	FY2013
A Pebble-Bed Breed and Burn Reactor	University of California, Berkeley	$400,000	Reasearchers will assess the feasibility of designing a type of metal cooled reactor able to establish and maintain operation when fueled with depleted uranium. If successful, this reactor will offer at least a 30-fold increase in the uranium ore utilization versus that achieved in contemporary light water reactors without the need for fuel reprocessing and recycling.	Document	RCRD&D	FY2013
Investigation of Thermal Aging Effects on the Evolution of Microstructure and Mechanical Properties of Cast Duplex Stainless Steels	University of Maryland, College Park	$799,966	This research will provide a better understanding of the microstructural evolution and simultaneous change in mechanical response during aging. The results of the research will provide data that can be used to estimate degraded mechanical properties for an 80-year service life of light water reactors.	Document	RCRD&D	FY2013
Model validation using CFD-grade experimental database for NGNP Reactor Cavity Cooling Systems with water and air	University of Michigan	$799,348	Reasearchers will use advanced innovative instrumentation to build a high-resolution experimental database and to use the novel experimental data to assess and further develop the predictive capabilities of computer codes for thermal hydraulics and computational fluid dynamics. The improved models developed by this project will also have the direct benefit of improving the predictive capability of the passive systems of third generation light water reactors and small modular reactor systems.	Document	RCRD&D	FY2013
Long-Term Prediction of Emissivity of Structural Material for High Temperature Reactor Systems	University of Missouri	$799,117	Reasearchers will study specific types of emissivity driven cooling from a variety of materials that are relevant to nuclear reactors. The research will provide a basis for numerical modeling to support reactor development.	Document	RCRD&D	FY2013
Advanced I&C for Fault-Tolerant Supervisory Control of Small Modular Reactors	University of Pittsburgh	$800,000	The purpose of this research is to develop advanced instrumentation and control techniques for supervisory control of advanced small modular reactors. This research supports the operational goals of small modular reactor concepts through the development of improved oversight and surveillance techniques.	Document	RCRD&D	FY2013
Corrosion of Structural Materials for Advanced Supercritical Carbon-Dioxide Brayton Cycle	University of Wisconsin-Madison	$798,672	Reasearchers will study a variety of materials for corrosion resistance under conditions that improve power conversion. In addition to studying the corrosion resistance of the materials, researchers will study the effect of additives to mitigate corrosion. Development of corrosion theories and modeling aimed at prediction of long-term corrosion will be the underlying theme throughout the project.	Document	RCRD&D	FY2013
Component and Technology Development for Advanced Liquid Metal Reactors	University of Wisconsin-Madison	$798,920	In support of liquid metal cooled reactors, the University of Wisconsin, Madison will evaluate advanced alloys and ceramics that come in contact with liquid metals. Additionally, a robust oxygen sensor and for use in liquid metals will be developed in order to better evaluate corrosion profiles in support of diagnostic testing.	Document	RCRD&D	FY2013
A New Paradigm for Understanding Multi-phase Ceramic Waste Form Performance	Clemson University	$800,000	Researchers will use advanced characterization tools to develop 3-D microstructural data that can be incorporated into computer-based simulations in order to predict the performance of waste forms. Materials system modeling will incorporate elemental release and the interconnected microstructural network of phases to better understand performance and degradation, which will accelerate waste form acceptance in repository settings.	Document	FCR&D	FY2014
Controlling Hexavalent Americium: A Centerpiece to a Compact Nuclear Fuel Cycle	Colorado School of Mines	$800,000	Researchers will develop and exploit the fundamental chemistry of Americium to enable an industrially viable means to co-recover the major and minor actinide elements from used nuclear fuel. The results would be a significant step forward in the development of aqueous separations approaches designed to recover the U-Am actinides based on the availability of the hexavalent oxidation state.	Document	FCR&D	FY2014
Zeolite Membranes for Krypton/Xenon Separation from Spent Nuclear Fuel Reprocessing Off-Gas	Georgia Institute of Technology	$400,000	Researchers will develop a high-performance, lower-cost zeolitic membrane process for Kr/Xe separations during spent nuclear fuel processing. Current separation methods are not considered economical and a membrane process would have relatively lower cost, equipment size, and ambient operating temperature. The process would form a sound basis for further development of this transformative separation technology for the nuclear fuel cycle.	Document	FCR&D	FY2014
Optimizing Polymer-Grafted Amidoxime-based Adsorbents for Uranium Uptake from Seawater	Georgia Institute of Technology	$399,999	Researchers will work to increase the adsorbent capacity and selectivity toward uranium by optimizing the adsorbent morphology, synthesis variables, and conditioning parameters and by investigating the rate-limiting variables through transport and reaction modeling. A novel adsorption/partition concept that has the potential to substantially increase the adsorbent capacity will be tested, making uranium from seawater extraction more economically viable.	Document	FCR&D	FY2014
Extraction of Uranium from Seawater: Design and Testing of a Symbiotic System	Massachusetts Institute of Technology	$400,000	Researchers will develop a seawater uranium extraction system that will work symbiotically with an offshore windmill by utilizing the structure, mooring and power of the windmill, while increasing the energy harvested by the installation. Uranium will be extracted by an adsorbent polymer belt, which will be cycled through the seawater and an elution plant located at the base of the windmill tower. Increasing the frequency of harvesting could overcome current economic barriers to seawater uranium extraction.	Document	FCR&D	FY2014
Imaging a Dry Storage Cask with Cosmic Ray Muons	Oregon State University	$799,871	Researchers will develop an imaging system to monitor the content of a dry storage cask with cosmic ray muons. A very large amount of plutonium under nuclear safeguards is contained in used fuel assemblies stored in dry storage casks. Muon imaging will allow a cost effective and reliable way to evaluate dry storage cask content and integrity before transport.	Document	FCR&D	FY2014
Apatite and sodalite based glass-bonded waste forms for immobilization of 129I and mixed halide radioactive wastes	Rutgers University	$800,000	Researchers will develop advanced and chemically durable waste forms for immobilizing 129I (aqueous based reprocessing of fuel) and mixed-halide wastes (molten-salt processing of fuel) by low temperature synthesis. Halide-containing sodalite and calcium phosphate-based apatite minerals will be synthesized, consolidated and tested for chemical durability. The project will provide needed baseline data for the development of advanced waste forms for immobilization of iodine and mixed-halide wastes.	Document	FCR&D	FY2014
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$350,000	Researchers will develop modeling tools supported by experiments for off-gas capture from future nuclear-fuel recycling facilities. Target species include tritium, iodine, krypton, and xenon. The models are intended to provide path forward recommendations to develop off-gas treatment adsorption processes. The project will contribute to the evaluation of options for environmentally acceptable recycle systems.	Document	FCR&D	FY2014
Development of high performance ODS alloys	Texas A&M University	$800,000	Researchers will study swelling, radiation hardening and changes in mechanical properties of ODS alloys to develop two sets of advanced ODS alloys. Two sets of first-round candidate alloys that have already undergone extensive development and testing will evaluate irradiation performance. The study will meet the need for high strength, radiation-tolerant cladding and core components that have enhanced resistance to void swelling.	Document	FCR&D	FY2014
Rare Earth Electrochemical Property Measurements and Phase Diagram Development in a Complex Molten Salt Mixture for Molten Salt Recycle	The Ohio State University	$800,000	Researchers will investigate rare earth (RE) properties in complex molten salt mixtures. In a molten salt recycle approach, the RE drawdown by electrolysis is a key step in which REs are separated from salt containing other fission products. Investigation of RE electrolysis must consider the electrochemical properties of the REs. We propose to conduct studies of detailed experiments and corresponding models to provide the physical properties and phase diagrams required to predict the performance of RE drawdown for processing complex molten salts.	Document	FCR&D	FY2014
Studies of Lanthanide Transport in Metallic Nuclear Fuels	The Ohio State University	$800,000	Researchers will study the redistribution of lanthanides and migration of lanthanides to the fuel surface. The mechanisms of lanthanide transport in metallic fuel based on the novel discovery of a Ôliquid-likeÕ transport mechanism will be studied analytically and experimentally. The project will develop a fundamental understanding of lanthanide fission product migration and redistribution in advanced metallic nuclear fuels, and theory and data to mitigate fuel-cladding chemical interactions.	Document	FCR&D	FY2014
Computational and Experimental Studies of Microstructure-Scale Porosity in Metallic Fuels for Improved Gas Swelling Behavior	University of Arkansas	$796,823	Researchers will study the microstructure of metallic uranium alloy fuels, and their resistance to densification, to minimize in-pile irradiation swelling through bimodal pore size distribution. The project will develop a predictive approach to design metallic fuel microstructures for optimal swelling resistance and fission gas retention.	Document	FCR&D	FY2014
Improved Hybrid Modeling of Spent Fuel Storage Facilities	University of California, Berkeley	$645,393	Researchers will develop a variance reduction method for computational transport that will improve the ability to design and operate monitoring systems for interim used fuel installations through enhanced modeling and simulation. This new tool will demonstrate that modeling calculations can be done more accurately in less time than with current tools and will perform studies characterizing how changes in material, cask configurations, and number of casks could impact monitoring systems.	Document	FCR&D	FY2014
Selective ligands for uranyl via combinatorial peptoid libraries: A synthetic, structural, thermodynamic and computational study	University of California, Berkeley	$400,000	Researchers will study how donor ligands bind to the uranyl ion, UO22+, with the longer-term goal of using this information to tackle selective recognition of uranyl in aqueous solution. The study will impact underlying approaches to controlling the behavior of uranium in these systems. The actinide separation technology could be used in several areas including uranium extraction from seawater, nuclear waste remediation and nuclear materials.	Document	FCR&D	FY2014
Combining Experiments and Simulations of Extraction Kinetics and Thermodynamics in Advanced Separation Processes for Used Nuclear Fuel	University of California, Irvine	$799,938	Researchers will study how the kinetics and thermodynamics of metal ion extraction in advanced separation processes for used nuclear fuel can be described by molecular dynamic (MD) simulations and how the simulations can be validated by experimental data. The project would have broad impacts on several separations processes including advanced TALSPEAK, ALSEP and GANEX by increasing the confidence and accuracy of computer modeling of metal ion extraction._	Document	FCR&D	FY2014
Effect of Metallic Li on the Behavior of Metals in Molten Salts	University of Nevada, Reno	$458,250	Researchers will identify the effect of metallic lithium on materials that are used in molten salt recycling. The study will try to understand how the presence of Li(0) in molten salts affects the degradation of alloys. Studying these changes will help accurately predict container material behavior and longevity.	Document	FCR&D	FY2014
Assessment of Corrosion Resistance of Promising Accident Tolerant Fuel Cladding under Reactor Conditions	University of Notre Dame	$800,000	Researchers will assess the corrosion behavior of accident tolerant fuel candidate iron-based alloys under normal LWR operating conditions consisting of high temperature, relevant water chemistry and irradiation. The assessment will produce data about possible irradiation-accelerated corrosion rates of iron-based alloys, and the mechanisms by which such corrosion rates are accelerated. The project will advance the selection of appropriate replacements for Zircaloy cladding.	Document	FCR&D	FY2014
Functionalized Porous Organic Polymers as Uranium Nano-Traps for Efficient Recovery of Uranium from Seawaterr	University of South Florida	$399,000	Researchers will develop functionalized porous organic polymers, or Ônano-trapsÕ for extraction of uranium from seawater. This technique allows for increased surface area and custom-designed pore size and chemistry to fit specific parameters. The adsorbent materials have high efficiency and effectiveness for uranium recovery from seawater, providing a potential supply for nuclear fuel.	Document	FCR&D	FY2014
Enhanced Accident-Tolerant Fuel Performance and Reliability for Aggressive iPWR/SMR Operation	University of Tennessee	$799,967	To develop a process that evaluates operational and safety performance of reactor-and-fuel combinations by integrating whole-core 3D neutronics with MOOSE/BISON fuel performance assessments via explicit time and space dependent fuel rod operational power histories. The project will be valuable in analyzing and evaluating accident tolerant fuel concepts and furthering the understanding of reactor physics and fuel performance aspects of key accident tolerant fuel concepts.	Document	FCR&D	FY2014
Nuclear Technology R&D Strategies in an Era of Energy Price Uncertainty	University of Texas, Austin	$799,112	Researchers will identify nuclear technology options that are competitive over a wide range of plausible future business environments. No single nuclear technology or business practice will be the best choice across all or even most future conditions. The study will focus on hybrid nuclear-fossil technologies, energy storage and conversion, which will result in an identification of nuclear strategies that can succeed under future market conditions.	Document	FCR&D	FY2014
Development and Optimization of Voltammetric Methods for Real Time Analysis of Electrorefiner Salt with High Concentrations of Actinides and Fission Products	University of Utah	$621,612	Researchers will develop an advanced voltammetry method to pursue the objective of real time monitoring of actinide concentrations in electrorefiner salt. This will include experimental measurement of key parameters such as activity coefficients and exchange current density. It will also involve simulation of voltammetry processes based on first principles. The project will allow for real time measurements that could support the commercialization of pyroprocessing.	Document	FCR&D	FY2014
Development of Self-Healing Zirconium-Silicide Coatings for Improved Performance of Zirconium-Alloy Fuel Cladding	University of Wisconsin, Madison	$798,621	Researchers will study the deposition of self-healing zirconium-silicide coatings on zirconium-alloy fuel cladding material to improve corrosion resistance under normal and accident conditions. Under these conditions, Zr-Si coating evolves into a highly protective functionally-graded multilayered system. The study will lead to improved performance of zirconium-alloy fuels._	Document	FCR&D	FY2014
Thermal Conductivity in Metallic Fuels	Virginia Polytechnic Institute and State University	$799,837	Researchers will calculate the thermal conductivity of metallic uranium and neptunium alloys, including the effects of noble gasses, using density functional theory. The experiments will validate the calculated effective thermal conductivity using the MARMOT code and by helping determine DFT simulation parameters. The study works to improve fuel lifetime by understanding its thermal behavior.	Document	FCR&D	FY2014
SiC-ODS Alloy Gradient Nanocomposites as Novel Cladding Materials	Virginia Polytechnic Institute and State University	$799,998	Researchers will combine nuclear nanomaterial design, processing, testing, and characterization efforts to develop revolutionary materials that can withstand neutron irradiation for long period of time using nanostructured SiC and oxide dispersion strengthened steel. The ultimate objective is to offer new cladding materials with increased corrosion resistance, strength, and creep resistance in both steady state and accident conditions.	Document	FCR&D	FY2014
Experimental Breeder Reactor II Benchmark Evaluation	Idaho State University	$400,000	Researchers will develop a benchmark evaluation of the Experimental Breeder Reactor II (EBR-II). During nearly 30 years of operation numerous experiments were conducted at EBR-II. The most significant of these experiments were conducted in 1986 demonstrating inherent safety features in loss of flow without reactor scram and loss of heat sink without reactor scram. Benchmark evaluation will be valuable for the reactor design efforts in the United States and South Korea.	Document	MSNE	FY2014
Integral full core multi-physics PWR benchmark with measured data	Massachusetts Institute of Technology	$400,000	Researchers will introduce BEAVRS, a new multi-cycle full-core Pressurized Water Reactor (PWR) depletion benchmark based on two operational cycles of a commercial nuclear power plant. This project aims at addressing the uncertainty quantification of the measured data and on making this benchmark a true non-proprietary international benchmark for the validation of high-fidelity multi-physics computational tools.	Document	MSNE	FY2014
Benchmark Evaluation of PROTEUS Gas-Cooled Reactor Experiments	University of Florida	$400,000	Researchers will create International Reactor Physics Experiment Evaluation Project (IRPhEP) benchmarks using data from 1970s experiments of the neutronics of gas-cooled fast reactor (GCFR) designs investigated in the PROTEUS reactor. The GCFR-PROTEUS experiments fill a gap in current integral benchmark data. These experiments can provide validation of computational models and nuclear data for next generation reactors.	Document	MSNE	FY2014
An Investigation To Establish Multiphysical Property Dataset Of Nuclear Materials Based On In-Situ Observations And Measurements	Purdue University	$800,000	Researchers will create an in-situ measurement based experimental approach to develop experimental validation dataset for NEAMS based code validation. Particular emphasis is on supplying data set for multiphysics simulations in extreme conditions as a function of material microstructure.	Document	NEAMS	FY2014
Experimental Validation of UO2 Microstructural Evolutions for NEAMS tool MARMOT	University of Florida	$798,000	Researchers will experimentally validate MARMOT for predicting the microstructural evolutions of UO2 oxide fuel under the driving forces of high temperatures and large temperature gradient in reactors. By performing the experiments and simulations simultaneously using precisely defined initial conditions, the experiment data will provide direct benchmarking of the MARMOT code.	Document	NEAMS	FY2014
High-resolution time-resolved experiments on mixing and entrainment of buoyant jets in stratified environments	University of Michigan	$799,983	Researchers will study high spatial and time-resolution experimental data of the fluid dynamics phenomena of flow jets interacting with a stratified layer. The issue plays an important role in the safety of several reactor designs, including sodium-cooled reactors. The data addresses the NEAMS needs for the validation of high fidelity computational fluid dynamics methodologies.	Document	NEAMS	FY2014
Fundamental study of key issues related to advanced S-CO2 Brayton Cycle: prototypic HX development and Cavitation	Georgia Institute of Technology	$799,000	Researchers will study scientific and operational issues pertinent to compact heat exchanger systems and turbo-machinery. The project will work to resolve issues with the fabrication of diffusion bonded compact heat exchangers, alternate heat exchange technology for recuperators, and resolution of issues with cavitation and fluid instabilities.	Document	RCRD&D	FY2014
Advanced Models for Nondestructive Evaluation of Aging Nuclear Power Plant Cables	Iowa State University	$787,291	Researchers will develop advanced models that relate environmentally induced microstructural and chemical changes in cable insulation polymers to their macroscopic electrical parameters. These parameters will be measured and modeled over a wide range of the electromagnetic spectrum, covering several potential nondestructive evaluation techniques, enabling identification of the most sensitive techniques for future development.	Document	RCRD&D	FY2014
Development of Novel Functionally Graded Transition Joints for Improving the Creep Strength of Dissimilar Metal Welds in Nuclear Applications	Lehigh University	$800,000	Researchers will develop graded transition joints and improved creep life models for increasing the life of dissimilar metal welds (DMWs) in nuclear reactors. The research represents the first application of functionally graded material concepts for solving the problem of DMW failures through an integrated approach of additive manufacturing, modeling, microstructural characterization, and advanced strain-sensing techniques.	Document	RCRD&D	FY2014
Feasibility Assessment of a Micro Modular Reactor (MMR)	North Carolina State University	$400,000	Researchers will develop an innovative compact reactor concept that integrates power production, power conversion and electricity generation in a single unit: the Micro Modular Reactor (MMR). It is designed to be absolutely melt-down proof (MDP) under all circumstances including complete loss of coolant scenarios with no possible release of radioactive material, to have a cycle length of greater than 10 years, and to be highly proliferation resistant.	Document	RCRD&D	FY2014
Scaling Studies for Advanced Gas Reactor Concepts	Oregon State University	$681,834	Researchers will expand the utilization of the Oregon State University High Temperature Test Facility (HTTF) to validate a broader range of advanced high temperature reactors and events. The facility will be revised to add a detailed scaling analysis of additional gas reactor concepts including advanced gas-cooled, molten salt, and sodium cooled reactors.	Document	RCRD&D	FY2014
Fluid Stratification Separate Effects Analysis, Testing and Benchmarking	Oregon State University	$800,000	Researchers will study fluid stratification in high temperature gas reactors. Coolant stratification is the result of incomplete mixing of one or more fluids, leading to a density gradient, which may or may not dissipate under diffusive or convective effects. This combined analytical and experimental project seeks to investigate stratification driven by diffusive and convective mechanisms and is expected to yield insight into this phenomenon.	Document	RCRD&D	FY2014
Probabilistic Economic Valuation of Safety Margin Management Analysis	Oregon State University	$795,364	Researchers will use RAVEN and develop a companion software package to facilitate economic analysis of safety margins. The project is a proof of concept that will use techniques to examine the cost of improving safety margins vs. the risk of accidents from not improving safety margins. This analysis can be used to evaluate the economic viability of various plant upgrades.	Document	RCRD&D	FY2014
Novel Dissimilar Joints Between Alloy 800H and 2.25%Cr and 1%Mo Steel	Pennsylvania State University	$800,000	Researchers will fabricate and test dissimilar metal joints between a nickel base alloy and a steel with gradual variations of chemical composition, microstructure and properties in a manner that reduces abrupt thermal expansion mismatch and the resulting residual stresses. Data on structure and properties will serve as valuable inputs for the initiation of an ASME code case.	Document	RCRD&D	FY2014
Multi-Phase Model Development to Assess RCIC System Capabilities under Severe Accident Conditions	Texas A&M University	$564,246	Researchers will develop physics-based models of the Reactor Core Isolation Cooling (RCIC) System and incorporating them into a multi-phase code for validation. The project will tackle the current major challenges in RCIC System analysis and enable evaluation of two-phase thermodynamic aspects.	Document	RCRD&D	FY2014
Experimental Investigation and CFD Analysis of Steam Ingress Accidents in HTGRs	The Ohio State University	$800,000	Researchers will study the steam ingress scenario for HTGRs. The study will investigate thermal-hydraulic behavior and graphite oxidation of stream ingress phenomena to validate predictive CFD models. This work will resolve concerns about possible steam generator tube ruptures in a HTGR He-Steam Rankine cycle.	Document	RCRD&D	FY2014
Coiled Tube Gas Heaters For Nuclear Gas-Brayton Power Conversion	University of California, Berkeley	$800,000	Researchers will develop heat exchangers for Brayton-cycle power conversion in reactors using sodium, NaK, or salt as intermediate coolants. The proposed coiled tube gas heaters (CTGHs) are expected to have excellent power density, thermal shock/creep, in-service inspection, and reparability characteristics.	Document	RCRD&D	FY2014
Fundamental Studies of Irradiation-Induced Modifications in Microstructural Evolution and Mechanical Properties of Advanced Alloys	University of Illinois, Urbana-Champaign	$800,000	Researchers will develop and test a mechanism for predicting neutron irradiation performance for optimized Grade 92 and Alloy 709 for applications in advanced reactor systems. The work will employ ion irradiations and available information from neutron irradiations of related alloys to develop a basis for predicting the neutron irradiation performance of the optimized alloys.	Document	RCRD&D	FY2014
Integrated Computational and Experimental Study of Radiation Damage Effects in Grade 92 Steel and Alloy 709	University of Tennessee	$800,000	Researchers will develop a mechanistic understanding and predictive models of irradiation-induced microstructural evolution and resulting mechanical properties in optimized ferritic-martensitic Grade 92 steel and austenitic alloy 709 using multiscale simulations coupled with rigorous experimental validation. The project will provide insights into the correlation between ion irradiation and fast neutron damage.	Document	RCRD&D	FY2014
Meta-Level Design Guidance and Operator Performance Measures for Hybrid Control Rooms	Vanderbilt University	$799,869	Researchers will apply human factors engineering methods and relevant expertise from non-nuclear high-risk high-consequence domains toward the measurement of operator performance in analog, digital, and hybrid main control rooms. Performance measures will be developed for evaluating the situation awareness and decision-making proficiencies to support the transition to digital or hybrid control room displays.	Document	RCRD&D	FY2014

FY 2018 Research and Development Awards

DOE is awarding $47 million through its Nuclear Energy University Program (NEUP) to support 63 university-led nuclear energy research and development projects in 29 states. NEUP seeks to maintain U.S. leadership in nuclear research across the country by providing top science and engineering faculty and their students opportunities to develop innovative technologies and solutions for civil nuclear capabilities.

A complete list of R&D projects with their associated abstracts is available below.

Title	Institution	Estimated Funding*	Project Description	Abstract	Project Type	Fiscal Year
Neutron Damage and MAX Phase Ternary Compounds	Drexel University			Document	IIR	FY2009
Atomistic Calculations of the Effect of Minor Actinides on Thermodynamic and Kinetic Properties of UO2+x	Georgia Institute of Technology			Document	IIR	FY2009
Maximum Fuel Utilization in Fast Reactors without Chemical Reprocessing	University of California, Berkeley			Document	IIR	FY2009
Developing a High Thermal Conductivity Fuel with Silicon Carbide Additives	University of Florida			Document	IIR	FY2009
Fabrication of Tungsten-Rhenium Cladding Materials via Spark Plasma Sintering for Ultra High Temperature Reactor Applications	University of Idaho			Document	IIR	FY2009
Ionic Liquid and Supercritical Fluid Hyphenated Techniques for Dissolution and Separation of Lanthanides, Actinides, and Fission Products	University of Idaho			Document	IIR	FY2009
Improved Fission Neutron Data Base for Active Interrogation of Actinides	University of Michigan			Document	IIR	FY2009
Utilization of Methacrylates and Polymer Matrices for the Synthesis of Ion Specific Resins	University of Nevada, Las Vegas			Document	IIR	FY2009
Improved LWR Cladding Performance by EPD Surface Modification Technique	University of Wisconsin, Madison			Document	IIR	FY2009
Advanced Models of LWR Pressure Vessel Embrittlement for Low Flux-High Fluence Conditions	University of California, Santa Barbara			Document	LWRS	FY2009
Irradiation Creep in Graphite	Boise State University			Document	NGNP	FY2009
Modeling the Stress Strain Relationships and Predicting Failure Probabilities For Graphite Core Components	Cleveland State University			Document	NGNP	FY2009
TRISO-Coated Fuel Durability Under Extreme Conditions	Colorado School of Mines			Document	NGNP	FY2009
An Innovative and Advanced Coupled Neutron Transport and Thermal Hydraulic Method (Tool) for the Design, Analysis and Optimization of VHTR/NGNP Prismatic Reactors	Georgia Institute of Technology			Document	NGNP	FY2009
Removal of 14C from Irradiated Graphite for Graphite Recycle and Waste Volume Reduction	Idaho State University			Document	NGNP	FY2009
Millimeter-Wave Thermal Analysis Development and Application to Gen IV Reactor Materials	Massachusetts Institute of Technology			Document	NGNP	FY2009
Accurate Development of Thermal Neutron Scattering Cross Section Libraries	North Carolina State University			Document	NGNP	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
Understanding Creep Mechanisms in Graphite with Experiments, Multiscale Simulations, and Modeling	North Carolina State University			Document	NGNP	FY2009
Simulations of the Thermodynamic and Diffusion Properties of Actinide Oxide Fuel Materials	University of Michigan			Document	AFCI	FY2009
Verification & Validation of High-Order Short-Characteristics-Based Deterministic Transport Methodology on Unstructured Grids	North Carolina State University			Document	NGNP	FY2009
Adsorptive Separation and Sequestration of Krypton, I and C14 on Diamond Nanoparticles	University of Missouri, Columbia			Document	AFCI	FY2009
Microscale Heat Conduction Models and Doppler Feedback	North Carolina State University			Document	NGNP	FY2009
Fundamental Understanding of Ambient and High-Temperature Plasticity Phenomena in Structural Materials in Advanced Reactors	Georgia Institute of Technology			Document	AFCI	FY2009
Development of Alternative Technetium Waste Forms	University of Nevada, Las Vegas			Document	AFCI	FY2009
Optimizing Neutron Thermal Scattering Effects in Very High Temperature Reactors	North Carolina State University			Document	NGNP	FY2009
Advanced Elastic/Inelastic Nuclear Data Development Project	Idaho State University			Document	AFCI	FY2009
Heterogeneous Recycling in Fast Reactors	Massachusetts Institute of Technology			Document	AFCI	FY2009
Quantification of UV-Visible and Laser Spectroscopic Techniques for Materials Accountability and Process Control	University of Nevada, Las Vegas			Document	AFCI	FY2009
Multiaxial Creep-Fatigue and CreepRatcheting Failures of Grade 91 and Haynes 230 Alloys Toward Addressing Design Issues of Gen IV Nuclear Power Plants	North Carolina State University			Document	NGNP	FY2009
Thermodynamic Development of Corrosion Rate Modeling in Iron Phosphate Glasses	Missouri University of Science and Technology			Document	AFCI	FY2009
Development of Subspace-Based Hybrid Monte Carlo-Deterministic Algorithms for Reactor Physics Calculations	North Carolina State University			Document	AFCI	FY2009
High-Fidelity Space-Time Adaptive Multiphysics Simulations in Nuclear Engineering	University of Nevada, Reno			Document	AFCI	FY2009
Improvements to Nuclear Data and Its Uncertainties by Theoretical Modeling	Rensselaer Polytechnic Institute			Document	AFCI	FY2009
Investigation of Countercurrent Helium-air Flows in Air-ingress Accidents for VHTRs	Ohio State University			Document	NGNP	FY2009
Sharp Interface Tracking in Rotating Microflows of Solvent Extraction	State University of New York at Stony Brook			Document	AFCI	FY2009
Bulk Nanostructured FCC Steels with Enhanced Radiation Tolerance	Texas A&M University			Document	AFCI	FY2009
Simulations of Failure via Three-Dimensional Cracking in Fuel Cladding for Advanced Nuclear Fuels	University of Texas, Dallas			Document	AFCI	FY2009
Testing of Performance of Optical Fibers Under Irradiation in Intense Radiation Fields, When Subjected to Very High Temperatures	Ohio State University			Document	NGNP	FY2009
Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels	Texas A&M University			Document	AFCI	FY2009
SiC Schottky Diode Detectors for Measurement of Actinide Concentrations from Alpha Activities in Molten Salt Electrolyte	The Ohio State University			Document	AFCI	FY2009
Computational Design of Advanced Nuclear Fuels	University of California, Davis			Document	AFCI	FY2009
Advanced Mesh-Enabled Monte Carlo Capability for Multi-Physics Reactor Analysis	University of Wisconsin, Madison			Document	AFCI	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
A Distributed Fiber Optic Sensor Network for Online 3-D Temperature and Neutron Fluence Mapping in a VHTR Environment	Texas A&M University			Document	NGNP	FY2009
Ab Initio Enhanced Calphad Modeling of Actinide Rich Nuclear Fuels	University of Wisconsin, Madison			Document	AFCI	FY2009
Investigation on the Core Bypass Flow in a Very High Temperature Reactor	Texas A&M University			Document	NGNP	FY2009
Development of Diffusion Barrier Coatings and Deposition Technologies for Mitigating Fuel Cladding Chemical Interactions (FCCI)	University of Wisconsin, Madison			Document	AFCI	FY2009
CFD Model Development and Validation for High Temperature Gas Cooled Reactor Cavity Cooling System (RCCS) Applications	Texas A&M University			Document	NGNP	FY2009
Thermal Properties of LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin, Madison			Document	AFCI	FY2009
Study of Air ingress across the duct during the accident conditions	Texas A&M University			Document	NGNP	FY2009
Verification of the CENTRM Module for Adaptation of the SCALE Code to NGNP Prismatic and PBR Core Designs	University of Arizona			Document	NGNP	FY2009
Integral and Separate Effects Tests for Thermal Hydraulics Code Validation for Liquid-Salt Cooled Nuclear Reactors	University of California, Berkeley			Document	NGNP	FY2009
Mechanisms Governing the Creep Behavior of High Temperature Alloys for Generation IV Nuclear Energy Systems	University of Cincinnati			Document	NGNP	FY2009
ALD Produced B2O3, Al2O3 and TiO2 Coatings on Gd2O3 Burnable Poison Nanoparticles	University of Colorado, Boulder			Document	NGNP	FY2009
Experimental Study and Computational Simulations of Key Pebble Bed Thermomechanics Issues for Design and Safety	University of Idaho			Document	NGNP	FY2009
Prediction and Monitoring Systems of Creep-Fracture Behavior of 9Cr-1Mo Steels for Reactor Pressure Vessels	University of Idaho			Document	NGNP	FY2009
Understanding Fundamental Material Degradation Processes in High Temperature Aggressive Chemomechanical Environments	University of Illinois, Urbana-Champaign			Document	NGNP	FY2009
Multi-Scale Multi-physics Methods Development for the Calculation of Hot-Spots in the NGNP	University of Michigan			Document	NGNP	FY2009
Corrosion and Creep of Candidate Alloys in High Temperature Helium and Steam Environments for the NGNP	University of Michigan			Document	NGNP	FY2009
Creation of a Full-Core HTR Benchmark with the Fort St. Vrain Initial Core and Validation of the DHF Method with Helios for NGNP Configurations	University of Michigan			Document	NGNP	FY2009
Fission Product Sorptivity in Graphite	University of Missouri, Columbia			Document	NGNP	FY2009
Identifying and Understanding Environment-Induced Crack Propagation Behavior in Ni-Based Superalloy INCONEL 617	University of Nevada, Las Vegas			Document	NGNP	FY2009
Graphite Oxidation Simulation in HTR Accident Conditions	University of New Mexico			Document	NGNP	FY2009
Non Destructive Thermal Analysis and In Situ Investigation of Creep Mechanism of Graphite and Ceramic Composites using Phase-sensitive THz Imaging & Nonlinear Resonant Ultrasonic Spectroscopy	University of Rochester			Document	NGNP	FY2009
Tritium Sequestration in Gen IV NGNP Gas Stream via Proton Conducting Ceramic Pumps	University of South Carolina			Document	NGNP	FY2009
Materials, Turbomachinery and Heat Exchangers for Supercritical CO2 Systems	University of Wisconsin, Madison			Document	NGNP	FY2009
Experimental Studies of NGNP Reactor Cavity Cooling System with Water	University of Wisconsin, Madison			Document	NGNP	FY2009
Assessment of Embrittlement of VHTR Structural Alloys in Impure Helium Environments	University of Wisconsin, Madison			Document	NGNP	FY2009
Modeling Fission Product Sorption in Graphite Structures	University of Wisconsin, Madison			Document	NGNP	FY2009
Liquid Salt Heat Exchanger Technology for VHTR Based Applications	University of Wisconsin, Madison			Document	NGNP	FY2009
Effect of Post-Weld Heat Treatment on Creep Rupture Properties of Grade 91 Steel Heavy Section Welds	Utah State University			Document	NGNP	FY2009
Alpha Radiolysis of Nuclear Solvent Extraction Ligands used for An(III) and Ln(III) Separations	California State University, Long Beach	$1,390,252		Document	FCR&D	FY2010
Predictive Maturity of Multi-Scale Simulation Models for Fuel Performance	Clemson University	$614,690		Document	FCR&D	FY2010
Freeze-casting as a Novel Manufacturing Process for Fast Reactor Fuels	Drexel University	$1,149,327		Document	FCR&D	FY2010
Fuel Performance Experiments on the Atomistic Level, Studying Fuel Through Engineered Single Crystal UO2	Idaho State University	$650,000		Document	FCR&D	FY2010
Development of A Self Biased High Efficiency Solid-State Neutron Detector for MPACT Applications	Rensselaer Polytechnic Institute	$810,141		Document	FCR&D	FY2010
Development of a Innovative High Thermal Conductivity UO 2 Ceramic Composites Fuel Pellets with Carbon Nano-Tubes Using Spark Plasma Sintering	University of Florida	$894,042		Document	FCR&D	FY2010
Exploration and Modeling of Structural Changes in Waste Glass under Corrosion	Pennsylvania State University	$1,377,444		Document	FCR&D	FY2010
Evaluation of materials for interim storage of spent fuel for more than 100 years	University of Michigan	$931,603		Document	FCR&D	FY2010
Implementation of On-the-Fly Doppler Broadening in MCNP5 for Multiphysics Simulation of Nuclear Reactors	University of Michigan	$406,712		Document	FCR&D	FY2010
Methods and tools to allow molecular flow simulations to be coupled to higher level continuum descriptions of flows in porous/fractured media and aerosol/dust dynamics	University of Missouri-Columbi	$541,286		Document	FCR&D	FY2010
Characterization and Modeling of Materials for Kr-Xe Separations	University of Nevada-Las Vegas	$989,800		Document	FCR&D	FY2010
Modeling Solute Thermokinetics in LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin-Madison	$616,073		Document	FCR&D	FY2010
Advanced Aqueous Separation Systems for Actinide Partitioning: Develop Fundamental Understanding of An(III)/Ln(III) Separation	Washington State University	$1,451,784		Document	FCR&D	FY2010
Consistent Multigroup Theory Enabling Accurate Coarse-Group Simulation of GenIV Reactors	Georgia Institute of Technology	$1,046,277		Document	GEN IV	FY2010
Studies of Deteriorated Heat Transfer in Prismatic Cores Stemming from Irradiation-Induced Geometry Distortion	Idaho State University	$1,287,921		Document	GEN IV	FY2010
Carbide Coatings for Nickel Alloys, Graphite, and Carbon/Carbon Composites to be Used in Fluoride Salt Valves	Johns Hopkins University	$1,183,239		Document	GEN IV	FY2010
Design, Testing, and Modeling of the Direct Reactor Auxiliary Cooling System for AHTRs	Ohio State University	$1,366,627		Document	GEN IV	FY2010
Monitoring microstructural evolution of Alloy 617 with nonlinear acoustics for remaining useful life prediction; multiaxial creep-fatigue and creep-ratcheting	Pennsylvania State University	$1,000,000		Document	GEN IV	FY2010
Development and Validation of Multidimensional Models of Supercritical CO 2 Energy Conversion Systems for Nuclear Power Reactors	Rensselaer Polytechnic Institute	$475,005		Document	GEN IV	FY2010
Multiscale Concrete Modeling for Aging Degradation	Mississippi State University	$345,941		Document	LWRS	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term and Elevated Temperature Irradiation: Modeling and Experimental Investigation	University of California-Berkeley	$1,320,667		Document	GEN IV	FY2010
Development of an advanced computational fluid dynamics technology for the next-generation nuclear reactor system analysis and safety margin characterization code	North Carolina State University	$418,199		Document	LWRS	FY2010
Development of Barrier Layers for the Protection of Candidate Alloys in the VHTR	University of California-Santa Barbara	$995,232		Document	GEN IV	FY2010
Precursor Derived Nanostructured Si-C-X Materials for Nuclear Applications	University of Washington	$899,518		Document	MRIIR	FY2010
Investigation of a Novel NDE Method for Monitoring Thermo-Mechanical Damage and Microstructure Evolution in Ferritic-Martensitic Steels for Generation IV Nuclear Energy Systems	University of Cincinnati	$833,109		Document	GEN IV	FY2010
Development and Testing of an Open-Loop Oscillator for Small Reactivity Worth Samples	Idaho State University	$597,252		Document	MRIIR	FY2010
Fission Product Transport in TRISO Particle Layers under Operating and Off-Normal Conditions	University of Michigan	$966,581		Document	GEN IV	FY2010
Understanding the Irradiation Behavior of Zirconium Carbide	Pennsylvania State University	$870,613		Document	MRIIR	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term Irradiation at Elevated Temperature: Critical Experiments	University of Michigan	$1,181,379		Document	GEN IV	FY2010
Modeling investigation of the stability and irradiation-induced evolution of nanoscale precipitates in advanced structural materials	University of Tennessee-Knoxville	$380,653		Document	MRIIR	FY2010
Three-dimensional NDE of VHTR Core Components via Simulation-based Testing	University of Minnesota	$1,366,163		Document	GEN IV	FY2010
Investigation of Laser Shock Peening for Enhancing Fatigue and Stress Corrosion Cracking Resistance of Nuclear Energy Materials	University of Cincinnati	$1,242,019		Document	MRIIR	FY2010
Failure Predictions for VHTR Core Components using a Probabilistic Continuum Damage Mechanics Model	University of Minnesota	$854,542		Document	GEN IV	FY2010
Irradiation Accelerated Corrosion of Reactor Core Materials	University of Michigan	$798,943		Document	MRIIR	FY2010
Development of a Scanning Microscale Fast Neutron Irradiation Platform for Examining the Correlation Between Local Neutron Damage and Graphite Microstructure	University of Missouri-Columbia	$703,064		Document	GEN IV	FY2010
Study of Interfacial Interactions using Thin Film Surface Modification: Radiation and Oxidation Effects in Materials	University of Wisconsin-Madison	$538,032		Document	MRIIR	FY2010
Development of Thermal Transient Flow Rate Sensors for High Temperature, Irradiation, Corrosive Environment	University of Nevada-Las Vegas	$451,269		Document	GEN IV	FY2010
Novel Engineered Refractory Materials for Advanced Reactor Applications	North Carolina State University	$1,129,304		Document	MRIIR	FY2010
Novel Methods of Tritium Sequestration: High Temperature Gettering and Separation Membrane Materials Discovery for Nuclear Energy Systems	University of South Carolina	$1,366,626		Document	GEN IV	FY2010
Heat Transfer Salts for Nuclear Reactor Systems - Chemistry Control, Corrosion Mitigation, and Modeling	University of Wisconsin-Madison	$1,352,040		Document	GEN IV	FY2010
Pulsed Magnetic Welding for Advanced Core and Cladding Steels	University of Wisconsin-Madison	$525,206		Document	GEN IV	FY2010
Corrosion in Supercritical Carbon Dioxide: Materials, Environmental Purity, Surface Treatments, and Flow Issues	University of Wisconsin-Madison	$651,447		Document	GEN IV	FY2010
Quantification of Cation Sorption to Engineered Barrier Materials Under Extreme Conditions	Clemson University	$1,171,380		Document	FCR&D	FY2011
In-Pile Instrumentation Multi-Parameter System Utilizing Photonic Fibers and Nanovision	Idaho State University	$1,199,990		Document	FCR&D	FY2011
Development of Plasmonically Cloaked Nanoparticles	Idaho State University	$800,000		Document	FCR&D	FY2011
Fission Product Transmutation in Mixed Radiation Fields	Idaho State University	$800,000		Document	FCR&D	FY2011
Life Prediction of Spent Fuel Storage Canister Material	Massachusetts Institute of Technology	$899,826		Document	FCR&D	FY2011
Active Interrogation using Photofission Technique for Nuclear Materials Control and Accountability	Oregon State University	$900,000		Document	FCR&D	FY2011
Anisotropic Azimuthal Power and Temperature Distribution on Fuel Rod: Impact of Hydride Distribution	Pennsylvania State University	$631,956		Document	FCR&D	FY2011
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$1,000,000		Document	FCR&D	FY2011
Recovery of Uranium from Seawater: Preparation and Development of Polymer-Supported Extractants	City College of New York, Hunter	$363,716		Document	MSTR	FY2011
Microemulsions and Aggregation Formation in Extraction Processes for Used Nuclear Fuel: Thermodynamics and Structural Studies	University of California, Irvine	$1,000,000		Document	FCR&D	FY2011
One-Dimensional Nanostructures for Neutron Detection	North Carolina State University	$455,629		Document	MSTR	FY2011
Optimized Processing Fabrication Paths for Larger Heats of Nanostructured Ferritic Alloys	University of California, Santa Barbara	$1,000,000		Document	FCR&D	FY2011
Feasibility and Safety Assessment for Advanced Reactor Concepts Using Vented Fuel	Oregon State University	$600,000		Document	MSTR	FY2011
Basic Physics Data: Measurement of Neutron Multiplicity from Induced Fission	University of Michigan	$973,364		Document	FCR&D	FY2011
Development of an Efficient Meso-Scale Multi-Phase Flow Solver in Nuclear Applications	City College of New York	$505,858		Document	NEAMS	FY2011
High Temperature Transducers for Online Monitoring of Microstructure Evolution	Pennsylvania State University	$455,628		Document	MSTR	FY2011
Radionuclide Incorporation and Long Term Performance of Apatite Waste Forms	University of Michigan	$862,500		Document	FCR&D	FY2011
Multiscale Modeling and Uncertainty Quantification for Nuclear Fuel Performance	Colorado State University	$1,098,250		Document	NEAMS	FY2011
Laser-Arc Hybrid Welding of Thick Section Ni-base Alloys- Advanced Modeling and Experiments	Pennsylvania State University	$536,117		Document	MSTR	FY2011
Actinide Foil Production for MPACT Research	University of Nevada-Las Vegas	$156,897		Document	FCR&D	FY2011
Fundamental Studies of the Role of Grain Boundaries on Uniform Corrosion of Advanced Nuclear Reactor Materials	Drexel University	$1,098,250		Document	NEAMS	FY2011
Correlates of Sensitive Technologies	Texas A&M University	$509,467		Document	MSTR	FY2011
Enriched Boron-Doped Amorphous Selenium Based Position-Sensitive Solid-State Thermal Neutron Detector for MPACT Applications	University of South Carolina	$1,000,000		Document	FCR&D	FY2011
Phenomena-based Uncertainty Quantification in Predictive Coupled-Physics Reactor Simulations	Texas A&M University	$1,098,250		Document	NEAMS	FY2011
Improved Safety Margin Characterization of Risk from Loss of Offsite Power	Texas A&M University	$600,000		Document	MSTR	FY2011
Development of Advanced High Uranium Density Fuels for Light Water Reactors	University of Wisconsin-Madison	$1,000,000		Document	FCR&D	FY2011
Characterization of Modeling of Grain Boundary Chemistry Evolution in Ferritic Steels Under Irradiation	University of Michigan	$1,098,250		Document	NEAMS	FY2011
Diffusion, Thermal Properties and chemical Compatibilities of Select MAX Phases with Materials for Advanced Nuclear Systems	Drexel University	$535,927		Document	NEET	FY2011
A High Temperature-Tolerant and Radiation-Resistant In-Core Neutron Sensor for Advanced Reactors	The Ohio State University	$455,629		Document	MSTR	FY2011
Developing the User Experience for a Next Generation Nuclear Fuel Cycle Simulator	University of Wisconsin-Madison	$1,200,000		Document	FCR&D	FY2011
Development of Multiscale Materials Modeling Techniques and Coarse-Graining Strategies for Predicting Materials Degradation in Extreme Irradiation Environments	University of Tennessee, Knoxville	$750,000		Document	NEAMS	FY2011
A New Light Weight Structural Material for Nuclear Structures	North Carolina State University	$399,490		Document	NEET	FY2011
Pathway Aggregation in the Risk Assessment of Proliferation Resistance and Physical Protection (PR&PP) of Nuclear Energy Systems	The Ohio State University	$534,471		Document	MSTR	FY2011
Experimental Investigation of Convection and Heat Transfer in the Reactor Core for a VHTR	City College of New York	$1,118,856		Document	RCRD&D	FY2011
Preparation of High Purity, High Molecular-Weight Chitin from Ionic Liquids for Use as an Adsorbate for the Extraction of Uranium from Seawater	University of Alabama	$338,260		Document	MSTR	FY2011
Graphite Microstructural Characterization Using Time-Domain and Correlation-Based Ultrasonics	Johns Hopkins University	$1,199,997		Document	RCRD&D	FY2011
Selectivity in Ligand Binding to Uranyl Compounds: A Synthetic, Structural, Thermodynamic and Computational Study	University of California-Berkeley	$500,000		Document	MSTR	FY2011
Methodology Development for Passive Component Reliability Modeling in a Multi-Physics Simulation Environment	The Ohio State University	$533,457		Document	RCRD&D	FY2011
Development of Seismic Isolation Systems Using Periodic Materials	University of Houston	$538,154		Document	MSTR	FY2011
Pebble Fuel Handling and Reactivity Control for Salt-Cooled High Temperature Reactors	University of California, Berkeley	$612,721		Document	RCRD&D	FY2011
Innovative Elution Processes for Recovering Uranium from Seawater	University of Idaho	$400,000		Document	MSTR	FY2011
Self-Sustaining Thorium Boiling Water Reactors	University of California, Berkeley	$1,145,932		Document	RCRD&D	FY2011
Development of Austenitic ODS Strengthened Alloys for Very High Temperature Applications	University of Illinois-Urbana Champaign	$538,154		Document	MSTR	FY2011
High Fluency Low Flux Embrittlement Models of LWR Reactor Pressure Vessel Embrittlement and a Supporting Database from the UCSB ATR-2 Irradiation Experiment	University of California, Santa Barbara	$1,199,607		Document	RCRD&D	FY2011
Enhancement of the Extraction of the Uranium from Seawater	University of Maryland	$400,000		Document	MSTR	FY2011
A Research Program for Fission Product/Dust Transport in HTGR's	University of Missouri-Columbia	$1,157,367		Document	RCRD&D	FY2011
Transient Safety Analysis of Fast Spectrum TRU Burning LWR with Internal Blankets	University of Michigan	$599,475		Document	MSTR	FY2011
Development and Validation of a Lifecycle-based Prognostics Architecture with Test Bed Validation	University of Tennessee, Knoxville	$846,315		Document	RCRD&D	FY2011
Development of Novel Sorbents for Uranium Extraction from Seawater	University of North Carolina, Chapel Hill	$400,000		Document	MSTR	FY2011
In-situ Condition Monitoring of Components in Small Modular Reactors Using Process and Electrical Signature Analysis	University of Tennessee, Knoxville	$650,000		Document	RCRD&D	FY2011
Radiation Behavior of High-Entropy Alloys for Advanced Reactors	University of Tennessee, Knoxville	$538,159		Document	MSTR	FY2011
Technical Development for S-CO2 Advanced Energy Conversion	University of Wisconsin	$815,000		Document	RCRD&D	FY2011
Rapid Computer Aided Ligand Design and Screening of Precious Metal Extractants from TRUEX Raffinate with Experimental Validation	Washington State University	$500,000		Document	MSTR	FY2011
Ag Transport Through Non-Irradiated and Irradiated SiC	University of Wisconsin-Madison	$1,055,456		Document	RCRD&D	FY2011
Critical Heat Flux Phenomena at High Pressure and Low Mass Fluxes: Tests and Models	University of Wisconsin-Madison	$1,199,781		Document	RCRD&D	FY2011
Modeling and Test Validation of a Reactor Cavity Cooling System with Air	University of Wisconsin-Madison	$1,199,988		Document	RCRD&D	FY2011
Transient Mixed Convection Validation for NGNP	Utah State University	$635,860		Document	RCRD&D	FY2011
Alternative High-Performance Ceramic Waste Forms	Alfred University	$840,000	This project aims to advance fundamental understanding of the kinetics of structural evolution of crystalline ceramic waste forms. The structure/property relationships will be identified and will reveal new formulations, improved processing routes, and strategies for improved performance or ceramic waste forms.	Document	FCR&D	FY2012
Surface Layer Bulk Glass Interface Evolution with Aqueous Corrosion	Alfred University	$880,000	This project will investigate the links between the morphology, structure and chemistry of surface layer-bulk glass interface and the long-term corrosion-reaction kinetics using in-situ and ex-situ experiments. The understanding will result in improved models for long-term predictive behavior of high-level-waste (HLW) glasses under repository conditions.	Document	FCR&D	FY2012
Improved Accident Tolerance of Austenitic Stainless Steel Cladding through Colossal Supersaturation with Interstitial Solutes	Case Western Reserve University	$850,000	This project aims to develop new case-hardened austenitic stainless steels by saturating them with materials that improve their mechanical properties, corrosion resistance and radiation resistance. This project, if successful, will result in safer, longer-lasting, and more accident tolerant fuel claddings.	Document	FCR&D	FY2012
Optimization of Deep Borehole Systems for HLW Disposal	Massachusetts Institute of Technology	$850,000	Researchers aim to carry out a comprehensive evaluation of the deep borehole option for disposal of used nuclear fuel and high livel waste. The models developed will predict potential movement of water through natural and engineered barriers and release of radionuclides to the biosphere which will aide in site selection.	Document	FCR&D	FY2012
Scholarship for Nuclear Communications and Methods for Evaluation of Nuclear Project Acceptability	Massachusetts Institute of Technology	$800,000	Researchers will work to develop a model to characterize the factors affecting social acceptance of nuclear projects with potential stakeholders. The resultant model will strengthen the ability to design and implement large projects more efficiently, leading to higher rates of success of future nuclear projects.	Document	FCR&D	FY2012
Accurate Holdup Calculations with Predictive Modeling and Data Integration	North Carolina State University	$875,000	Researchers will develop and use state-of-the-art radiation transport codes to account accurately for the fissile material in a nuclear materials processing facility. An accurate estimation of the materials will allow for ensured radiological safety, security, waste management and efficient plant operation.	Document	FCR&D	FY2012
Novel Metal Sulfides to Achieve Effective Capture and Durable Consolidation of Radionuclides	Northwestern University	$760,000	Researchers will evaluate the effectiveness of chalcogenide based materials design novel metal sulfides to effectively capture and store of radioisotopes released during reprocessing of used nuclear fuel. This project will focus on understanding structure-property relationships to enable refined and direct synthesis approaches for improved and cost-efficient nuclear waste forms.	Document	FCR&D	FY2012
Nonlinear Ultrasonic Diagnosis and Prognosis of ASR Damage in Dry Cask Storage	Northwestern University	$885,000	Researchers aim to use nondestructive damage characterization methods to detect, manage and mitigate the degradation/damage mechanisms of dry cask storage systems for nuclear fuels. This project, if successful, will provide tools that will allow the prediction of the reliability and the safety of concrete structures in dry cask storage systems.	Document	FCR&D	FY2012
Prototype Demonstration of Gamma-Blind Tensioned Metastable Fluid Neutron/Multiplicity/Alpha Detector- Real Time Methods for Advanced Fuel Cycle Applications	Texas A&M University	$875,000	This project aims to create a prototype demonstration of a novel neutron/alpha detector based on a technology that is blind to gamma field used fuel. The prototype, if successful, will enhance instrumentation for monitoring real-time material balance during various stages of the nuclear cycle.	Document	FCR&D	FY2012
Testing of Sapphire Optical Fiber and Sensors in Intense Radiation Fields, when Subjected to Very High Temperatures	The Ohio State University	$885,000	The researchers on this project will investigate the performance of sapphire optical fibers and sensors in reactor environments. The project, if successful, will result in improved instrumentation to understand the behavior and predict performance of nuclear fuel systems at the microstructural level.	Document	FCR&D	FY2012
Concrete Materials with Ultra-High Damage Resistance and Self-Sensing Capacity for Extended Nuclear Fuel Storage Systems	University of California, Irvine	$800,000	Researchers aim to design a new class of multifunctional concrete materials. This project, if successful, will result in a novel multifunctional concrete material that possesses inherent degradation monitoring capability and is suitable for an extended storage system for the used nuclear fuel.	Document	FCR&D	FY2012
Development of Innovative Accident Tolerant High Thermal Conductivity UO2 Fuel Pellets with a Diamond Dopant	University of Florida	$800,000	Researchers will evaluate the use of diamond nanoparticles composite material in innovative accident tolerant fuel pellets. This could significantly improve both the thermal conductivity of fuel pellets and light water reactors' efficiency safety.	Document	FCR&D	FY2012
Probabilistic Multi-Hazard Assessment of Dry Cask Structures	University of Houston	$865,000	This project aims to investigate the performance of dry cask storage systems under multiple hazard systems (earthquake, tornados, combined with aging effects) using a probabilistic multi-hazard framework. This framework will be validated based on experimental research and will provide improved models for safety and reliability of spent nuclear fuels during storage and transportation.	Document	FCR&D	FY2012
Measurement of Irradiated Pyroprocessing Samples via Laser Induced Breakdown Spectroscopy	University of Idaho	$820,000	This project aims to use advanced characterization techniques to investigate microstructural changes and the micromechanisms related to irradiation induced damage in used nuclear fuels and waste forms. This project, if successful, will result in enhanced models to predict the structural and chemical response of used fuel and waster forms during interim storage and permanent disposal.	Document	FCR&D	FY2012
Elastic/Inelastic Measurement Project	University of Kentucky	$880,523	Researchers will measure nuclear data for elastic/inelastic scattered neutrons on coolants and structural materials. The data generated, will be useful for future R&D programs that will study innovative next generation LWR and future fast systems.	Document	FCR&D	FY2012
Electrochemical Corrosion Studies for Modeling Metallic Waste Form Release Rates	University of Nevada- Las Vegas	$790,000	This project aims to use advanced electrochemical methods to investigate the corrosion related degradation of metal alloys used for housing fission products. The data obtained from this study will allow for the prediction of the long-term behavior of the metallic host phase materials over geological time-scales.	Document	FCR&D	FY2012
Thermodynamic and Microstructural Mechanisms in the Corrosion of Advanced Ceramic Tc-bearing Waste Forms and Thermophysical Properties	University of Nevada- Las Vegas	$795,000	This project team will harvest thermodynamic and microstructural data on the evolution of ceramic based waste forms. The data will be used to advance the current state-of-the-art methodology used for isolation and stabilization of fission products and improve on nuclear fuel recycling processes.	Document	FCR&D	FY2012
Development and Experimental Benchmark of Simulations to Predict Used Nuclear Fuel Cladding Temperatures during Drying and Transfer Operations	University of Nevada- Reno	$745,000	Researchers will conduct experiments to investigate and develop advanced computational models of heat transfer in post-pool-storage drying operations. This project, if successful, will result in tools that can be used to design efficient drying processes to as to ensure suitability for dry-cask systems for long-term storage and transport.	Document	FCR&D	FY2012
Better Radiation Response and Accident Tolerance of Nanostructured Ceramic Fuel Materials?	University of Tennessee	$815,000	Researchers will use novel experimental methods to investigate the links between microstructure, phase stability and damage evolution in nanostructured ceramic fuel materials. The project will study fuel materials at temperatures and irradiation conditions relevant to operation and accidental scenarios.	Document	FCR&D	FY2012
Radiation and Thermal Effects on Used Nuclear Fuel and Nuclear Waste Forms	University of Tennesssee	$770,000	This project aims to investigate the structural and chemical response of used nuclear fuel and waste forms during interim storage and permanent disposal. If successful, this project will generate models that will allow the prediction of structural evolution and hence the radiological safety and security of nuclear fuel and waste forms.	Document	FCR&D	FY2012
Seismic Performance of Dry Casks Storage for Long-Term Exposure	University of Utah	$873,319	Researchers will evaluate the mechanical performance of dry-cask storage under seismic loading for mid-term operational periods. Simulations will include scenarios for freestanding, anchored, and vaulted casks. The experimental tests will also evaluate the dynamic seismic response of freestanding and anchored dry-cask storage prototypes, providing recommendations for optimal Interim Spent Fuel Storage Installations (ISFSIs) design.	Document	FCR&D	FY2012
Validation Experiments for Spent-Fuel Dry-Cask In-Basket Convection	Utah State University	$690,000	Researchers in this project aim to conduct experiments that generate data on natural convection through a fuel assembly. The data will be used to validate the computational models being developed for nuclear safety and design.	Document	FCR&D	FY2012
Re-Branding the Nuclear Fuel Cycle	Virginia Commonwealth University	$850,000	This project will create a comprehensive framework for the evaluation of alternative fuel cycle systems that will be used to identify and analyze key elements related to long-term management of nuclear fuels , with the ultimate goal to develop a communications strategy to reach stakeholders.	Document	FCR&D	FY2012
Advanced Characterization of Molecular Interactions in TALSPEAK-like Separations Systems	Washington State University	$875,000	Researchers will use advanced characterization techniques (experimental and computational) to improve understanding of the molecular level processes/interactions during separation processes for advanced fuel cycles. The understanding of these interactions will be used to develop more robust and streamlined separation processes for advanced fuel cycles.	Document	FCR&D	FY2012
Coupling of Nuclear Waste Form Corrosion and Radionuclide Transport in Presence of Relevant Repository Sediments	Washington State University	$885,000	Researchers will conduct experiments to understand the mechanisms responsible for the corrosion of nuclear waste forms in realistic chemical environments. The data generated from these experiments will enable increased reliability of the models used to predict the waste form performance in repository environments.	Document	FCR&D	FY2012
Stationary Liquid Fuel Fast Reactor (SLFFR) Concept for TRU Burning	Purdue University	$450,000	Reasearchers will investigate a new type of molten metallic fuel reactor concept that will consume hazardous transuranic waste. The liquid fuel alloy has several advantages over solid fuel fast reactors that are used for the same purpose.	Document	MSTR	FY2012
ABR for TRU Transmutation with Breed & Burn Thorium Blanket for Improved Economics and Resource Utilization	University of California- Berkeley	$450,000	The research team will use detailed neutronic analysis for a new Advanced Burner Reactor concept with low conversion ratio. The concept will use a new core shape to improve the utilization of neutrons to perform breed and burn.	Document	MSTR	FY2012
New Materials for High Temperature Thermoelecric Power Generation	University of California, Davis	$450,000	Reasearchers will work to develop nanostructured and other new materials to support the development of higher efficiency thermoelectric devices. These devices convert thermal energy to electricity with no moving parts. The new materials will operate at higher efficiencies and over a wider temperature range than those currently available--an important quality for future nuclear-powered deep space exploration.	Document	MSTR	FY2012
Microscopic Fuel Particles Produced by Self-Assembly of Actinide Nanoclusters on Carbon Nanomaterials	University of Notre Dame	$440,000	Reasearchers will develop the mechanisms, conditions and protocols to prepare uranium-carbon nanocomposite materials to make them more flexible. This could result in the generation of wholesale electricity, providing process heat, and providing power for households.	Document	MSTR	FY2012
High Hydrogen Content Graphene Hydride Compounds & High Cross-Section Cladding Coatings for Fast Neutron Detection	University of South Carolina	$430,000	This project will exploit recent breakthroughs to grow epitaxial graphene on commercial SiC wafers. This will allow researchers to develop a new detection method for fast neutrons. In addition, it will lead to better and more compact neutron detection system.	Document	MSTR	FY2012
Reducing Actinide Production Using Inert Matrix Fuels	University of Texas- Austin	$435,000	Reasearchers will perform a neutronic analysis, a thermal-hydraulic analysis and a simulation of fuel decay heat as a functionof fuel burnup, to determine if inert matrix fuel in coventional reactors will continue to be licensable. If successful, the inert matrix fuel mixtures will reduce harmful transuranic components in the fuel discharge streams at a level comparable to a fast reactcor burner.	Document	MSTR	FY2012
An Integrated Fuel Depletion Calculator for Fuel Cycle Options Analysis	University of Texas- Austin	$395,000	Reasearchers use new analysis techniques to better predict nuclear fuel behavior. The new model will allow improved fuel cycle for a larger number of users.	Document	MSTR	FY2012
Atomic-Scale to Meso-Scale Simulation Studies of Thermal Ageing and Irradiation Effects in Fe-Cr Alloys	Boston University	$874,997	Reasearchers will develop predictive, multi-scale simulation tools for iron-chromium alloys, which are expected to be key components of advanced steels envisioned as fuel cladding and structural components for Generation IV reactors. Such modeling is necessary to avoid resource intensive and costly thermal and neutron irradiation experiments to obtain required performance data.	Document	NEAMS	FY2012
Validation Data and Model Development for Fuel Assembly Response to Seismic Loads	George Washington University	$862,435	Reasearchers will conduct experiments that will provide comprehensive data characterizing the dynamics of the fluid and the structure in Pressurized Water Reactors (PWR) fuel assemblies under seismic loads (earthquakes and loss of coolant accidents). Completion of their project will greatly benefit the safety of existing and future nuclear reactors.	Document	NEAMS	FY2012
Uncertainty Quantification and Management for Multiscale Nuclear Materials Modeling	Georgia Institute of Technology	$743,444	Reasearchers will address the question of uncertainty propogation and error estimates associated with model prediction of material behavior under irradiation. Their work will facilitate a better understanding of the connection of various unit processes to collective responses in a multiscale model chain enabling the development of high strength and high ductility materials.	Document	NEAMS	FY2012
Fuel and Core Design Options to Overcome the Heavy Metal Loading Limit and Improve Performance and Safety of Liquid Salt Cooled Reactors	Georgia Insitute of Technology	$784,689	Reasearchers will examine new options for fuel and core designs in liquid salt cooled reactors where the current standard of TRISO type fuel has limitations due to loading characteristics. The research could enable new, more feasible fuel-core-reload options that will improve safety and performance parameters.	Document	RCRD&D	FY2012
Nonlinear Ultrasonic Techniques to Monitor Radiation Damage in RPV and Internal Components	Georgia Institute of Technology	$877,000	Reasearchers will explore new nondestructive materials evaluation and monitoring techniques utilizing nonlinear ultrasonic measurements . This technique will allow researchers to assess remaining useful life of select reactor components. Breakthroughs in this area will lead to the ability to characterize radiation damage in reactor pressure vessels and other components-leading to a clearer definition of reactor safety margins.	Document	RCRD&D	FY2012
Intergral Reactor Containment Condensation Model and Experimental Validation	Oregon State University	$871,119	Reasearchers will conduct experiments to enhance the safety and efficiency of small modular reactors (SMRs). This project will assess the impact of high-pressure steam condensation on steel containment vessels to be used for SMR deigns.	Document	RCRD&D	FY2012
Investigation of Natural Circulation Instability and Transients in Passively Safe Small Modular Reactors	Purdue University	$871,100	Reasearchers will perform scaled experiments to study the thermal-hydraulic instabilities that can occur in Small Modular Reactors (SMR) which rely on natural circulation cooling during normal operation and accident conditions. Their work will not only improve our understanding of general natural circulation instability but also lead to the development of stability criteria and predictability in the operation of SMRÃs.	Document	RCRD&D	FY2012
Thermoelectric-Driven Sustainable Sensing and Actuation Systems for Fault-Tolerant Nuclear Incidents	State University of New York, Stony Brook	$599,802	Reasearchers will examine the use of solid-state thermoelectric generators to produce electricity to sense and opeate during both normal and abnormal situations. This will provide indefinite monitoring of key components during power outages or station blackouts.	Document	RCRD&D	FY2012
Experimental and CFD Studies of Coolant Flow Mixing within Scaled Models of the Upper and Lower Plenums of NGNP Gas-Cooled Reactors	Texas A&M University	$713,051	Reasearchers will model the internal coolant flow of a prismatic core very high temperature reactor (VHTR) by using large eddy simulation tools. This method will enable more accurate prediction of flow field characteristics and better evaluation of VHTR behavior under operational and accidental conditions.	Document	RCRD&D	FY2012
Demonstrating Hybrid Heat Transport and Energy Conversion System Performance Characterization Using Intelligent Control Systems	University of Idaho	$877,000	Reasearchers will demonstrate an intelligent control systems in a hybrid energy conversion loop for a next generation nuclear power plant. Hybrid energy systems are a method of optimizing the use of natural resources for energy production. Hybrid systems present an opportunity to develop domestic energy sources to improve energy security.	Document	RCRD&D	FY2012
Advanced Reactor-Intermediate Heat Exchanger (IHX) Coupling: Theoretical Modeling and Experimental Validation	University of Idaho	$869,997	Reasearchers will model the behavior of the Advanced Reactor Intermediate Heat Exchanger Chemical Process system and develop advanced control techniques that take into account abnormal scenarios. The data and information obtained will assist in the development of intelligent control systems for next generation nuclear reactor systems.	Document	RCRD&D	FY2012
Irradiation Performance of Fe-Cr Base Alloys	University of Illinois- Urbana Champaign	$876,332	Reasearchers will perform post-radiation analysis and develop tools for future development and application of the Fe-Cr class of alloys. The results of this research will lead to better modeling of performance and development of an alloy designated as the primary choice for reactor fuel cladding and structural applications in advanced systems.	Document	RCRD&D	FY2012
Accelerated Irradiations for High Dose Microstructures in Fast Reactor Alloys	University of Michigan	$831,876	Reasearchers will determine the extent to which high dose rate irradiation can be used as an irradiation damage tool to understand microstructure evolution at high doses and temperatures relevant to advanced fast reactors. The project will provide fundamental understanding of the effectiveness of this process and thus of microstructure development in irradiated materials.	Document	RCRD&D	FY2012
Mitigating IASCC of Reactor Core Internals by Post-Irradiation Annealing Advanced Mitigation Strategies	University of Michigan	$876,985	Reasearchers will determine the optimum Post-irradiation annealing (PIA)-driven mitigation strategy to extend the potential lifetime of light water reactors. Samples that have already been irradiated in a light water reactor will be used to test PIA treatments to understand IASCC initiation and propoagation, annealing kinetics, the role of microstructure features in irradation hardening and localized deformation, and the optimum mitigation strategy based on PIA.	Document	RCRD&D	FY2012
Experimentally Validated Numerical Models for Effects of Non-Isothermal Turbulent Mixing on Wall Stresses in High Temperature Reactors	University of Pittsburgh	$876,422	Reasearchers will develop a comprehensive experimentally validated computational framework for the turbulent mixing in the lower plenum of a very high temperature reactor (VHTR). Through CFD modeling and experimental validation, the results from this project will lay the groundwork for future stress analysis, failure and fatigue studies, and uncertainty quantification for the VHTR system.	Document	RCRD&D	FY2012
Role of Defects in Swelling and Creep of Irradiated SiC	University of Wisconsin- Madison	$875,350	Reasearchers will study mechanisms controlling both radiation swelling and radiation creep in silicon carbide. These two effects are crucial to understanding the issues associated with the brittle silicon carbide composite. Success in this project will ground progress in the adoption of silicon carbide for reactor solutions, particularly as fuel cladding.	Document	RCRD&D	FY2012
Advanced Supercritical Carbon Dioxide Brayton Cycle Development	University of Wisconsin, Madison	$877,000	Reasearchers will investigate the benefits of utilizing advanced Brayton cycles with supercritical carbon dioxide in new reactor systems and components. Benefits of this research include improvement of analysis and performance of components currently utilizing these cycles as well as the potential for a large scale advanced CO2 power system.	Document	RCRD&D	FY2012
Mechanical Behavior of UO2 at Sub-grain Length Scales: Quantification of Elastic, Plastic and Creep Properties via Microscale Testing	Arizona State University	$800,000	Reasearchers will develop techniques to measure properties at sub-grain scales using depleted Uranium Oxide samples. The project will provide a framework to measure sub-grain scale mechanical properties, as well as provide experimental data to improve the understanding of advanced oxide fuels.	Document	FCR&D	FY2013
The Impacts of Pore-Scale Physical and Chemical Heterogeneities on the Transport of Radionuclide-Carrying Colloids	Colorado School of Mines	$800,000	Reasearchers will identify the dominant transport mechanisms to develop models that predict radionuclide distribution in porous materials. Experimental and computational models will be created that couple pore-scale geometric and interfacial structures. Simulators such as these are a necessary step towards fully predictive models for field-scale applications in the future.	Document	FCR&D	FY2013
Recovery of Uranium from Seawater: Polymer-Supported Aminophosphinates as Selective Extractants	Hunter College, CUNY	$399,999	Reasearchers will prepare a polymer-supported extractant for the recovery of uranium from seawater. The project will focus on primary amines that could provide a 3-fold increase in uranium capture capacity than current methods.	Document	FCR&D	FY2013
In-pile Thermal Conductivity Characterization with Single-laser Heating/Time Resolved Raman	Iowa State University	$800,000	Reasearchers will develop a time-resolved Raman-based thermal conductivity measurement system to improve remote in-pile thermal conductivity measurement. These measurements will provide new insights into the behavior of materials exposed to extreme radiation and temperature environments. Understanding the behavior of materials at the microstructural level will support optimized fuel designs.	Document	FCR&D	FY2013
Organic Speciation and Interactions in ALSEP - One Step Partitioning Process of Minor Actinides, Lanthanides, and Fission Products	Oregon State University	$600,000	Reasearchers will investigate the Actinide-Lanthanide Separation (ALSEP) process organic phase prior to aqueous phase separation and after aqueous separation phases of bare and metal-loaded acids. Quantifying these effects can be used to determine how an engineering scale process will perform and generate an accurate chemical model for the system.	Document	FCR&D	FY2013
Glass Composition and Solution Speciation Effects on Stage III Dissolution	Pennsylvania State University	$700,000	Reasearchers will study the chemical and structural triggers of long-term vitrified nuclear waste form behavior. They will study a range of waste glass compositions in corrosive environments. The study will improve understanding of the long-term residual rate and may provide new options for environmental control of glass dissolution rates.	Document	FCR&D	FY2013
Correlating Thermal, Mechanical, and Electrical Coupling Based Multiphysics Behavior of Nuclear Materials Through In-Situ Measurements	Purdue University	$800,000	Reasearchers will use in-situ experimental techniques to monitor the influence of extreme conditions on fuel cladding. The project will establish an in-situ experimental setup that can predict change in thermal properties and their correlation with mechanical properties and correlate such changes to changes in microstructural and chemical features.	Document	FCR&D	FY2013
Creation of a Geant4 Muon Tomography Package for Imaging of Nuclear Fuel in Dry Cask Storage	Purdue University	$440,000	Reasearchers will develop a simulation and analysis package to aid in the non-destructive assessment of sealed used nuclear fuel dry casks using cosmic ray muons. Cosmic ray muon tomography allows for non-destructive assessment that can independently verify and identify weapons grade material sealed within dense dry casks.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Two-stage Fast Reactor Fuel Cycle Options for Optimum Resource Utilization and Waste Management	Purdue University	$400,000	Reasearchers will evaluate the two different two-stage fast reactor fuel cycle options that will offer efficient use of uranium resources and the ability to burn actinides and long-live fission products. Evaluation of these fast fuel cycle options will serve as a useful complement to the options currently being considered in the Fuel Cycle Options Campaign.	Document	FCR&D	FY2013
Mixed Metal Phosphonate-Phosphate Resins for Separation of Lanthanides from Actinides	Texas A&M University	$650,000	Reasearchers will use ion exchangers to cleanly separate lanthanides and curium from reusable actinides. The study will assist in the development of an inexpensive, simple way in which to separate lanthanides from actinides found in used nuclear fuel rods and to recover a large portion of the usable fuel.	Document	FCR&D	FY2013
Safeguards in Pyroprocessing: an Integrated Model Development and Measurement Data Analysis	The Ohio State University	$626,151	Reasearchers will develop a comprehensive and effective safeguards approach for a pyroprocessing facility to support safeguards for future fuel cycles in the United States. The new approach and design will focus directly on the special nuclear materials in the electrorefiner where actinides are separated from fission products through electrochemical process.	Document	FCR&D	FY2013
Using Ionic Liquids for the Development of Renewable Biopolymer-Based Adsorbents for the Extraction of Uranium from Seawater and Testing Under Marine Conditions	University of Alabama	$400,000	Reasearchers will explore the fundamental engineering parameters for a renewable high-performance adsorbent for the extraction of uranium from sweater based on a recently proven ionic liquid (IL)-chitin platform. The project will use the platform to develop a versatile, modifiable adsorbent and characterize its performance and degradation in marine conditions.	Document	FCR&D	FY2013
Developing Ultra-Small Scale Mechanical Testing Methods and Microstructural Investigation Procedures for Irradiated Materials.	University of California, Berkeley	$800,000	Reasearchers will develop new small-scale mechanical testing techniques to allow for the estimation or direct measurement of bulk properties. The combined experiments and modeling will significantly enhance the statistics and information that can be obtained on small radioactive archived samples, as well as new ion beam irradiated specimens.	Document	FCR&D	FY2013
Improved Delayed-Neutron Spectroscopy Using Trapped Ions	University of California, Berkeley	$400,000	Reasearchers will develop innovative spectroscopy techniques to measure the decay of fission fragments. The resulting data from these new techniques will be used to better understand reactor kinetics under accident conditions and failure scenarios.	Document	FCR&D	FY2013
Thermally and Chemically Responsive Nanoporous Materials for Efficient Capture of Fission Product Gases	University of California, Davis	$750,000	Reasearchers will create new nanoporous materials that will be highly effective at capturing fission product gases. These materials would be relevant to both reactor fuels applications and reprocessing operations. Tests will be performed in carbon based and nitride based nanostructures, with the most promising materials from the modeling perspective undergoing further testing.	Document	FCR&D	FY2013
Multiphase Nanocrystalline Ceramic Concept for Nuclear Fuel	University of California, Irvine	$800,000	Researchers will study the use of nanoparticles and nanostructured ceramics to create new materials that can extend the service life and increase efficiency for nuclear fuel. Multiphase nanocrystalline ceramics will be used to design simulated nuclear fuel that can provide added plasticity, better radiation tolerance and improved thermal conductivity.	Document	FCR&D	FY2013
Development of Novel Porous Sorbents for Extraction of Uranium from Seawater	University of Chicago	$400,000	Reasearchers will develop a highly porous sorbent for the extraction of uranium from seawater. Previous research has established sorbent performance. This project will use past foundational studies to design and investigate a new nanocomposites that will be processed into tacks or braids for field tests in seawater tests. The technology may also be used for other metals.	Document	FCR&D	FY2013
Microwave Readout Techniques for Very Large Arrays of Nuclear Sensors	University of Colorado, Boulder	$799,937	Reasearchers will develop a powerful readout technique based on microwave transmission and reflection. The technique will enable very large arrays of diverse sensor types for nuclear materials quantification and tracking. It will provide more accurate data on material composition and quantity.	Document	FCR&D	FY2013
BiI3 Gamma-Ray Spectrometers for Reliable Room-Temperature Nuclear Materials Safeguarding	University of Florida	$799,999	Reasearchers will develop gamma-ray spectrometers based on BiI3 single crystals for MPACT applications such as burnup validation quantification, improved assay of plutonium, determination of uranium enrichment and overall monitoring spent fuel within the fuel cycle. The project will improve energy resolution, efficiency and environmental performance with this new gamma-ray detector.	Document	FCR&D	FY2013
Innovative Coating of Nanostructured Vanadium Carbide on the F/M Cladding Tube Inner Surface for Mitigating the Fuel Cladding Chemical Interactions	University of Florida	$760,276	Researchers will develop barrier coatings on the inner surface of fuel cladding tubes to improve performance of materials at elevated temperatures and high neutron exposures in fast reactors. The project will develop and test a low temperature coating process of nanostructured vanadium carbide that will provide a benchmark for use in future studies.	Document	FCR&D	FY2013
Doubling the Life of Concrete Structures	University of Idaho	$800,000	Reasearchers will use nanoscale techniques to develop methods for doubling the service life of concrete structures. They will study the effect of temperature load and temperature cycling (freezing and thawing) on the durability of concrete with nanoscale viscosity modifiers. The project will benefit from non-destructive evaluation of concrete performance through electrochemical techniques.	Document	FCR&D	FY2013
Off-Gas Treatment: Evaluation of Nano-structured Sorbents for Selective Removal of Contaminants	University of Idaho	$785,910	Reasearchers will evaluate nanostructured sorbent materials for their effectiveness in removing and immobilizing radionuclides for the off-gas treatment from used nuclear fuel recycling operations. The project aims at achieving near-zero emissions of radionuclides by capturing them from the off-gas of recycling operations, allowing for the development of advanced fuel cycles.	Document	FCR&D	FY2013
Innovative Elution Processes for Recovering Uranium and Transition Metals from Amidoxime-Based Sorbents	University of Idaho	$399,864	Reasearchers will develop a new two-step elution process to achieve total recovery of uranium and effective recycling of the sorbent. The extraction process would selectively remove uranium from the sorbent with little or no damage. The process would then remove transition metals and regenerate the sorbent for repeated use, making uranium extraction from seawater economically viable.	Document	FCR&D	FY2013
Performance of a Steel/Oxide Composite Waste Form for Combined Waste Streams from Advanced Electrochemical Processes over Geologic Time Scales	University of Illinois at Chicago	$700,000	Reasearchers will develop and validate a mechanistically-based corrosion model for cermet-type waste forms, creating a testing protocol and modeling approach for predicting long-term performance. The study will apply novel electrochemical testing and modeling methods to the behavior of metal/oxide phase boundaries to evaluate waste form performance.	Document	FCR&D	FY2013
Enhancement of the Extraction of Uranium from Seawater	University of Maryland, College Park	$400,000	Reasearchers will develop and optimize novel adsorbents for uranium recovery from seawater. The team will use radiation-induced grafting of organic phosphates onto polymers. The experiments will use ocean water, with mechanistic analysis, to provide a solid basis for large-scale demonstration of the performance of the new adsorbents in ocean environments.	Document	FCR&D	FY2013
Improving the Understanding of the Coupled Thermal-Mechanical-Hydrologic Behavior of Consolidating Granular Salt	University of New Mexico	$800,000	Reasearchers will increase the understanding of granular salt seal materials for shafts, drifts and boreholes. By coupling thermal, mechanical and hydrological responses, the study will result in greater confidence in granular salt consolidation as a principal strategy for closure and isolation of long-term waste repositories.	Document	FCR&D	FY2013
Fission Fragment Yield Data in Support of Advanced Reactor Technology	University of New Mexico	$399,816	Reasearchers will produce a highly accurate data set for thermal fission. These precision data are necessary for high-accuracy simulations of nuclear criticality, transmutation rates, radiation effects and heating as well as for nuclear fuel, material accounting and identification needs.	Document	FCR&D	FY2013
Molecular dynamics-based simulations of bulk/interfacial structures and diffusion behaviors in nuclear waste glasses	University of North Texas	$700,000	Reasearchers will generate accurate atomic structural models for use in Monte Carlo simulations of the dissolution of nuclear waste glasses. Large-scale molecular dynamics-based computer simulations will be used to investigate self-diffusion behaviors, interfacial structure, and other structures formed during dissolution of these glasses.	Document	FCR&D	FY2013
U3Si2 Fabrication and Testing for Implementation into the BISON Fuel Performance Code	University of South Carolina	$800,000	Reasearchers will fabricate, test and model a high uranium density, advanced nuclear fuel that operates at a much lower temperature and stores less energy. The work will deliver key research data on creep and grain growth, improving economics, through possible power uprates, and advancing accident tolerant fuels research.	Document	FCR&D	FY2013
Structural Health Monitoring of Nuclear Spent Fuel Storage Facilities	University of South Carolina	$738,618	Reasearchers will develop a nuclear structural health monitoring system based on a sensing technology that monitors material degradation and aging for dry cask storage systems. The low-cost, low-profile sensors will perform on-demand monitoring of the structural integrity of individual components as well as the entire system.	Document	FCR&D	FY2013
ORIGEN-based Nuclear Fuel Depletion Module for Fuel Cycle Assessment	University of Tennessee at Knoxville	$755,181	Reasearchers will develop a flexible reactor analysis module for the CYCLUS fuel cycle simulator based on established tools for reactor fuel depletion and decay. They will use ORIGEN, a mature and experimentally validated code, affording greater flexibility and allowing for accurate evaluations of impacts of both present and future fuel cycle options.	Document	FCR&D	FY2013
Cost and System Analysis of Innovative Fuel Resources Concepts	University of Texas at Austin	$295,960	_This project will develop and test braided polymer fiber adsorbents that surpass the sorption capacity, selectivity and durability of the best existing technology to recover uranium from seawater.	Document	FCR&D	FY2013
Risk Assessment of Structural Integrity of Transportation Casks	University of Utah	$789,296	Reasearchers will assess the loss of structural integrity of transportation casks and fuel cladding after extended storage. This risk assessment will conduct experimental tests and simulations to evaluate the structural performance of fuel, fuel assemblies and cask components when subjected to vibration and impact loads during transport.	Document	FCR&D	FY2013
Market-Based and System-Wide Fuel Cycle Optimization	University of Wisconsin, Madison	$612,731	Reasearchers will create market and economic optimizers to improve calculations for the CYCLUS fuel cycle simulator. The team will leverage existing optimization software frameworks within the simulator to resolve top level policy questions. The optimizations will allow CYCLUS to move beyond static material compositions, providing a holistic view of the fuel cycle system.		FCR&D	FY2013
Optical Fiber Based System for Multiple Thermophysical Properties for Glove Box, Hot Cell and In-Pile Applications	Utah State University	$799,975	Reasearchers will use a small pressure vessel to develop a robust technique for the measurement of multiple thermophysical properties at very high temperatures. The technique will lead to a system design moving toward the eventual measurement of irradiated fuels in a glovebox and/or hot cell with all sensors and electronics outside of the glovebox and/or hot cell.	Document	FCR&D	FY2013
Development of a Nano-Modified Concrete for Next Generation of Storage Systems	Vanderbilt University	$796,268	Reasearchers will use nano-sized and nano-structured particles based on enhanced reactivity to develop a superior concrete for the long-term storage of used nuclear fuel. The project will use state-of-the-art experimental chemical and mechanical characterizations and computation analysis to assess the performance of nano-modified concretes.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Thorium Fuel Cycle Options	Vanderbilt University	$797,995	Reasearchers will develop six fuel cycle data packages for multi-stage, thermal fuel cycles which incorporate thorium. These new fuel cycle data packages will provide the opportunity to examine fuel cycle options beyond those which have traditionally been considered. A thorium fuel cycle database will also be assembled as a basis for thorium literature for future evaluations of the thorium fuel cycle.	Document	FCR&D	FY2013
Enhanced Shielding Performance of HLW Storage Packages via Multi-Component Coatings	Virginia Polytechnic Institute and State University	$796,947	Reasearchers will develop a multi-layer composite that will enhance long-term storage and facilitate safe transport of storage packages. This novel multi-layer, multi-component coating would create an outer shield material that is resistant to the corrosion, radiation, diffusion and thermal cycling processes that affect fuel packages during long term storage.	Document	FCR&D	FY2013
Managing Zirconium Chemistry and Phase Compatibility in Combined Process Separations for Minor Actinide Partitioning	Washington State University	$700,000	Reasearchers will address unique challenges for combining TRUEX and TALSPEAK processes for partitioning of lanthanides and minor actinides. The project will develop improved information on the thermodynamics of fission product zirconium and develop a framework for an organic phase solvation model. Combined process development could streamline separations processes.	Document	FCR&D	FY2013
Advances in the Recovery of Uranium from Seawater: Studies Under Real Ocean Conditions	Woods Hole Oceanographic Institution	$398,882	Reasearchers will provide infrastructure and expertise for marine testing of currently available adsorbents in real ocean conditions. The team will move adsorbent research from the lab to field testing in order to quantify sorptive properties and uranium uptake. The project will provide valuable field data that will show the potential of large scale applications of these technologies.	Document	FCR&D	FY2013
NEUP Project 20-19172: Irradiation of Sensors and Adhesive Couplants for Application in LWR Primary Loop Piping and Components		$497,881	Reasearchers paln to attach ultrasonic transducers to substrates using various adhesive couplants that will be irradiated at elevated temperature to simulate LWR primary loop conditions at the PULSTAR reactor at North Carolina State University. Ultrasonic data will be taken in-situ. Subsequently, the sensors and couplant interfaces will be characterized using the LAMDA facility at ORNL. The results will be used to benefit a parallel EPRI project on online monitoring of cracks in LWR primary loop piping._	Document	R&D NSUF	FY2013
NEUP Project 20-19404: Extension of MSTDB to Provide a High-Quality, Validated Thermochemical Database for Predicting/Simulating Corrosion in Molten Salt Reactor SystemsUniversity of South Carolina		$600,000	Reasearchers will generate a validated, consistent database of initial fuel compositions and potential corrossion products of fluoride and chloride salts, allowing for important phenomena predictions in molten salt reactors to guide confident decisions. The database will be integral to the currently being developed Molten Salt Thermochemical Database (MSTDB), structured to allow use by commercial and open source codes._	Document	NEAMS	FY2013
Lower Length Scale Characterization and Validation of Formation and Stability of Helium Bubbles in Nano-structured Ferritic Alloys under Irradiation	Clemson University	$399,870	Reasearchers will provide a fundamental knowledge about the formation and stability of ultra-fine helium bubbles within 14YWT after neutron/ion irradiation for further design of new advanced structural materials with a characteristic high density nanoparticles feature which can increase the mechanical strength, hardness, irradiation resistance and the operational temperature range of materials.	Document	NEAMS	FY2013
Three-Dimensional Fuel Pin Model Validation by Prediction of Hydrogen Distribution in Cladding and Comparison with Experiment	Pennsylvania State University	$800,000	Reasearchers will validate important three-dimensional aspects of the fuel pin modeling by using specialized numerical modeling techniques coupled with laboratory experiments to validate existing models for predicting fuel performance in light water reactors.	Document	NEAMS	FY2013
Collocation-Based Surrogate Models for Uncertainty Quantification and Validation of Coupled, Multiphysics Fuel Performance Simulation Tools	University of Michigan	$596,835	Reasearchers will provide the necessary high fidelity, coupled, multiphysics fuel performance simulator for computational modeling and develop surrogates which will accelerate and focus the validation of the coupled codes. This will be achieved by utilizing the high fidelity coupled fuel performance, thermal-hydraulics and neutronics codes BISON/STAR-CCM+/MPACT and an innovative collocation-based surrogate methodology.	Document	NEAMS	FY2013
Multi-Resolution In-Situ Testing and Mutliscale Simulation for Creep Damage Fatigue Damage Analysis of Alloy 617	Arizona State University	$800,000	This project will develop novel testing and experimentally validated prediction methodologies for micro-structural damage mechanisms of structural materials for advanced reactor systems. The investigations will focus on the characterization and testing of specific metal alloys, but the proposed testing and life-prediction methodologies are applicable to other structural materials as well.	Document	RCRD&D	FY2013
Novel High Temperature and Radiation Resistant Infrared Glasses and Optical Fibers for Sensing in Advanced Small Modular Reactors	Clemson University	$800,000	Clemson University, in partnership with the Iowa State University and the Pacific Northwest National Laboratory, will develop novel optical materials with improved heat and radiation exposure resistance in order to enable in-vessel fiber optic sensing for advanced Small Modular Reactors.	Document	RCRD&D	FY2013
Validation Data Acquisition in HTTF during PCC Events	George Washington University	$800,000	Reasearchers at the George Washington University and Oregon State University will collaborate with NASA Langley Research Center to measure flow velocities in a high temperature test facility. This work supports the development of very-high temperature reactors with passive safety systems.	Document	RCRD&D	FY2013
Advanced High Temperature Inspection Capabilities for Small Modular Reactors	Iowa State University	$790,822	The objective of this project is to develop non-destructive evaluation techniques for advanced small modular reactors. The research will provide key enabling inspection technologies needed to support the design and the reactor component performance validation process for advanced small modular reactors.	Document	RCRD&D	FY2013
Experimental and Computational Investigations of Plenum-to-Plenum Heat Transfer under Natural Circulation in a Prismatic Very High Temperature Reactor	Missouri University of Science and Technology	$799,999	Reasearchers will perform experimental and computational investigations to study heat transfer and natural circulation phenomena in very-high temperature reactors. The study will assist in the ability to predict and analyze passive safety systems.	Document	RCRD&D	FY2013
New Mechanistic Models of Creep-Fatigue Crack Growth Interactions for Advanced High Temperature Reactor Components	Oregon State University	$790,790	Reasearchers will create and validate a robust, multi-scale, numerical model to predict material degradation in nickel-based reactor alloys. If successful, this project will provide better numerical tools for reactor designers and greatly improve their capability to design against material failures for reactor alloys in the long term.	Document	RCRD&D	FY2013
Self-Powered Wireless Dual-mode Langasite Sensor for Pressure/Temperature Monitoring of Nuclear Reactors	State University of New York, Stony Brook	$800,000	This research will develop a novel self-powered wireless hybrid sensor that can accurately monitor both pressure and temperature using a single device without requiring external electricity, even in extreme harsh environments.	Document	RCRD&D	FY2013
Compact Heat Exchanger Design and Testing for Advanced Nuclear Reactors and Advanced Power Cycles	The Ohio State University	$800,000	The goal of this project is to investigate optimal heat exchanger designs for advanced reactors. The research will study the optimization of printed circuit heat exchangers for specific fluids under a variety of conditions as well as perform numerical modeling. Experiments will focus on thermal performance and heat stress during extreme conditions.	Document	RCRD&D	FY2013
Fundamental Understanding of Creep-Fatigue Interactions in 9Cr-1MoV Steel Welds	The Ohio State University	$798,000	This project will advance the state of knowledge and fundamental understanding of deforming materials and welds under loading conditions. Specifically, new integrated testing procedures will be evaluated and applied for conditions that are most detrimental to material stability leading to improved predictions of life expectancy for reactor steels and welds.	Document	RCRD&D	FY2013
Advanced Mechanistic 3D Spatial Modeling and Analysis Methods to Accurately Represent Nuclear Facility External Event Scenarios	The Ohio State University	$800,000	Reasearchers will develop three-dimensional characterization uncertainty analysis for commercial power plants. The project will involve combining experts from the fields of seismic structural modeling and advanced methods of risk assessment. This effort is expected to result in next generation tools that can be used for assessment of seismic risks.	Document	RCRD&D	FY2013
Tritium Mitigation/Control for Advanced Reactor Systems	The Ohio State University	$400,000	Reasearchers will develop a fluoride salt cooled high-temperature reactor featuring a specialized system to control tritium production. If successful, this will result in a significant reduction in size and cost in comparison to other reactor designs.	Document	RCRD&D	FY2013
A Pebble-Bed Breed and Burn Reactor	University of California, Berkeley	$400,000	Reasearchers will assess the feasibility of designing a type of metal cooled reactor able to establish and maintain operation when fueled with depleted uranium. If successful, this reactor will offer at least a 30-fold increase in the uranium ore utilization versus that achieved in contemporary light water reactors without the need for fuel reprocessing and recycling.	Document	RCRD&D	FY2013
Investigation of Thermal Aging Effects on the Evolution of Microstructure and Mechanical Properties of Cast Duplex Stainless Steels	University of Maryland, College Park	$799,966	This research will provide a better understanding of the microstructural evolution and simultaneous change in mechanical response during aging. The results of the research will provide data that can be used to estimate degraded mechanical properties for an 80-year service life of light water reactors.	Document	RCRD&D	FY2013
Model validation using CFD-grade experimental database for NGNP Reactor Cavity Cooling Systems with water and air	University of Michigan	$799,348	Reasearchers will use advanced innovative instrumentation to build a high-resolution experimental database and to use the novel experimental data to assess and further develop the predictive capabilities of computer codes for thermal hydraulics and computational fluid dynamics. The improved models developed by this project will also have the direct benefit of improving the predictive capability of the passive systems of third generation light water reactors and small modular reactor systems.	Document	RCRD&D	FY2013
Long-Term Prediction of Emissivity of Structural Material for High Temperature Reactor Systems	University of Missouri	$799,117	Reasearchers will study specific types of emissivity driven cooling from a variety of materials that are relevant to nuclear reactors. The research will provide a basis for numerical modeling to support reactor development.	Document	RCRD&D	FY2013
Advanced I&C for Fault-Tolerant Supervisory Control of Small Modular Reactors	University of Pittsburgh	$800,000	The purpose of this research is to develop advanced instrumentation and control techniques for supervisory control of advanced small modular reactors. This research supports the operational goals of small modular reactor concepts through the development of improved oversight and surveillance techniques.	Document	RCRD&D	FY2013
Corrosion of Structural Materials for Advanced Supercritical Carbon-Dioxide Brayton Cycle	University of Wisconsin-Madison	$798,672	Reasearchers will study a variety of materials for corrosion resistance under conditions that improve power conversion. In addition to studying the corrosion resistance of the materials, researchers will study the effect of additives to mitigate corrosion. Development of corrosion theories and modeling aimed at prediction of long-term corrosion will be the underlying theme throughout the project.	Document	RCRD&D	FY2013
Component and Technology Development for Advanced Liquid Metal Reactors	University of Wisconsin-Madison	$798,920	In support of liquid metal cooled reactors, the University of Wisconsin, Madison will evaluate advanced alloys and ceramics that come in contact with liquid metals. Additionally, a robust oxygen sensor and for use in liquid metals will be developed in order to better evaluate corrosion profiles in support of diagnostic testing.	Document	RCRD&D	FY2013
A New Paradigm for Understanding Multi-phase Ceramic Waste Form Performance	Clemson University	$800,000	Researchers will use advanced characterization tools to develop 3-D microstructural data that can be incorporated into computer-based simulations in order to predict the performance of waste forms. Materials system modeling will incorporate elemental release and the interconnected microstructural network of phases to better understand performance and degradation, which will accelerate waste form acceptance in repository settings.	Document	FCR&D	FY2014
Controlling Hexavalent Americium: A Centerpiece to a Compact Nuclear Fuel Cycle	Colorado School of Mines	$800,000	Researchers will develop and exploit the fundamental chemistry of Americium to enable an industrially viable means to co-recover the major and minor actinide elements from used nuclear fuel. The results would be a significant step forward in the development of aqueous separations approaches designed to recover the U-Am actinides based on the availability of the hexavalent oxidation state.	Document	FCR&D	FY2014
Zeolite Membranes for Krypton/Xenon Separation from Spent Nuclear Fuel Reprocessing Off-Gas	Georgia Institute of Technology	$400,000	Researchers will develop a high-performance, lower-cost zeolitic membrane process for Kr/Xe separations during spent nuclear fuel processing. Current separation methods are not considered economical and a membrane process would have relatively lower cost, equipment size, and ambient operating temperature. The process would form a sound basis for further development of this transformative separation technology for the nuclear fuel cycle.	Document	FCR&D	FY2014
Optimizing Polymer-Grafted Amidoxime-based Adsorbents for Uranium Uptake from Seawater	Georgia Institute of Technology	$399,999	Researchers will work to increase the adsorbent capacity and selectivity toward uranium by optimizing the adsorbent morphology, synthesis variables, and conditioning parameters and by investigating the rate-limiting variables through transport and reaction modeling. A novel adsorption/partition concept that has the potential to substantially increase the adsorbent capacity will be tested, making uranium from seawater extraction more economically viable.	Document	FCR&D	FY2014
Extraction of Uranium from Seawater: Design and Testing of a Symbiotic System	Massachusetts Institute of Technology	$400,000	Researchers will develop a seawater uranium extraction system that will work symbiotically with an offshore windmill by utilizing the structure, mooring and power of the windmill, while increasing the energy harvested by the installation. Uranium will be extracted by an adsorbent polymer belt, which will be cycled through the seawater and an elution plant located at the base of the windmill tower. Increasing the frequency of harvesting could overcome current economic barriers to seawater uranium extraction.	Document	FCR&D	FY2014
Imaging a Dry Storage Cask with Cosmic Ray Muons	Oregon State University	$799,871	Researchers will develop an imaging system to monitor the content of a dry storage cask with cosmic ray muons. A very large amount of plutonium under nuclear safeguards is contained in used fuel assemblies stored in dry storage casks. Muon imaging will allow a cost effective and reliable way to evaluate dry storage cask content and integrity before transport.	Document	FCR&D	FY2014
Apatite and sodalite based glass-bonded waste forms for immobilization of 129I and mixed halide radioactive wastes	Rutgers University	$800,000	Researchers will develop advanced and chemically durable waste forms for immobilizing 129I (aqueous based reprocessing of fuel) and mixed-halide wastes (molten-salt processing of fuel) by low temperature synthesis. Halide-containing sodalite and calcium phosphate-based apatite minerals will be synthesized, consolidated and tested for chemical durability. The project will provide needed baseline data for the development of advanced waste forms for immobilization of iodine and mixed-halide wastes.	Document	FCR&D	FY2014
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$350,000	Researchers will develop modeling tools supported by experiments for off-gas capture from future nuclear-fuel recycling facilities. Target species include tritium, iodine, krypton, and xenon. The models are intended to provide path forward recommendations to develop off-gas treatment adsorption processes. The project will contribute to the evaluation of options for environmentally acceptable recycle systems.	Document	FCR&D	FY2014
Development of high performance ODS alloys	Texas A&M University	$800,000	Researchers will study swelling, radiation hardening and changes in mechanical properties of ODS alloys to develop two sets of advanced ODS alloys. Two sets of first-round candidate alloys that have already undergone extensive development and testing will evaluate irradiation performance. The study will meet the need for high strength, radiation-tolerant cladding and core components that have enhanced resistance to void swelling.	Document	FCR&D	FY2014
Rare Earth Electrochemical Property Measurements and Phase Diagram Development in a Complex Molten Salt Mixture for Molten Salt Recycle	The Ohio State University	$800,000	Researchers will investigate rare earth (RE) properties in complex molten salt mixtures. In a molten salt recycle approach, the RE drawdown by electrolysis is a key step in which REs are separated from salt containing other fission products. Investigation of RE electrolysis must consider the electrochemical properties of the REs. We propose to conduct studies of detailed experiments and corresponding models to provide the physical properties and phase diagrams required to predict the performance of RE drawdown for processing complex molten salts.	Document	FCR&D	FY2014
Studies of Lanthanide Transport in Metallic Nuclear Fuels	The Ohio State University	$800,000	Researchers will study the redistribution of lanthanides and migration of lanthanides to the fuel surface. The mechanisms of lanthanide transport in metallic fuel based on the novel discovery of a Ôliquid-likeÕ transport mechanism will be studied analytically and experimentally. The project will develop a fundamental understanding of lanthanide fission product migration and redistribution in advanced metallic nuclear fuels, and theory and data to mitigate fuel-cladding chemical interactions.	Document	FCR&D	FY2014
Computational and Experimental Studies of Microstructure-Scale Porosity in Metallic Fuels for Improved Gas Swelling Behavior	University of Arkansas	$796,823	Researchers will study the microstructure of metallic uranium alloy fuels, and their resistance to densification, to minimize in-pile irradiation swelling through bimodal pore size distribution. The project will develop a predictive approach to design metallic fuel microstructures for optimal swelling resistance and fission gas retention.	Document	FCR&D	FY2014
Improved Hybrid Modeling of Spent Fuel Storage Facilities	University of California, Berkeley	$645,393	Researchers will develop a variance reduction method for computational transport that will improve the ability to design and operate monitoring systems for interim used fuel installations through enhanced modeling and simulation. This new tool will demonstrate that modeling calculations can be done more accurately in less time than with current tools and will perform studies characterizing how changes in material, cask configurations, and number of casks could impact monitoring systems.	Document	FCR&D	FY2014
Selective ligands for uranyl via combinatorial peptoid libraries: A synthetic, structural, thermodynamic and computational study	University of California, Berkeley	$400,000	Researchers will study how donor ligands bind to the uranyl ion, UO22+, with the longer-term goal of using this information to tackle selective recognition of uranyl in aqueous solution. The study will impact underlying approaches to controlling the behavior of uranium in these systems. The actinide separation technology could be used in several areas including uranium extraction from seawater, nuclear waste remediation and nuclear materials.	Document	FCR&D	FY2014
Combining Experiments and Simulations of Extraction Kinetics and Thermodynamics in Advanced Separation Processes for Used Nuclear Fuel	University of California, Irvine	$799,938	Researchers will study how the kinetics and thermodynamics of metal ion extraction in advanced separation processes for used nuclear fuel can be described by molecular dynamic (MD) simulations and how the simulations can be validated by experimental data. The project would have broad impacts on several separations processes including advanced TALSPEAK, ALSEP and GANEX by increasing the confidence and accuracy of computer modeling of metal ion extraction._	Document	FCR&D	FY2014
Effect of Metallic Li on the Behavior of Metals in Molten Salts	University of Nevada, Reno	$458,250	Researchers will identify the effect of metallic lithium on materials that are used in molten salt recycling. The study will try to understand how the presence of Li(0) in molten salts affects the degradation of alloys. Studying these changes will help accurately predict container material behavior and longevity.	Document	FCR&D	FY2014
Assessment of Corrosion Resistance of Promising Accident Tolerant Fuel Cladding under Reactor Conditions	University of Notre Dame	$800,000	Researchers will assess the corrosion behavior of accident tolerant fuel candidate iron-based alloys under normal LWR operating conditions consisting of high temperature, relevant water chemistry and irradiation. The assessment will produce data about possible irradiation-accelerated corrosion rates of iron-based alloys, and the mechanisms by which such corrosion rates are accelerated. The project will advance the selection of appropriate replacements for Zircaloy cladding.	Document	FCR&D	FY2014
Functionalized Porous Organic Polymers as Uranium Nano-Traps for Efficient Recovery of Uranium from Seawaterr	University of South Florida	$399,000	Researchers will develop functionalized porous organic polymers, or Ônano-trapsÕ for extraction of uranium from seawater. This technique allows for increased surface area and custom-designed pore size and chemistry to fit specific parameters. The adsorbent materials have high efficiency and effectiveness for uranium recovery from seawater, providing a potential supply for nuclear fuel.	Document	FCR&D	FY2014
Enhanced Accident-Tolerant Fuel Performance and Reliability for Aggressive iPWR/SMR Operation	University of Tennessee	$799,967	To develop a process that evaluates operational and safety performance of reactor-and-fuel combinations by integrating whole-core 3D neutronics with MOOSE/BISON fuel performance assessments via explicit time and space dependent fuel rod operational power histories. The project will be valuable in analyzing and evaluating accident tolerant fuel concepts and furthering the understanding of reactor physics and fuel performance aspects of key accident tolerant fuel concepts.	Document	FCR&D	FY2014
Nuclear Technology R&D Strategies in an Era of Energy Price Uncertainty	University of Texas, Austin	$799,112	Researchers will identify nuclear technology options that are competitive over a wide range of plausible future business environments. No single nuclear technology or business practice will be the best choice across all or even most future conditions. The study will focus on hybrid nuclear-fossil technologies, energy storage and conversion, which will result in an identification of nuclear strategies that can succeed under future market conditions.	Document	FCR&D	FY2014
Development and Optimization of Voltammetric Methods for Real Time Analysis of Electrorefiner Salt with High Concentrations of Actinides and Fission Products	University of Utah	$621,612	Researchers will develop an advanced voltammetry method to pursue the objective of real time monitoring of actinide concentrations in electrorefiner salt. This will include experimental measurement of key parameters such as activity coefficients and exchange current density. It will also involve simulation of voltammetry processes based on first principles. The project will allow for real time measurements that could support the commercialization of pyroprocessing.	Document	FCR&D	FY2014
Development of Self-Healing Zirconium-Silicide Coatings for Improved Performance of Zirconium-Alloy Fuel Cladding	University of Wisconsin, Madison	$798,621	Researchers will study the deposition of self-healing zirconium-silicide coatings on zirconium-alloy fuel cladding material to improve corrosion resistance under normal and accident conditions. Under these conditions, Zr-Si coating evolves into a highly protective functionally-graded multilayered system. The study will lead to improved performance of zirconium-alloy fuels._	Document	FCR&D	FY2014
Thermal Conductivity in Metallic Fuels	Virginia Polytechnic Institute and State University	$799,837	Researchers will calculate the thermal conductivity of metallic uranium and neptunium alloys, including the effects of noble gasses, using density functional theory. The experiments will validate the calculated effective thermal conductivity using the MARMOT code and by helping determine DFT simulation parameters. The study works to improve fuel lifetime by understanding its thermal behavior.	Document	FCR&D	FY2014
SiC-ODS Alloy Gradient Nanocomposites as Novel Cladding Materials	Virginia Polytechnic Institute and State University	$799,998	Researchers will combine nuclear nanomaterial design, processing, testing, and characterization efforts to develop revolutionary materials that can withstand neutron irradiation for long period of time using nanostructured SiC and oxide dispersion strengthened steel. The ultimate objective is to offer new cladding materials with increased corrosion resistance, strength, and creep resistance in both steady state and accident conditions.	Document	FCR&D	FY2014
Experimental Breeder Reactor II Benchmark Evaluation	Idaho State University	$400,000	Researchers will develop a benchmark evaluation of the Experimental Breeder Reactor II (EBR-II). During nearly 30 years of operation numerous experiments were conducted at EBR-II. The most significant of these experiments were conducted in 1986 demonstrating inherent safety features in loss of flow without reactor scram and loss of heat sink without reactor scram. Benchmark evaluation will be valuable for the reactor design efforts in the United States and South Korea.	Document	MSNE	FY2014
Integral full core multi-physics PWR benchmark with measured data	Massachusetts Institute of Technology	$400,000	Researchers will introduce BEAVRS, a new multi-cycle full-core Pressurized Water Reactor (PWR) depletion benchmark based on two operational cycles of a commercial nuclear power plant. This project aims at addressing the uncertainty quantification of the measured data and on making this benchmark a true non-proprietary international benchmark for the validation of high-fidelity multi-physics computational tools.	Document	MSNE	FY2014
Benchmark Evaluation of PROTEUS Gas-Cooled Reactor Experiments	University of Florida	$400,000	Researchers will create International Reactor Physics Experiment Evaluation Project (IRPhEP) benchmarks using data from 1970s experiments of the neutronics of gas-cooled fast reactor (GCFR) designs investigated in the PROTEUS reactor. The GCFR-PROTEUS experiments fill a gap in current integral benchmark data. These experiments can provide validation of computational models and nuclear data for next generation reactors.	Document	MSNE	FY2014
An Investigation To Establish Multiphysical Property Dataset Of Nuclear Materials Based On In-Situ Observations And Measurements	Purdue University	$800,000	Researchers will create an in-situ measurement based experimental approach to develop experimental validation dataset for NEAMS based code validation. Particular emphasis is on supplying data set for multiphysics simulations in extreme conditions as a function of material microstructure.	Document	NEAMS	FY2014
Experimental Validation of UO2 Microstructural Evolutions for NEAMS tool MARMOT	University of Florida	$798,000	Researchers will experimentally validate MARMOT for predicting the microstructural evolutions of UO2 oxide fuel under the driving forces of high temperatures and large temperature gradient in reactors. By performing the experiments and simulations simultaneously using precisely defined initial conditions, the experiment data will provide direct benchmarking of the MARMOT code.	Document	NEAMS	FY2014
High-resolution time-resolved experiments on mixing and entrainment of buoyant jets in stratified environments	University of Michigan	$799,983	Researchers will study high spatial and time-resolution experimental data of the fluid dynamics phenomena of flow jets interacting with a stratified layer. The issue plays an important role in the safety of several reactor designs, including sodium-cooled reactors. The data addresses the NEAMS needs for the validation of high fidelity computational fluid dynamics methodologies.	Document	NEAMS	FY2014
Fundamental study of key issues related to advanced S-CO2 Brayton Cycle: prototypic HX development and Cavitation	Georgia Institute of Technology	$799,000	Researchers will study scientific and operational issues pertinent to compact heat exchanger systems and turbo-machinery. The project will work to resolve issues with the fabrication of diffusion bonded compact heat exchangers, alternate heat exchange technology for recuperators, and resolution of issues with cavitation and fluid instabilities.	Document	RCRD&D	FY2014
Advanced Models for Nondestructive Evaluation of Aging Nuclear Power Plant Cables	Iowa State University	$787,291	Researchers will develop advanced models that relate environmentally induced microstructural and chemical changes in cable insulation polymers to their macroscopic electrical parameters. These parameters will be measured and modeled over a wide range of the electromagnetic spectrum, covering several potential nondestructive evaluation techniques, enabling identification of the most sensitive techniques for future development.	Document	RCRD&D	FY2014
Development of Novel Functionally Graded Transition Joints for Improving the Creep Strength of Dissimilar Metal Welds in Nuclear Applications	Lehigh University	$800,000	Researchers will develop graded transition joints and improved creep life models for increasing the life of dissimilar metal welds (DMWs) in nuclear reactors. The research represents the first application of functionally graded material concepts for solving the problem of DMW failures through an integrated approach of additive manufacturing, modeling, microstructural characterization, and advanced strain-sensing techniques.	Document	RCRD&D	FY2014
Feasibility Assessment of a Micro Modular Reactor (MMR)	North Carolina State University	$400,000	Researchers will develop an innovative compact reactor concept that integrates power production, power conversion and electricity generation in a single unit: the Micro Modular Reactor (MMR). It is designed to be absolutely melt-down proof (MDP) under all circumstances including complete loss of coolant scenarios with no possible release of radioactive material, to have a cycle length of greater than 10 years, and to be highly proliferation resistant.	Document	RCRD&D	FY2014
Scaling Studies for Advanced Gas Reactor Concepts	Oregon State University	$681,834	Researchers will expand the utilization of the Oregon State University High Temperature Test Facility (HTTF) to validate a broader range of advanced high temperature reactors and events. The facility will be revised to add a detailed scaling analysis of additional gas reactor concepts including advanced gas-cooled, molten salt, and sodium cooled reactors.	Document	RCRD&D	FY2014
Fluid Stratification Separate Effects Analysis, Testing and Benchmarking	Oregon State University	$800,000	Researchers will study fluid stratification in high temperature gas reactors. Coolant stratification is the result of incomplete mixing of one or more fluids, leading to a density gradient, which may or may not dissipate under diffusive or convective effects. This combined analytical and experimental project seeks to investigate stratification driven by diffusive and convective mechanisms and is expected to yield insight into this phenomenon.	Document	RCRD&D	FY2014
Probabilistic Economic Valuation of Safety Margin Management Analysis	Oregon State University	$795,364	Researchers will use RAVEN and develop a companion software package to facilitate economic analysis of safety margins. The project is a proof of concept that will use techniques to examine the cost of improving safety margins vs. the risk of accidents from not improving safety margins. This analysis can be used to evaluate the economic viability of various plant upgrades.	Document	RCRD&D	FY2014
Novel Dissimilar Joints Between Alloy 800H and 2.25%Cr and 1%Mo Steel	Pennsylvania State University	$800,000	Researchers will fabricate and test dissimilar metal joints between a nickel base alloy and a steel with gradual variations of chemical composition, microstructure and properties in a manner that reduces abrupt thermal expansion mismatch and the resulting residual stresses. Data on structure and properties will serve as valuable inputs for the initiation of an ASME code case.	Document	RCRD&D	FY2014
Multi-Phase Model Development to Assess RCIC System Capabilities under Severe Accident Conditions	Texas A&M University	$564,246	Researchers will develop physics-based models of the Reactor Core Isolation Cooling (RCIC) System and incorporating them into a multi-phase code for validation. The project will tackle the current major challenges in RCIC System analysis and enable evaluation of two-phase thermodynamic aspects.	Document	RCRD&D	FY2014
Experimental Investigation and CFD Analysis of Steam Ingress Accidents in HTGRs	The Ohio State University	$800,000	Researchers will study the steam ingress scenario for HTGRs. The study will investigate thermal-hydraulic behavior and graphite oxidation of stream ingress phenomena to validate predictive CFD models. This work will resolve concerns about possible steam generator tube ruptures in a HTGR He-Steam Rankine cycle.	Document	RCRD&D	FY2014
Coiled Tube Gas Heaters For Nuclear Gas-Brayton Power Conversion	University of California, Berkeley	$800,000	Researchers will develop heat exchangers for Brayton-cycle power conversion in reactors using sodium, NaK, or salt as intermediate coolants. The proposed coiled tube gas heaters (CTGHs) are expected to have excellent power density, thermal shock/creep, in-service inspection, and reparability characteristics.	Document	RCRD&D	FY2014
Fundamental Studies of Irradiation-Induced Modifications in Microstructural Evolution and Mechanical Properties of Advanced Alloys	University of Illinois, Urbana-Champaign	$800,000	Researchers will develop and test a mechanism for predicting neutron irradiation performance for optimized Grade 92 and Alloy 709 for applications in advanced reactor systems. The work will employ ion irradiations and available information from neutron irradiations of related alloys to develop a basis for predicting the neutron irradiation performance of the optimized alloys.	Document	RCRD&D	FY2014
Integrated Computational and Experimental Study of Radiation Damage Effects in Grade 92 Steel and Alloy 709	University of Tennessee	$800,000	Researchers will develop a mechanistic understanding and predictive models of irradiation-induced microstructural evolution and resulting mechanical properties in optimized ferritic-martensitic Grade 92 steel and austenitic alloy 709 using multiscale simulations coupled with rigorous experimental validation. The project will provide insights into the correlation between ion irradiation and fast neutron damage.	Document	RCRD&D	FY2014
Meta-Level Design Guidance and Operator Performance Measures for Hybrid Control Rooms	Vanderbilt University	$799,869	Researchers will apply human factors engineering methods and relevant expertise from non-nuclear high-risk high-consequence domains toward the measurement of operator performance in analog, digital, and hybrid main control rooms. Performance measures will be developed for evaluating the situation awareness and decision-making proficiencies to support the transition to digital or hybrid control room displays.	Document	RCRD&D	FY2014

FY 2017 Research and Development Awards

DOE is awarding over $31 million through its Nuclear Energy University Program (NEUP) to support 32 university-led nuclear energy research and development projects in 23 states. NEUP seeks to maintain U.S. leadership in nuclear research across the country by providing top science and engineering faculty and their student’s opportunities to develop innovative technologies and solutions for civil nuclear capabilities.

A complete list of R&D projects with their associated abstracts is available below.

Title	Institution	Estimated Funding*	Project Description	Abstract	Project Type	Fiscal Year
Neutron Damage and MAX Phase Ternary Compounds	Drexel University			Document	IIR	FY2009
Atomistic Calculations of the Effect of Minor Actinides on Thermodynamic and Kinetic Properties of UO2+x	Georgia Institute of Technology			Document	IIR	FY2009
Maximum Fuel Utilization in Fast Reactors without Chemical Reprocessing	University of California, Berkeley			Document	IIR	FY2009
Developing a High Thermal Conductivity Fuel with Silicon Carbide Additives	University of Florida			Document	IIR	FY2009
Fabrication of Tungsten-Rhenium Cladding Materials via Spark Plasma Sintering for Ultra High Temperature Reactor Applications	University of Idaho			Document	IIR	FY2009
Ionic Liquid and Supercritical Fluid Hyphenated Techniques for Dissolution and Separation of Lanthanides, Actinides, and Fission Products	University of Idaho			Document	IIR	FY2009
Improved Fission Neutron Data Base for Active Interrogation of Actinides	University of Michigan			Document	IIR	FY2009
Utilization of Methacrylates and Polymer Matrices for the Synthesis of Ion Specific Resins	University of Nevada, Las Vegas			Document	IIR	FY2009
Improved LWR Cladding Performance by EPD Surface Modification Technique	University of Wisconsin, Madison			Document	IIR	FY2009
Advanced Models of LWR Pressure Vessel Embrittlement for Low Flux-High Fluence Conditions	University of California, Santa Barbara			Document	LWRS	FY2009
Irradiation Creep in Graphite	Boise State University			Document	NGNP	FY2009
Modeling the Stress Strain Relationships and Predicting Failure Probabilities For Graphite Core Components	Cleveland State University			Document	NGNP	FY2009
TRISO-Coated Fuel Durability Under Extreme Conditions	Colorado School of Mines			Document	NGNP	FY2009
An Innovative and Advanced Coupled Neutron Transport and Thermal Hydraulic Method (Tool) for the Design, Analysis and Optimization of VHTR/NGNP Prismatic Reactors	Georgia Institute of Technology			Document	NGNP	FY2009
Removal of 14C from Irradiated Graphite for Graphite Recycle and Waste Volume Reduction	Idaho State University			Document	NGNP	FY2009
Millimeter-Wave Thermal Analysis Development and Application to Gen IV Reactor Materials	Massachusetts Institute of Technology			Document	NGNP	FY2009
Accurate Development of Thermal Neutron Scattering Cross Section Libraries	North Carolina State University			Document	NGNP	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
Understanding Creep Mechanisms in Graphite with Experiments, Multiscale Simulations, and Modeling	North Carolina State University			Document	NGNP	FY2009
Simulations of the Thermodynamic and Diffusion Properties of Actinide Oxide Fuel Materials	University of Michigan			Document	AFCI	FY2009
Verification & Validation of High-Order Short-Characteristics-Based Deterministic Transport Methodology on Unstructured Grids	North Carolina State University			Document	NGNP	FY2009
Adsorptive Separation and Sequestration of Krypton, I and C14 on Diamond Nanoparticles	University of Missouri, Columbia			Document	AFCI	FY2009
Microscale Heat Conduction Models and Doppler Feedback	North Carolina State University			Document	NGNP	FY2009
Fundamental Understanding of Ambient and High-Temperature Plasticity Phenomena in Structural Materials in Advanced Reactors	Georgia Institute of Technology			Document	AFCI	FY2009
Development of Alternative Technetium Waste Forms	University of Nevada, Las Vegas			Document	AFCI	FY2009
Optimizing Neutron Thermal Scattering Effects in Very High Temperature Reactors	North Carolina State University			Document	NGNP	FY2009
Advanced Elastic/Inelastic Nuclear Data Development Project	Idaho State University			Document	AFCI	FY2009
Heterogeneous Recycling in Fast Reactors	Massachusetts Institute of Technology			Document	AFCI	FY2009
Quantification of UV-Visible and Laser Spectroscopic Techniques for Materials Accountability and Process Control	University of Nevada, Las Vegas			Document	AFCI	FY2009
Multiaxial Creep-Fatigue and CreepRatcheting Failures of Grade 91 and Haynes 230 Alloys Toward Addressing Design Issues of Gen IV Nuclear Power Plants	North Carolina State University			Document	NGNP	FY2009
Thermodynamic Development of Corrosion Rate Modeling in Iron Phosphate Glasses	Missouri University of Science and Technology			Document	AFCI	FY2009
Development of Subspace-Based Hybrid Monte Carlo-Deterministic Algorithms for Reactor Physics Calculations	North Carolina State University			Document	AFCI	FY2009
High-Fidelity Space-Time Adaptive Multiphysics Simulations in Nuclear Engineering	University of Nevada, Reno			Document	AFCI	FY2009
Improvements to Nuclear Data and Its Uncertainties by Theoretical Modeling	Rensselaer Polytechnic Institute			Document	AFCI	FY2009
Investigation of Countercurrent Helium-air Flows in Air-ingress Accidents for VHTRs	Ohio State University			Document	NGNP	FY2009
Sharp Interface Tracking in Rotating Microflows of Solvent Extraction	State University of New York at Stony Brook			Document	AFCI	FY2009
Bulk Nanostructured FCC Steels with Enhanced Radiation Tolerance	Texas A&M University			Document	AFCI	FY2009
Simulations of Failure via Three-Dimensional Cracking in Fuel Cladding for Advanced Nuclear Fuels	University of Texas, Dallas			Document	AFCI	FY2009
Testing of Performance of Optical Fibers Under Irradiation in Intense Radiation Fields, When Subjected to Very High Temperatures	Ohio State University			Document	NGNP	FY2009
Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels	Texas A&M University			Document	AFCI	FY2009
SiC Schottky Diode Detectors for Measurement of Actinide Concentrations from Alpha Activities in Molten Salt Electrolyte	The Ohio State University			Document	AFCI	FY2009
Computational Design of Advanced Nuclear Fuels	University of California, Davis			Document	AFCI	FY2009
Advanced Mesh-Enabled Monte Carlo Capability for Multi-Physics Reactor Analysis	University of Wisconsin, Madison			Document	AFCI	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
A Distributed Fiber Optic Sensor Network for Online 3-D Temperature and Neutron Fluence Mapping in a VHTR Environment	Texas A&M University			Document	NGNP	FY2009
Ab Initio Enhanced Calphad Modeling of Actinide Rich Nuclear Fuels	University of Wisconsin, Madison			Document	AFCI	FY2009
Investigation on the Core Bypass Flow in a Very High Temperature Reactor	Texas A&M University			Document	NGNP	FY2009
Development of Diffusion Barrier Coatings and Deposition Technologies for Mitigating Fuel Cladding Chemical Interactions (FCCI)	University of Wisconsin, Madison			Document	AFCI	FY2009
CFD Model Development and Validation for High Temperature Gas Cooled Reactor Cavity Cooling System (RCCS) Applications	Texas A&M University			Document	NGNP	FY2009
Thermal Properties of LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin, Madison			Document	AFCI	FY2009
Study of Air ingress across the duct during the accident conditions	Texas A&M University			Document	NGNP	FY2009
Verification of the CENTRM Module for Adaptation of the SCALE Code to NGNP Prismatic and PBR Core Designs	University of Arizona			Document	NGNP	FY2009
Integral and Separate Effects Tests for Thermal Hydraulics Code Validation for Liquid-Salt Cooled Nuclear Reactors	University of California, Berkeley			Document	NGNP	FY2009
Mechanisms Governing the Creep Behavior of High Temperature Alloys for Generation IV Nuclear Energy Systems	University of Cincinnati			Document	NGNP	FY2009
ALD Produced B2O3, Al2O3 and TiO2 Coatings on Gd2O3 Burnable Poison Nanoparticles	University of Colorado, Boulder			Document	NGNP	FY2009
Experimental Study and Computational Simulations of Key Pebble Bed Thermomechanics Issues for Design and Safety	University of Idaho			Document	NGNP	FY2009
Prediction and Monitoring Systems of Creep-Fracture Behavior of 9Cr-1Mo Steels for Reactor Pressure Vessels	University of Idaho			Document	NGNP	FY2009
Understanding Fundamental Material Degradation Processes in High Temperature Aggressive Chemomechanical Environments	University of Illinois, Urbana-Champaign			Document	NGNP	FY2009
Multi-Scale Multi-physics Methods Development for the Calculation of Hot-Spots in the NGNP	University of Michigan			Document	NGNP	FY2009
Corrosion and Creep of Candidate Alloys in High Temperature Helium and Steam Environments for the NGNP	University of Michigan			Document	NGNP	FY2009
Creation of a Full-Core HTR Benchmark with the Fort St. Vrain Initial Core and Validation of the DHF Method with Helios for NGNP Configurations	University of Michigan			Document	NGNP	FY2009
Fission Product Sorptivity in Graphite	University of Missouri, Columbia			Document	NGNP	FY2009
Identifying and Understanding Environment-Induced Crack Propagation Behavior in Ni-Based Superalloy INCONEL 617	University of Nevada, Las Vegas			Document	NGNP	FY2009
Graphite Oxidation Simulation in HTR Accident Conditions	University of New Mexico			Document	NGNP	FY2009
Non Destructive Thermal Analysis and In Situ Investigation of Creep Mechanism of Graphite and Ceramic Composites using Phase-sensitive THz Imaging & Nonlinear Resonant Ultrasonic Spectroscopy	University of Rochester			Document	NGNP	FY2009
Tritium Sequestration in Gen IV NGNP Gas Stream via Proton Conducting Ceramic Pumps	University of South Carolina			Document	NGNP	FY2009
Materials, Turbomachinery and Heat Exchangers for Supercritical CO2 Systems	University of Wisconsin, Madison			Document	NGNP	FY2009
Experimental Studies of NGNP Reactor Cavity Cooling System with Water	University of Wisconsin, Madison			Document	NGNP	FY2009
Assessment of Embrittlement of VHTR Structural Alloys in Impure Helium Environments	University of Wisconsin, Madison			Document	NGNP	FY2009
Modeling Fission Product Sorption in Graphite Structures	University of Wisconsin, Madison			Document	NGNP	FY2009
Liquid Salt Heat Exchanger Technology for VHTR Based Applications	University of Wisconsin, Madison			Document	NGNP	FY2009
Effect of Post-Weld Heat Treatment on Creep Rupture Properties of Grade 91 Steel Heavy Section Welds	Utah State University			Document	NGNP	FY2009
Alpha Radiolysis of Nuclear Solvent Extraction Ligands used for An(III) and Ln(III) Separations	California State University, Long Beach	$1,390,252		Document	FCR&D	FY2010
Predictive Maturity of Multi-Scale Simulation Models for Fuel Performance	Clemson University	$614,690		Document	FCR&D	FY2010
Freeze-casting as a Novel Manufacturing Process for Fast Reactor Fuels	Drexel University	$1,149,327		Document	FCR&D	FY2010
Fuel Performance Experiments on the Atomistic Level, Studying Fuel Through Engineered Single Crystal UO2	Idaho State University	$650,000		Document	FCR&D	FY2010
Development of A Self Biased High Efficiency Solid-State Neutron Detector for MPACT Applications	Rensselaer Polytechnic Institute	$810,141		Document	FCR&D	FY2010
Development of a Innovative High Thermal Conductivity UO 2 Ceramic Composites Fuel Pellets with Carbon Nano-Tubes Using Spark Plasma Sintering	University of Florida	$894,042		Document	FCR&D	FY2010
Exploration and Modeling of Structural Changes in Waste Glass under Corrosion	Pennsylvania State University	$1,377,444		Document	FCR&D	FY2010
Evaluation of materials for interim storage of spent fuel for more than 100 years	University of Michigan	$931,603		Document	FCR&D	FY2010
Implementation of On-the-Fly Doppler Broadening in MCNP5 for Multiphysics Simulation of Nuclear Reactors	University of Michigan	$406,712		Document	FCR&D	FY2010
Methods and tools to allow molecular flow simulations to be coupled to higher level continuum descriptions of flows in porous/fractured media and aerosol/dust dynamics	University of Missouri-Columbi	$541,286		Document	FCR&D	FY2010
Characterization and Modeling of Materials for Kr-Xe Separations	University of Nevada-Las Vegas	$989,800		Document	FCR&D	FY2010
Modeling Solute Thermokinetics in LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin-Madison	$616,073		Document	FCR&D	FY2010
Advanced Aqueous Separation Systems for Actinide Partitioning: Develop Fundamental Understanding of An(III)/Ln(III) Separation	Washington State University	$1,451,784		Document	FCR&D	FY2010
Consistent Multigroup Theory Enabling Accurate Coarse-Group Simulation of GenIV Reactors	Georgia Institute of Technology	$1,046,277		Document	GEN IV	FY2010
Studies of Deteriorated Heat Transfer in Prismatic Cores Stemming from Irradiation-Induced Geometry Distortion	Idaho State University	$1,287,921		Document	GEN IV	FY2010
Carbide Coatings for Nickel Alloys, Graphite, and Carbon/Carbon Composites to be Used in Fluoride Salt Valves	Johns Hopkins University	$1,183,239		Document	GEN IV	FY2010
Design, Testing, and Modeling of the Direct Reactor Auxiliary Cooling System for AHTRs	Ohio State University	$1,366,627		Document	GEN IV	FY2010
Monitoring microstructural evolution of Alloy 617 with nonlinear acoustics for remaining useful life prediction; multiaxial creep-fatigue and creep-ratcheting	Pennsylvania State University	$1,000,000		Document	GEN IV	FY2010
Development and Validation of Multidimensional Models of Supercritical CO 2 Energy Conversion Systems for Nuclear Power Reactors	Rensselaer Polytechnic Institute	$475,005		Document	GEN IV	FY2010
Multiscale Concrete Modeling for Aging Degradation	Mississippi State University	$345,941		Document	LWRS	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term and Elevated Temperature Irradiation: Modeling and Experimental Investigation	University of California-Berkeley	$1,320,667		Document	GEN IV	FY2010
Development of an advanced computational fluid dynamics technology for the next-generation nuclear reactor system analysis and safety margin characterization code	North Carolina State University	$418,199		Document	LWRS	FY2010
Development of Barrier Layers for the Protection of Candidate Alloys in the VHTR	University of California-Santa Barbara	$995,232		Document	GEN IV	FY2010
Precursor Derived Nanostructured Si-C-X Materials for Nuclear Applications	University of Washington	$899,518		Document	MRIIR	FY2010
Investigation of a Novel NDE Method for Monitoring Thermo-Mechanical Damage and Microstructure Evolution in Ferritic-Martensitic Steels for Generation IV Nuclear Energy Systems	University of Cincinnati	$833,109		Document	GEN IV	FY2010
Development and Testing of an Open-Loop Oscillator for Small Reactivity Worth Samples	Idaho State University	$597,252		Document	MRIIR	FY2010
Fission Product Transport in TRISO Particle Layers under Operating and Off-Normal Conditions	University of Michigan	$966,581		Document	GEN IV	FY2010
Understanding the Irradiation Behavior of Zirconium Carbide	Pennsylvania State University	$870,613		Document	MRIIR	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term Irradiation at Elevated Temperature: Critical Experiments	University of Michigan	$1,181,379		Document	GEN IV	FY2010
Modeling investigation of the stability and irradiation-induced evolution of nanoscale precipitates in advanced structural materials	University of Tennessee-Knoxville	$380,653		Document	MRIIR	FY2010
Three-dimensional NDE of VHTR Core Components via Simulation-based Testing	University of Minnesota	$1,366,163		Document	GEN IV	FY2010
Investigation of Laser Shock Peening for Enhancing Fatigue and Stress Corrosion Cracking Resistance of Nuclear Energy Materials	University of Cincinnati	$1,242,019		Document	MRIIR	FY2010
Failure Predictions for VHTR Core Components using a Probabilistic Continuum Damage Mechanics Model	University of Minnesota	$854,542		Document	GEN IV	FY2010
Irradiation Accelerated Corrosion of Reactor Core Materials	University of Michigan	$798,943		Document	MRIIR	FY2010
Development of a Scanning Microscale Fast Neutron Irradiation Platform for Examining the Correlation Between Local Neutron Damage and Graphite Microstructure	University of Missouri-Columbia	$703,064		Document	GEN IV	FY2010
Study of Interfacial Interactions using Thin Film Surface Modification: Radiation and Oxidation Effects in Materials	University of Wisconsin-Madison	$538,032		Document	MRIIR	FY2010
Development of Thermal Transient Flow Rate Sensors for High Temperature, Irradiation, Corrosive Environment	University of Nevada-Las Vegas	$451,269		Document	GEN IV	FY2010
Novel Engineered Refractory Materials for Advanced Reactor Applications	North Carolina State University	$1,129,304		Document	MRIIR	FY2010
Novel Methods of Tritium Sequestration: High Temperature Gettering and Separation Membrane Materials Discovery for Nuclear Energy Systems	University of South Carolina	$1,366,626		Document	GEN IV	FY2010
Heat Transfer Salts for Nuclear Reactor Systems - Chemistry Control, Corrosion Mitigation, and Modeling	University of Wisconsin-Madison	$1,352,040		Document	GEN IV	FY2010
Pulsed Magnetic Welding for Advanced Core and Cladding Steels	University of Wisconsin-Madison	$525,206		Document	GEN IV	FY2010
Corrosion in Supercritical Carbon Dioxide: Materials, Environmental Purity, Surface Treatments, and Flow Issues	University of Wisconsin-Madison	$651,447		Document	GEN IV	FY2010
Quantification of Cation Sorption to Engineered Barrier Materials Under Extreme Conditions	Clemson University	$1,171,380		Document	FCR&D	FY2011
In-Pile Instrumentation Multi-Parameter System Utilizing Photonic Fibers and Nanovision	Idaho State University	$1,199,990		Document	FCR&D	FY2011
Development of Plasmonically Cloaked Nanoparticles	Idaho State University	$800,000		Document	FCR&D	FY2011
Fission Product Transmutation in Mixed Radiation Fields	Idaho State University	$800,000		Document	FCR&D	FY2011
Life Prediction of Spent Fuel Storage Canister Material	Massachusetts Institute of Technology	$899,826		Document	FCR&D	FY2011
Active Interrogation using Photofission Technique for Nuclear Materials Control and Accountability	Oregon State University	$900,000		Document	FCR&D	FY2011
Anisotropic Azimuthal Power and Temperature Distribution on Fuel Rod: Impact of Hydride Distribution	Pennsylvania State University	$631,956		Document	FCR&D	FY2011
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$1,000,000		Document	FCR&D	FY2011
Recovery of Uranium from Seawater: Preparation and Development of Polymer-Supported Extractants	City College of New York, Hunter	$363,716		Document	MSTR	FY2011
Microemulsions and Aggregation Formation in Extraction Processes for Used Nuclear Fuel: Thermodynamics and Structural Studies	University of California, Irvine	$1,000,000		Document	FCR&D	FY2011
One-Dimensional Nanostructures for Neutron Detection	North Carolina State University	$455,629		Document	MSTR	FY2011
Optimized Processing Fabrication Paths for Larger Heats of Nanostructured Ferritic Alloys	University of California, Santa Barbara	$1,000,000		Document	FCR&D	FY2011
Feasibility and Safety Assessment for Advanced Reactor Concepts Using Vented Fuel	Oregon State University	$600,000		Document	MSTR	FY2011
Basic Physics Data: Measurement of Neutron Multiplicity from Induced Fission	University of Michigan	$973,364		Document	FCR&D	FY2011
Development of an Efficient Meso-Scale Multi-Phase Flow Solver in Nuclear Applications	City College of New York	$505,858		Document	NEAMS	FY2011
High Temperature Transducers for Online Monitoring of Microstructure Evolution	Pennsylvania State University	$455,628		Document	MSTR	FY2011
Radionuclide Incorporation and Long Term Performance of Apatite Waste Forms	University of Michigan	$862,500		Document	FCR&D	FY2011
Multiscale Modeling and Uncertainty Quantification for Nuclear Fuel Performance	Colorado State University	$1,098,250		Document	NEAMS	FY2011
Laser-Arc Hybrid Welding of Thick Section Ni-base Alloys- Advanced Modeling and Experiments	Pennsylvania State University	$536,117		Document	MSTR	FY2011
Actinide Foil Production for MPACT Research	University of Nevada-Las Vegas	$156,897		Document	FCR&D	FY2011
Fundamental Studies of the Role of Grain Boundaries on Uniform Corrosion of Advanced Nuclear Reactor Materials	Drexel University	$1,098,250		Document	NEAMS	FY2011
Correlates of Sensitive Technologies	Texas A&M University	$509,467		Document	MSTR	FY2011
Enriched Boron-Doped Amorphous Selenium Based Position-Sensitive Solid-State Thermal Neutron Detector for MPACT Applications	University of South Carolina	$1,000,000		Document	FCR&D	FY2011
Phenomena-based Uncertainty Quantification in Predictive Coupled-Physics Reactor Simulations	Texas A&M University	$1,098,250		Document	NEAMS	FY2011
Improved Safety Margin Characterization of Risk from Loss of Offsite Power	Texas A&M University	$600,000		Document	MSTR	FY2011
Development of Advanced High Uranium Density Fuels for Light Water Reactors	University of Wisconsin-Madison	$1,000,000		Document	FCR&D	FY2011
Characterization of Modeling of Grain Boundary Chemistry Evolution in Ferritic Steels Under Irradiation	University of Michigan	$1,098,250		Document	NEAMS	FY2011
Diffusion, Thermal Properties and chemical Compatibilities of Select MAX Phases with Materials for Advanced Nuclear Systems	Drexel University	$535,927		Document	NEET	FY2011
A High Temperature-Tolerant and Radiation-Resistant In-Core Neutron Sensor for Advanced Reactors	The Ohio State University	$455,629		Document	MSTR	FY2011
Developing the User Experience for a Next Generation Nuclear Fuel Cycle Simulator	University of Wisconsin-Madison	$1,200,000		Document	FCR&D	FY2011
Development of Multiscale Materials Modeling Techniques and Coarse-Graining Strategies for Predicting Materials Degradation in Extreme Irradiation Environments	University of Tennessee, Knoxville	$750,000		Document	NEAMS	FY2011
A New Light Weight Structural Material for Nuclear Structures	North Carolina State University	$399,490		Document	NEET	FY2011
Pathway Aggregation in the Risk Assessment of Proliferation Resistance and Physical Protection (PR&PP) of Nuclear Energy Systems	The Ohio State University	$534,471		Document	MSTR	FY2011
Experimental Investigation of Convection and Heat Transfer in the Reactor Core for a VHTR	City College of New York	$1,118,856		Document	RCRD&D	FY2011
Preparation of High Purity, High Molecular-Weight Chitin from Ionic Liquids for Use as an Adsorbate for the Extraction of Uranium from Seawater	University of Alabama	$338,260		Document	MSTR	FY2011
Graphite Microstructural Characterization Using Time-Domain and Correlation-Based Ultrasonics	Johns Hopkins University	$1,199,997		Document	RCRD&D	FY2011
Selectivity in Ligand Binding to Uranyl Compounds: A Synthetic, Structural, Thermodynamic and Computational Study	University of California-Berkeley	$500,000		Document	MSTR	FY2011
Methodology Development for Passive Component Reliability Modeling in a Multi-Physics Simulation Environment	The Ohio State University	$533,457		Document	RCRD&D	FY2011
Development of Seismic Isolation Systems Using Periodic Materials	University of Houston	$538,154		Document	MSTR	FY2011
Pebble Fuel Handling and Reactivity Control for Salt-Cooled High Temperature Reactors	University of California, Berkeley	$612,721		Document	RCRD&D	FY2011
Innovative Elution Processes for Recovering Uranium from Seawater	University of Idaho	$400,000		Document	MSTR	FY2011
Self-Sustaining Thorium Boiling Water Reactors	University of California, Berkeley	$1,145,932		Document	RCRD&D	FY2011
Development of Austenitic ODS Strengthened Alloys for Very High Temperature Applications	University of Illinois-Urbana Champaign	$538,154		Document	MSTR	FY2011
High Fluency Low Flux Embrittlement Models of LWR Reactor Pressure Vessel Embrittlement and a Supporting Database from the UCSB ATR-2 Irradiation Experiment	University of California, Santa Barbara	$1,199,607		Document	RCRD&D	FY2011
Enhancement of the Extraction of the Uranium from Seawater	University of Maryland	$400,000		Document	MSTR	FY2011
A Research Program for Fission Product/Dust Transport in HTGR's	University of Missouri-Columbia	$1,157,367		Document	RCRD&D	FY2011
Transient Safety Analysis of Fast Spectrum TRU Burning LWR with Internal Blankets	University of Michigan	$599,475		Document	MSTR	FY2011
Development and Validation of a Lifecycle-based Prognostics Architecture with Test Bed Validation	University of Tennessee, Knoxville	$846,315		Document	RCRD&D	FY2011
Development of Novel Sorbents for Uranium Extraction from Seawater	University of North Carolina, Chapel Hill	$400,000		Document	MSTR	FY2011
In-situ Condition Monitoring of Components in Small Modular Reactors Using Process and Electrical Signature Analysis	University of Tennessee, Knoxville	$650,000		Document	RCRD&D	FY2011
Radiation Behavior of High-Entropy Alloys for Advanced Reactors	University of Tennessee, Knoxville	$538,159		Document	MSTR	FY2011
Technical Development for S-CO2 Advanced Energy Conversion	University of Wisconsin	$815,000		Document	RCRD&D	FY2011
Rapid Computer Aided Ligand Design and Screening of Precious Metal Extractants from TRUEX Raffinate with Experimental Validation	Washington State University	$500,000		Document	MSTR	FY2011
Ag Transport Through Non-Irradiated and Irradiated SiC	University of Wisconsin-Madison	$1,055,456		Document	RCRD&D	FY2011
Critical Heat Flux Phenomena at High Pressure and Low Mass Fluxes: Tests and Models	University of Wisconsin-Madison	$1,199,781		Document	RCRD&D	FY2011
Modeling and Test Validation of a Reactor Cavity Cooling System with Air	University of Wisconsin-Madison	$1,199,988		Document	RCRD&D	FY2011
Transient Mixed Convection Validation for NGNP	Utah State University	$635,860		Document	RCRD&D	FY2011
Alternative High-Performance Ceramic Waste Forms	Alfred University	$840,000	This project aims to advance fundamental understanding of the kinetics of structural evolution of crystalline ceramic waste forms. The structure/property relationships will be identified and will reveal new formulations, improved processing routes, and strategies for improved performance or ceramic waste forms.	Document	FCR&D	FY2012
Surface Layer Bulk Glass Interface Evolution with Aqueous Corrosion	Alfred University	$880,000	This project will investigate the links between the morphology, structure and chemistry of surface layer-bulk glass interface and the long-term corrosion-reaction kinetics using in-situ and ex-situ experiments. The understanding will result in improved models for long-term predictive behavior of high-level-waste (HLW) glasses under repository conditions.	Document	FCR&D	FY2012
Improved Accident Tolerance of Austenitic Stainless Steel Cladding through Colossal Supersaturation with Interstitial Solutes	Case Western Reserve University	$850,000	This project aims to develop new case-hardened austenitic stainless steels by saturating them with materials that improve their mechanical properties, corrosion resistance and radiation resistance. This project, if successful, will result in safer, longer-lasting, and more accident tolerant fuel claddings.	Document	FCR&D	FY2012
Optimization of Deep Borehole Systems for HLW Disposal	Massachusetts Institute of Technology	$850,000	Researchers aim to carry out a comprehensive evaluation of the deep borehole option for disposal of used nuclear fuel and high livel waste. The models developed will predict potential movement of water through natural and engineered barriers and release of radionuclides to the biosphere which will aide in site selection.	Document	FCR&D	FY2012
Scholarship for Nuclear Communications and Methods for Evaluation of Nuclear Project Acceptability	Massachusetts Institute of Technology	$800,000	Researchers will work to develop a model to characterize the factors affecting social acceptance of nuclear projects with potential stakeholders. The resultant model will strengthen the ability to design and implement large projects more efficiently, leading to higher rates of success of future nuclear projects.	Document	FCR&D	FY2012
Accurate Holdup Calculations with Predictive Modeling and Data Integration	North Carolina State University	$875,000	Researchers will develop and use state-of-the-art radiation transport codes to account accurately for the fissile material in a nuclear materials processing facility. An accurate estimation of the materials will allow for ensured radiological safety, security, waste management and efficient plant operation.	Document	FCR&D	FY2012
Novel Metal Sulfides to Achieve Effective Capture and Durable Consolidation of Radionuclides	Northwestern University	$760,000	Researchers will evaluate the effectiveness of chalcogenide based materials design novel metal sulfides to effectively capture and store of radioisotopes released during reprocessing of used nuclear fuel. This project will focus on understanding structure-property relationships to enable refined and direct synthesis approaches for improved and cost-efficient nuclear waste forms.	Document	FCR&D	FY2012
Nonlinear Ultrasonic Diagnosis and Prognosis of ASR Damage in Dry Cask Storage	Northwestern University	$885,000	Researchers aim to use nondestructive damage characterization methods to detect, manage and mitigate the degradation/damage mechanisms of dry cask storage systems for nuclear fuels. This project, if successful, will provide tools that will allow the prediction of the reliability and the safety of concrete structures in dry cask storage systems.	Document	FCR&D	FY2012
Prototype Demonstration of Gamma-Blind Tensioned Metastable Fluid Neutron/Multiplicity/Alpha Detector- Real Time Methods for Advanced Fuel Cycle Applications	Texas A&M University	$875,000	This project aims to create a prototype demonstration of a novel neutron/alpha detector based on a technology that is blind to gamma field used fuel. The prototype, if successful, will enhance instrumentation for monitoring real-time material balance during various stages of the nuclear cycle.	Document	FCR&D	FY2012
Testing of Sapphire Optical Fiber and Sensors in Intense Radiation Fields, when Subjected to Very High Temperatures	The Ohio State University	$885,000	The researchers on this project will investigate the performance of sapphire optical fibers and sensors in reactor environments. The project, if successful, will result in improved instrumentation to understand the behavior and predict performance of nuclear fuel systems at the microstructural level.	Document	FCR&D	FY2012
Concrete Materials with Ultra-High Damage Resistance and Self-Sensing Capacity for Extended Nuclear Fuel Storage Systems	University of California, Irvine	$800,000	Researchers aim to design a new class of multifunctional concrete materials. This project, if successful, will result in a novel multifunctional concrete material that possesses inherent degradation monitoring capability and is suitable for an extended storage system for the used nuclear fuel.	Document	FCR&D	FY2012
Development of Innovative Accident Tolerant High Thermal Conductivity UO2 Fuel Pellets with a Diamond Dopant	University of Florida	$800,000	Researchers will evaluate the use of diamond nanoparticles composite material in innovative accident tolerant fuel pellets. This could significantly improve both the thermal conductivity of fuel pellets and light water reactors' efficiency safety.	Document	FCR&D	FY2012
Probabilistic Multi-Hazard Assessment of Dry Cask Structures	University of Houston	$865,000	This project aims to investigate the performance of dry cask storage systems under multiple hazard systems (earthquake, tornados, combined with aging effects) using a probabilistic multi-hazard framework. This framework will be validated based on experimental research and will provide improved models for safety and reliability of spent nuclear fuels during storage and transportation.	Document	FCR&D	FY2012
Measurement of Irradiated Pyroprocessing Samples via Laser Induced Breakdown Spectroscopy	University of Idaho	$820,000	This project aims to use advanced characterization techniques to investigate microstructural changes and the micromechanisms related to irradiation induced damage in used nuclear fuels and waste forms. This project, if successful, will result in enhanced models to predict the structural and chemical response of used fuel and waster forms during interim storage and permanent disposal.	Document	FCR&D	FY2012
Elastic/Inelastic Measurement Project	University of Kentucky	$880,523	Researchers will measure nuclear data for elastic/inelastic scattered neutrons on coolants and structural materials. The data generated, will be useful for future R&D programs that will study innovative next generation LWR and future fast systems.	Document	FCR&D	FY2012
Electrochemical Corrosion Studies for Modeling Metallic Waste Form Release Rates	University of Nevada- Las Vegas	$790,000	This project aims to use advanced electrochemical methods to investigate the corrosion related degradation of metal alloys used for housing fission products. The data obtained from this study will allow for the prediction of the long-term behavior of the metallic host phase materials over geological time-scales.	Document	FCR&D	FY2012
Thermodynamic and Microstructural Mechanisms in the Corrosion of Advanced Ceramic Tc-bearing Waste Forms and Thermophysical Properties	University of Nevada- Las Vegas	$795,000	This project team will harvest thermodynamic and microstructural data on the evolution of ceramic based waste forms. The data will be used to advance the current state-of-the-art methodology used for isolation and stabilization of fission products and improve on nuclear fuel recycling processes.	Document	FCR&D	FY2012
Development and Experimental Benchmark of Simulations to Predict Used Nuclear Fuel Cladding Temperatures during Drying and Transfer Operations	University of Nevada- Reno	$745,000	Researchers will conduct experiments to investigate and develop advanced computational models of heat transfer in post-pool-storage drying operations. This project, if successful, will result in tools that can be used to design efficient drying processes to as to ensure suitability for dry-cask systems for long-term storage and transport.	Document	FCR&D	FY2012
Better Radiation Response and Accident Tolerance of Nanostructured Ceramic Fuel Materials?	University of Tennessee	$815,000	Researchers will use novel experimental methods to investigate the links between microstructure, phase stability and damage evolution in nanostructured ceramic fuel materials. The project will study fuel materials at temperatures and irradiation conditions relevant to operation and accidental scenarios.	Document	FCR&D	FY2012
Radiation and Thermal Effects on Used Nuclear Fuel and Nuclear Waste Forms	University of Tennesssee	$770,000	This project aims to investigate the structural and chemical response of used nuclear fuel and waste forms during interim storage and permanent disposal. If successful, this project will generate models that will allow the prediction of structural evolution and hence the radiological safety and security of nuclear fuel and waste forms.	Document	FCR&D	FY2012
Seismic Performance of Dry Casks Storage for Long-Term Exposure	University of Utah	$873,319	Researchers will evaluate the mechanical performance of dry-cask storage under seismic loading for mid-term operational periods. Simulations will include scenarios for freestanding, anchored, and vaulted casks. The experimental tests will also evaluate the dynamic seismic response of freestanding and anchored dry-cask storage prototypes, providing recommendations for optimal Interim Spent Fuel Storage Installations (ISFSIs) design.	Document	FCR&D	FY2012
Validation Experiments for Spent-Fuel Dry-Cask In-Basket Convection	Utah State University	$690,000	Researchers in this project aim to conduct experiments that generate data on natural convection through a fuel assembly. The data will be used to validate the computational models being developed for nuclear safety and design.	Document	FCR&D	FY2012
Re-Branding the Nuclear Fuel Cycle	Virginia Commonwealth University	$850,000	This project will create a comprehensive framework for the evaluation of alternative fuel cycle systems that will be used to identify and analyze key elements related to long-term management of nuclear fuels , with the ultimate goal to develop a communications strategy to reach stakeholders.	Document	FCR&D	FY2012
Advanced Characterization of Molecular Interactions in TALSPEAK-like Separations Systems	Washington State University	$875,000	Researchers will use advanced characterization techniques (experimental and computational) to improve understanding of the molecular level processes/interactions during separation processes for advanced fuel cycles. The understanding of these interactions will be used to develop more robust and streamlined separation processes for advanced fuel cycles.	Document	FCR&D	FY2012
Coupling of Nuclear Waste Form Corrosion and Radionuclide Transport in Presence of Relevant Repository Sediments	Washington State University	$885,000	Researchers will conduct experiments to understand the mechanisms responsible for the corrosion of nuclear waste forms in realistic chemical environments. The data generated from these experiments will enable increased reliability of the models used to predict the waste form performance in repository environments.	Document	FCR&D	FY2012
Stationary Liquid Fuel Fast Reactor (SLFFR) Concept for TRU Burning	Purdue University	$450,000	Reasearchers will investigate a new type of molten metallic fuel reactor concept that will consume hazardous transuranic waste. The liquid fuel alloy has several advantages over solid fuel fast reactors that are used for the same purpose.	Document	MSTR	FY2012
ABR for TRU Transmutation with Breed & Burn Thorium Blanket for Improved Economics and Resource Utilization	University of California- Berkeley	$450,000	The research team will use detailed neutronic analysis for a new Advanced Burner Reactor concept with low conversion ratio. The concept will use a new core shape to improve the utilization of neutrons to perform breed and burn.	Document	MSTR	FY2012
New Materials for High Temperature Thermoelecric Power Generation	University of California, Davis	$450,000	Reasearchers will work to develop nanostructured and other new materials to support the development of higher efficiency thermoelectric devices. These devices convert thermal energy to electricity with no moving parts. The new materials will operate at higher efficiencies and over a wider temperature range than those currently available--an important quality for future nuclear-powered deep space exploration.	Document	MSTR	FY2012
Microscopic Fuel Particles Produced by Self-Assembly of Actinide Nanoclusters on Carbon Nanomaterials	University of Notre Dame	$440,000	Reasearchers will develop the mechanisms, conditions and protocols to prepare uranium-carbon nanocomposite materials to make them more flexible. This could result in the generation of wholesale electricity, providing process heat, and providing power for households.	Document	MSTR	FY2012
High Hydrogen Content Graphene Hydride Compounds & High Cross-Section Cladding Coatings for Fast Neutron Detection	University of South Carolina	$430,000	This project will exploit recent breakthroughs to grow epitaxial graphene on commercial SiC wafers. This will allow researchers to develop a new detection method for fast neutrons. In addition, it will lead to better and more compact neutron detection system.	Document	MSTR	FY2012
Reducing Actinide Production Using Inert Matrix Fuels	University of Texas- Austin	$435,000	Reasearchers will perform a neutronic analysis, a thermal-hydraulic analysis and a simulation of fuel decay heat as a functionof fuel burnup, to determine if inert matrix fuel in coventional reactors will continue to be licensable. If successful, the inert matrix fuel mixtures will reduce harmful transuranic components in the fuel discharge streams at a level comparable to a fast reactcor burner.	Document	MSTR	FY2012
An Integrated Fuel Depletion Calculator for Fuel Cycle Options Analysis	University of Texas- Austin	$395,000	Reasearchers use new analysis techniques to better predict nuclear fuel behavior. The new model will allow improved fuel cycle for a larger number of users.	Document	MSTR	FY2012
Atomic-Scale to Meso-Scale Simulation Studies of Thermal Ageing and Irradiation Effects in Fe-Cr Alloys	Boston University	$874,997	Reasearchers will develop predictive, multi-scale simulation tools for iron-chromium alloys, which are expected to be key components of advanced steels envisioned as fuel cladding and structural components for Generation IV reactors. Such modeling is necessary to avoid resource intensive and costly thermal and neutron irradiation experiments to obtain required performance data.	Document	NEAMS	FY2012
Validation Data and Model Development for Fuel Assembly Response to Seismic Loads	George Washington University	$862,435	Reasearchers will conduct experiments that will provide comprehensive data characterizing the dynamics of the fluid and the structure in Pressurized Water Reactors (PWR) fuel assemblies under seismic loads (earthquakes and loss of coolant accidents). Completion of their project will greatly benefit the safety of existing and future nuclear reactors.	Document	NEAMS	FY2012
Uncertainty Quantification and Management for Multiscale Nuclear Materials Modeling	Georgia Institute of Technology	$743,444	Reasearchers will address the question of uncertainty propogation and error estimates associated with model prediction of material behavior under irradiation. Their work will facilitate a better understanding of the connection of various unit processes to collective responses in a multiscale model chain enabling the development of high strength and high ductility materials.	Document	NEAMS	FY2012
Fuel and Core Design Options to Overcome the Heavy Metal Loading Limit and Improve Performance and Safety of Liquid Salt Cooled Reactors	Georgia Insitute of Technology	$784,689	Reasearchers will examine new options for fuel and core designs in liquid salt cooled reactors where the current standard of TRISO type fuel has limitations due to loading characteristics. The research could enable new, more feasible fuel-core-reload options that will improve safety and performance parameters.	Document	RCRD&D	FY2012
Nonlinear Ultrasonic Techniques to Monitor Radiation Damage in RPV and Internal Components	Georgia Institute of Technology	$877,000	Reasearchers will explore new nondestructive materials evaluation and monitoring techniques utilizing nonlinear ultrasonic measurements . This technique will allow researchers to assess remaining useful life of select reactor components. Breakthroughs in this area will lead to the ability to characterize radiation damage in reactor pressure vessels and other components-leading to a clearer definition of reactor safety margins.	Document	RCRD&D	FY2012
Intergral Reactor Containment Condensation Model and Experimental Validation	Oregon State University	$871,119	Reasearchers will conduct experiments to enhance the safety and efficiency of small modular reactors (SMRs). This project will assess the impact of high-pressure steam condensation on steel containment vessels to be used for SMR deigns.	Document	RCRD&D	FY2012
Investigation of Natural Circulation Instability and Transients in Passively Safe Small Modular Reactors	Purdue University	$871,100	Reasearchers will perform scaled experiments to study the thermal-hydraulic instabilities that can occur in Small Modular Reactors (SMR) which rely on natural circulation cooling during normal operation and accident conditions. Their work will not only improve our understanding of general natural circulation instability but also lead to the development of stability criteria and predictability in the operation of SMRÃs.	Document	RCRD&D	FY2012
Thermoelectric-Driven Sustainable Sensing and Actuation Systems for Fault-Tolerant Nuclear Incidents	State University of New York, Stony Brook	$599,802	Reasearchers will examine the use of solid-state thermoelectric generators to produce electricity to sense and opeate during both normal and abnormal situations. This will provide indefinite monitoring of key components during power outages or station blackouts.	Document	RCRD&D	FY2012
Experimental and CFD Studies of Coolant Flow Mixing within Scaled Models of the Upper and Lower Plenums of NGNP Gas-Cooled Reactors	Texas A&M University	$713,051	Reasearchers will model the internal coolant flow of a prismatic core very high temperature reactor (VHTR) by using large eddy simulation tools. This method will enable more accurate prediction of flow field characteristics and better evaluation of VHTR behavior under operational and accidental conditions.	Document	RCRD&D	FY2012
Demonstrating Hybrid Heat Transport and Energy Conversion System Performance Characterization Using Intelligent Control Systems	University of Idaho	$877,000	Reasearchers will demonstrate an intelligent control systems in a hybrid energy conversion loop for a next generation nuclear power plant. Hybrid energy systems are a method of optimizing the use of natural resources for energy production. Hybrid systems present an opportunity to develop domestic energy sources to improve energy security.	Document	RCRD&D	FY2012
Advanced Reactor-Intermediate Heat Exchanger (IHX) Coupling: Theoretical Modeling and Experimental Validation	University of Idaho	$869,997	Reasearchers will model the behavior of the Advanced Reactor Intermediate Heat Exchanger Chemical Process system and develop advanced control techniques that take into account abnormal scenarios. The data and information obtained will assist in the development of intelligent control systems for next generation nuclear reactor systems.	Document	RCRD&D	FY2012
Irradiation Performance of Fe-Cr Base Alloys	University of Illinois- Urbana Champaign	$876,332	Reasearchers will perform post-radiation analysis and develop tools for future development and application of the Fe-Cr class of alloys. The results of this research will lead to better modeling of performance and development of an alloy designated as the primary choice for reactor fuel cladding and structural applications in advanced systems.	Document	RCRD&D	FY2012
Accelerated Irradiations for High Dose Microstructures in Fast Reactor Alloys	University of Michigan	$831,876	Reasearchers will determine the extent to which high dose rate irradiation can be used as an irradiation damage tool to understand microstructure evolution at high doses and temperatures relevant to advanced fast reactors. The project will provide fundamental understanding of the effectiveness of this process and thus of microstructure development in irradiated materials.	Document	RCRD&D	FY2012
Mitigating IASCC of Reactor Core Internals by Post-Irradiation Annealing Advanced Mitigation Strategies	University of Michigan	$876,985	Reasearchers will determine the optimum Post-irradiation annealing (PIA)-driven mitigation strategy to extend the potential lifetime of light water reactors. Samples that have already been irradiated in a light water reactor will be used to test PIA treatments to understand IASCC initiation and propoagation, annealing kinetics, the role of microstructure features in irradation hardening and localized deformation, and the optimum mitigation strategy based on PIA.	Document	RCRD&D	FY2012
Experimentally Validated Numerical Models for Effects of Non-Isothermal Turbulent Mixing on Wall Stresses in High Temperature Reactors	University of Pittsburgh	$876,422	Reasearchers will develop a comprehensive experimentally validated computational framework for the turbulent mixing in the lower plenum of a very high temperature reactor (VHTR). Through CFD modeling and experimental validation, the results from this project will lay the groundwork for future stress analysis, failure and fatigue studies, and uncertainty quantification for the VHTR system.	Document	RCRD&D	FY2012
Role of Defects in Swelling and Creep of Irradiated SiC	University of Wisconsin- Madison	$875,350	Reasearchers will study mechanisms controlling both radiation swelling and radiation creep in silicon carbide. These two effects are crucial to understanding the issues associated with the brittle silicon carbide composite. Success in this project will ground progress in the adoption of silicon carbide for reactor solutions, particularly as fuel cladding.	Document	RCRD&D	FY2012
Advanced Supercritical Carbon Dioxide Brayton Cycle Development	University of Wisconsin, Madison	$877,000	Reasearchers will investigate the benefits of utilizing advanced Brayton cycles with supercritical carbon dioxide in new reactor systems and components. Benefits of this research include improvement of analysis and performance of components currently utilizing these cycles as well as the potential for a large scale advanced CO2 power system.	Document	RCRD&D	FY2012
Mechanical Behavior of UO2 at Sub-grain Length Scales: Quantification of Elastic, Plastic and Creep Properties via Microscale Testing	Arizona State University	$800,000	Reasearchers will develop techniques to measure properties at sub-grain scales using depleted Uranium Oxide samples. The project will provide a framework to measure sub-grain scale mechanical properties, as well as provide experimental data to improve the understanding of advanced oxide fuels.	Document	FCR&D	FY2013
The Impacts of Pore-Scale Physical and Chemical Heterogeneities on the Transport of Radionuclide-Carrying Colloids	Colorado School of Mines	$800,000	Reasearchers will identify the dominant transport mechanisms to develop models that predict radionuclide distribution in porous materials. Experimental and computational models will be created that couple pore-scale geometric and interfacial structures. Simulators such as these are a necessary step towards fully predictive models for field-scale applications in the future.	Document	FCR&D	FY2013
Recovery of Uranium from Seawater: Polymer-Supported Aminophosphinates as Selective Extractants	Hunter College, CUNY	$399,999	Reasearchers will prepare a polymer-supported extractant for the recovery of uranium from seawater. The project will focus on primary amines that could provide a 3-fold increase in uranium capture capacity than current methods.	Document	FCR&D	FY2013
In-pile Thermal Conductivity Characterization with Single-laser Heating/Time Resolved Raman	Iowa State University	$800,000	Reasearchers will develop a time-resolved Raman-based thermal conductivity measurement system to improve remote in-pile thermal conductivity measurement. These measurements will provide new insights into the behavior of materials exposed to extreme radiation and temperature environments. Understanding the behavior of materials at the microstructural level will support optimized fuel designs.	Document	FCR&D	FY2013
Organic Speciation and Interactions in ALSEP - One Step Partitioning Process of Minor Actinides, Lanthanides, and Fission Products	Oregon State University	$600,000	Reasearchers will investigate the Actinide-Lanthanide Separation (ALSEP) process organic phase prior to aqueous phase separation and after aqueous separation phases of bare and metal-loaded acids. Quantifying these effects can be used to determine how an engineering scale process will perform and generate an accurate chemical model for the system.	Document	FCR&D	FY2013
Glass Composition and Solution Speciation Effects on Stage III Dissolution	Pennsylvania State University	$700,000	Reasearchers will study the chemical and structural triggers of long-term vitrified nuclear waste form behavior. They will study a range of waste glass compositions in corrosive environments. The study will improve understanding of the long-term residual rate and may provide new options for environmental control of glass dissolution rates.	Document	FCR&D	FY2013
Correlating Thermal, Mechanical, and Electrical Coupling Based Multiphysics Behavior of Nuclear Materials Through In-Situ Measurements	Purdue University	$800,000	Reasearchers will use in-situ experimental techniques to monitor the influence of extreme conditions on fuel cladding. The project will establish an in-situ experimental setup that can predict change in thermal properties and their correlation with mechanical properties and correlate such changes to changes in microstructural and chemical features.	Document	FCR&D	FY2013
Creation of a Geant4 Muon Tomography Package for Imaging of Nuclear Fuel in Dry Cask Storage	Purdue University	$440,000	Reasearchers will develop a simulation and analysis package to aid in the non-destructive assessment of sealed used nuclear fuel dry casks using cosmic ray muons. Cosmic ray muon tomography allows for non-destructive assessment that can independently verify and identify weapons grade material sealed within dense dry casks.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Two-stage Fast Reactor Fuel Cycle Options for Optimum Resource Utilization and Waste Management	Purdue University	$400,000	Reasearchers will evaluate the two different two-stage fast reactor fuel cycle options that will offer efficient use of uranium resources and the ability to burn actinides and long-live fission products. Evaluation of these fast fuel cycle options will serve as a useful complement to the options currently being considered in the Fuel Cycle Options Campaign.	Document	FCR&D	FY2013
Mixed Metal Phosphonate-Phosphate Resins for Separation of Lanthanides from Actinides	Texas A&M University	$650,000	Reasearchers will use ion exchangers to cleanly separate lanthanides and curium from reusable actinides. The study will assist in the development of an inexpensive, simple way in which to separate lanthanides from actinides found in used nuclear fuel rods and to recover a large portion of the usable fuel.	Document	FCR&D	FY2013
Safeguards in Pyroprocessing: an Integrated Model Development and Measurement Data Analysis	The Ohio State University	$626,151	Reasearchers will develop a comprehensive and effective safeguards approach for a pyroprocessing facility to support safeguards for future fuel cycles in the United States. The new approach and design will focus directly on the special nuclear materials in the electrorefiner where actinides are separated from fission products through electrochemical process.	Document	FCR&D	FY2013
Using Ionic Liquids for the Development of Renewable Biopolymer-Based Adsorbents for the Extraction of Uranium from Seawater and Testing Under Marine Conditions	University of Alabama	$400,000	Reasearchers will explore the fundamental engineering parameters for a renewable high-performance adsorbent for the extraction of uranium from sweater based on a recently proven ionic liquid (IL)-chitin platform. The project will use the platform to develop a versatile, modifiable adsorbent and characterize its performance and degradation in marine conditions.	Document	FCR&D	FY2013
Developing Ultra-Small Scale Mechanical Testing Methods and Microstructural Investigation Procedures for Irradiated Materials.	University of California, Berkeley	$800,000	Reasearchers will develop new small-scale mechanical testing techniques to allow for the estimation or direct measurement of bulk properties. The combined experiments and modeling will significantly enhance the statistics and information that can be obtained on small radioactive archived samples, as well as new ion beam irradiated specimens.	Document	FCR&D	FY2013
Improved Delayed-Neutron Spectroscopy Using Trapped Ions	University of California, Berkeley	$400,000	Reasearchers will develop innovative spectroscopy techniques to measure the decay of fission fragments. The resulting data from these new techniques will be used to better understand reactor kinetics under accident conditions and failure scenarios.	Document	FCR&D	FY2013
Thermally and Chemically Responsive Nanoporous Materials for Efficient Capture of Fission Product Gases	University of California, Davis	$750,000	Reasearchers will create new nanoporous materials that will be highly effective at capturing fission product gases. These materials would be relevant to both reactor fuels applications and reprocessing operations. Tests will be performed in carbon based and nitride based nanostructures, with the most promising materials from the modeling perspective undergoing further testing.	Document	FCR&D	FY2013
Multiphase Nanocrystalline Ceramic Concept for Nuclear Fuel	University of California, Irvine	$800,000	Researchers will study the use of nanoparticles and nanostructured ceramics to create new materials that can extend the service life and increase efficiency for nuclear fuel. Multiphase nanocrystalline ceramics will be used to design simulated nuclear fuel that can provide added plasticity, better radiation tolerance and improved thermal conductivity.	Document	FCR&D	FY2013
Development of Novel Porous Sorbents for Extraction of Uranium from Seawater	University of Chicago	$400,000	Reasearchers will develop a highly porous sorbent for the extraction of uranium from seawater. Previous research has established sorbent performance. This project will use past foundational studies to design and investigate a new nanocomposites that will be processed into tacks or braids for field tests in seawater tests. The technology may also be used for other metals.	Document	FCR&D	FY2013
Microwave Readout Techniques for Very Large Arrays of Nuclear Sensors	University of Colorado, Boulder	$799,937	Reasearchers will develop a powerful readout technique based on microwave transmission and reflection. The technique will enable very large arrays of diverse sensor types for nuclear materials quantification and tracking. It will provide more accurate data on material composition and quantity.	Document	FCR&D	FY2013
BiI3 Gamma-Ray Spectrometers for Reliable Room-Temperature Nuclear Materials Safeguarding	University of Florida	$799,999	Reasearchers will develop gamma-ray spectrometers based on BiI3 single crystals for MPACT applications such as burnup validation quantification, improved assay of plutonium, determination of uranium enrichment and overall monitoring spent fuel within the fuel cycle. The project will improve energy resolution, efficiency and environmental performance with this new gamma-ray detector.	Document	FCR&D	FY2013
Innovative Coating of Nanostructured Vanadium Carbide on the F/M Cladding Tube Inner Surface for Mitigating the Fuel Cladding Chemical Interactions	University of Florida	$760,276	Researchers will develop barrier coatings on the inner surface of fuel cladding tubes to improve performance of materials at elevated temperatures and high neutron exposures in fast reactors. The project will develop and test a low temperature coating process of nanostructured vanadium carbide that will provide a benchmark for use in future studies.	Document	FCR&D	FY2013
Doubling the Life of Concrete Structures	University of Idaho	$800,000	Reasearchers will use nanoscale techniques to develop methods for doubling the service life of concrete structures. They will study the effect of temperature load and temperature cycling (freezing and thawing) on the durability of concrete with nanoscale viscosity modifiers. The project will benefit from non-destructive evaluation of concrete performance through electrochemical techniques.	Document	FCR&D	FY2013
Off-Gas Treatment: Evaluation of Nano-structured Sorbents for Selective Removal of Contaminants	University of Idaho	$785,910	Reasearchers will evaluate nanostructured sorbent materials for their effectiveness in removing and immobilizing radionuclides for the off-gas treatment from used nuclear fuel recycling operations. The project aims at achieving near-zero emissions of radionuclides by capturing them from the off-gas of recycling operations, allowing for the development of advanced fuel cycles.	Document	FCR&D	FY2013
Innovative Elution Processes for Recovering Uranium and Transition Metals from Amidoxime-Based Sorbents	University of Idaho	$399,864	Reasearchers will develop a new two-step elution process to achieve total recovery of uranium and effective recycling of the sorbent. The extraction process would selectively remove uranium from the sorbent with little or no damage. The process would then remove transition metals and regenerate the sorbent for repeated use, making uranium extraction from seawater economically viable.	Document	FCR&D	FY2013
Performance of a Steel/Oxide Composite Waste Form for Combined Waste Streams from Advanced Electrochemical Processes over Geologic Time Scales	University of Illinois at Chicago	$700,000	Reasearchers will develop and validate a mechanistically-based corrosion model for cermet-type waste forms, creating a testing protocol and modeling approach for predicting long-term performance. The study will apply novel electrochemical testing and modeling methods to the behavior of metal/oxide phase boundaries to evaluate waste form performance.	Document	FCR&D	FY2013
Enhancement of the Extraction of Uranium from Seawater	University of Maryland, College Park	$400,000	Reasearchers will develop and optimize novel adsorbents for uranium recovery from seawater. The team will use radiation-induced grafting of organic phosphates onto polymers. The experiments will use ocean water, with mechanistic analysis, to provide a solid basis for large-scale demonstration of the performance of the new adsorbents in ocean environments.	Document	FCR&D	FY2013
Improving the Understanding of the Coupled Thermal-Mechanical-Hydrologic Behavior of Consolidating Granular Salt	University of New Mexico	$800,000	Reasearchers will increase the understanding of granular salt seal materials for shafts, drifts and boreholes. By coupling thermal, mechanical and hydrological responses, the study will result in greater confidence in granular salt consolidation as a principal strategy for closure and isolation of long-term waste repositories.	Document	FCR&D	FY2013
Fission Fragment Yield Data in Support of Advanced Reactor Technology	University of New Mexico	$399,816	Reasearchers will produce a highly accurate data set for thermal fission. These precision data are necessary for high-accuracy simulations of nuclear criticality, transmutation rates, radiation effects and heating as well as for nuclear fuel, material accounting and identification needs.	Document	FCR&D	FY2013
Molecular dynamics-based simulations of bulk/interfacial structures and diffusion behaviors in nuclear waste glasses	University of North Texas	$700,000	Reasearchers will generate accurate atomic structural models for use in Monte Carlo simulations of the dissolution of nuclear waste glasses. Large-scale molecular dynamics-based computer simulations will be used to investigate self-diffusion behaviors, interfacial structure, and other structures formed during dissolution of these glasses.	Document	FCR&D	FY2013
U3Si2 Fabrication and Testing for Implementation into the BISON Fuel Performance Code	University of South Carolina	$800,000	Reasearchers will fabricate, test and model a high uranium density, advanced nuclear fuel that operates at a much lower temperature and stores less energy. The work will deliver key research data on creep and grain growth, improving economics, through possible power uprates, and advancing accident tolerant fuels research.	Document	FCR&D	FY2013
Structural Health Monitoring of Nuclear Spent Fuel Storage Facilities	University of South Carolina	$738,618	Reasearchers will develop a nuclear structural health monitoring system based on a sensing technology that monitors material degradation and aging for dry cask storage systems. The low-cost, low-profile sensors will perform on-demand monitoring of the structural integrity of individual components as well as the entire system.	Document	FCR&D	FY2013
ORIGEN-based Nuclear Fuel Depletion Module for Fuel Cycle Assessment	University of Tennessee at Knoxville	$755,181	Reasearchers will develop a flexible reactor analysis module for the CYCLUS fuel cycle simulator based on established tools for reactor fuel depletion and decay. They will use ORIGEN, a mature and experimentally validated code, affording greater flexibility and allowing for accurate evaluations of impacts of both present and future fuel cycle options.	Document	FCR&D	FY2013
Cost and System Analysis of Innovative Fuel Resources Concepts	University of Texas at Austin	$295,960	_This project will develop and test braided polymer fiber adsorbents that surpass the sorption capacity, selectivity and durability of the best existing technology to recover uranium from seawater.	Document	FCR&D	FY2013
Risk Assessment of Structural Integrity of Transportation Casks	University of Utah	$789,296	Reasearchers will assess the loss of structural integrity of transportation casks and fuel cladding after extended storage. This risk assessment will conduct experimental tests and simulations to evaluate the structural performance of fuel, fuel assemblies and cask components when subjected to vibration and impact loads during transport.	Document	FCR&D	FY2013
Market-Based and System-Wide Fuel Cycle Optimization	University of Wisconsin, Madison	$612,731	Reasearchers will create market and economic optimizers to improve calculations for the CYCLUS fuel cycle simulator. The team will leverage existing optimization software frameworks within the simulator to resolve top level policy questions. The optimizations will allow CYCLUS to move beyond static material compositions, providing a holistic view of the fuel cycle system.		FCR&D	FY2013
Optical Fiber Based System for Multiple Thermophysical Properties for Glove Box, Hot Cell and In-Pile Applications	Utah State University	$799,975	Reasearchers will use a small pressure vessel to develop a robust technique for the measurement of multiple thermophysical properties at very high temperatures. The technique will lead to a system design moving toward the eventual measurement of irradiated fuels in a glovebox and/or hot cell with all sensors and electronics outside of the glovebox and/or hot cell.	Document	FCR&D	FY2013
Development of a Nano-Modified Concrete for Next Generation of Storage Systems	Vanderbilt University	$796,268	Reasearchers will use nano-sized and nano-structured particles based on enhanced reactivity to develop a superior concrete for the long-term storage of used nuclear fuel. The project will use state-of-the-art experimental chemical and mechanical characterizations and computation analysis to assess the performance of nano-modified concretes.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Thorium Fuel Cycle Options	Vanderbilt University	$797,995	Reasearchers will develop six fuel cycle data packages for multi-stage, thermal fuel cycles which incorporate thorium. These new fuel cycle data packages will provide the opportunity to examine fuel cycle options beyond those which have traditionally been considered. A thorium fuel cycle database will also be assembled as a basis for thorium literature for future evaluations of the thorium fuel cycle.	Document	FCR&D	FY2013
Enhanced Shielding Performance of HLW Storage Packages via Multi-Component Coatings	Virginia Polytechnic Institute and State University	$796,947	Reasearchers will develop a multi-layer composite that will enhance long-term storage and facilitate safe transport of storage packages. This novel multi-layer, multi-component coating would create an outer shield material that is resistant to the corrosion, radiation, diffusion and thermal cycling processes that affect fuel packages during long term storage.	Document	FCR&D	FY2013
Managing Zirconium Chemistry and Phase Compatibility in Combined Process Separations for Minor Actinide Partitioning	Washington State University	$700,000	Reasearchers will address unique challenges for combining TRUEX and TALSPEAK processes for partitioning of lanthanides and minor actinides. The project will develop improved information on the thermodynamics of fission product zirconium and develop a framework for an organic phase solvation model. Combined process development could streamline separations processes.	Document	FCR&D	FY2013
Advances in the Recovery of Uranium from Seawater: Studies Under Real Ocean Conditions	Woods Hole Oceanographic Institution	$398,882	Reasearchers will provide infrastructure and expertise for marine testing of currently available adsorbents in real ocean conditions. The team will move adsorbent research from the lab to field testing in order to quantify sorptive properties and uranium uptake. The project will provide valuable field data that will show the potential of large scale applications of these technologies.	Document	FCR&D	FY2013
NEUP Project 20-19172: Irradiation of Sensors and Adhesive Couplants for Application in LWR Primary Loop Piping and Components		$497,881	Reasearchers paln to attach ultrasonic transducers to substrates using various adhesive couplants that will be irradiated at elevated temperature to simulate LWR primary loop conditions at the PULSTAR reactor at North Carolina State University. Ultrasonic data will be taken in-situ. Subsequently, the sensors and couplant interfaces will be characterized using the LAMDA facility at ORNL. The results will be used to benefit a parallel EPRI project on online monitoring of cracks in LWR primary loop piping._	Document	R&D NSUF	FY2013
NEUP Project 20-19404: Extension of MSTDB to Provide a High-Quality, Validated Thermochemical Database for Predicting/Simulating Corrosion in Molten Salt Reactor SystemsUniversity of South Carolina		$600,000	Reasearchers will generate a validated, consistent database of initial fuel compositions and potential corrossion products of fluoride and chloride salts, allowing for important phenomena predictions in molten salt reactors to guide confident decisions. The database will be integral to the currently being developed Molten Salt Thermochemical Database (MSTDB), structured to allow use by commercial and open source codes._	Document	NEAMS	FY2013
Lower Length Scale Characterization and Validation of Formation and Stability of Helium Bubbles in Nano-structured Ferritic Alloys under Irradiation	Clemson University	$399,870	Reasearchers will provide a fundamental knowledge about the formation and stability of ultra-fine helium bubbles within 14YWT after neutron/ion irradiation for further design of new advanced structural materials with a characteristic high density nanoparticles feature which can increase the mechanical strength, hardness, irradiation resistance and the operational temperature range of materials.	Document	NEAMS	FY2013
Three-Dimensional Fuel Pin Model Validation by Prediction of Hydrogen Distribution in Cladding and Comparison with Experiment	Pennsylvania State University	$800,000	Reasearchers will validate important three-dimensional aspects of the fuel pin modeling by using specialized numerical modeling techniques coupled with laboratory experiments to validate existing models for predicting fuel performance in light water reactors.	Document	NEAMS	FY2013
Collocation-Based Surrogate Models for Uncertainty Quantification and Validation of Coupled, Multiphysics Fuel Performance Simulation Tools	University of Michigan	$596,835	Reasearchers will provide the necessary high fidelity, coupled, multiphysics fuel performance simulator for computational modeling and develop surrogates which will accelerate and focus the validation of the coupled codes. This will be achieved by utilizing the high fidelity coupled fuel performance, thermal-hydraulics and neutronics codes BISON/STAR-CCM+/MPACT and an innovative collocation-based surrogate methodology.	Document	NEAMS	FY2013
Multi-Resolution In-Situ Testing and Mutliscale Simulation for Creep Damage Fatigue Damage Analysis of Alloy 617	Arizona State University	$800,000	This project will develop novel testing and experimentally validated prediction methodologies for micro-structural damage mechanisms of structural materials for advanced reactor systems. The investigations will focus on the characterization and testing of specific metal alloys, but the proposed testing and life-prediction methodologies are applicable to other structural materials as well.	Document	RCRD&D	FY2013
Novel High Temperature and Radiation Resistant Infrared Glasses and Optical Fibers for Sensing in Advanced Small Modular Reactors	Clemson University	$800,000	Clemson University, in partnership with the Iowa State University and the Pacific Northwest National Laboratory, will develop novel optical materials with improved heat and radiation exposure resistance in order to enable in-vessel fiber optic sensing for advanced Small Modular Reactors.	Document	RCRD&D	FY2013
Validation Data Acquisition in HTTF during PCC Events	George Washington University	$800,000	Reasearchers at the George Washington University and Oregon State University will collaborate with NASA Langley Research Center to measure flow velocities in a high temperature test facility. This work supports the development of very-high temperature reactors with passive safety systems.	Document	RCRD&D	FY2013
Advanced High Temperature Inspection Capabilities for Small Modular Reactors	Iowa State University	$790,822	The objective of this project is to develop non-destructive evaluation techniques for advanced small modular reactors. The research will provide key enabling inspection technologies needed to support the design and the reactor component performance validation process for advanced small modular reactors.	Document	RCRD&D	FY2013
Experimental and Computational Investigations of Plenum-to-Plenum Heat Transfer under Natural Circulation in a Prismatic Very High Temperature Reactor	Missouri University of Science and Technology	$799,999	Reasearchers will perform experimental and computational investigations to study heat transfer and natural circulation phenomena in very-high temperature reactors. The study will assist in the ability to predict and analyze passive safety systems.	Document	RCRD&D	FY2013
New Mechanistic Models of Creep-Fatigue Crack Growth Interactions for Advanced High Temperature Reactor Components	Oregon State University	$790,790	Reasearchers will create and validate a robust, multi-scale, numerical model to predict material degradation in nickel-based reactor alloys. If successful, this project will provide better numerical tools for reactor designers and greatly improve their capability to design against material failures for reactor alloys in the long term.	Document	RCRD&D	FY2013
Self-Powered Wireless Dual-mode Langasite Sensor for Pressure/Temperature Monitoring of Nuclear Reactors	State University of New York, Stony Brook	$800,000	This research will develop a novel self-powered wireless hybrid sensor that can accurately monitor both pressure and temperature using a single device without requiring external electricity, even in extreme harsh environments.	Document	RCRD&D	FY2013
Compact Heat Exchanger Design and Testing for Advanced Nuclear Reactors and Advanced Power Cycles	The Ohio State University	$800,000	The goal of this project is to investigate optimal heat exchanger designs for advanced reactors. The research will study the optimization of printed circuit heat exchangers for specific fluids under a variety of conditions as well as perform numerical modeling. Experiments will focus on thermal performance and heat stress during extreme conditions.	Document	RCRD&D	FY2013
Fundamental Understanding of Creep-Fatigue Interactions in 9Cr-1MoV Steel Welds	The Ohio State University	$798,000	This project will advance the state of knowledge and fundamental understanding of deforming materials and welds under loading conditions. Specifically, new integrated testing procedures will be evaluated and applied for conditions that are most detrimental to material stability leading to improved predictions of life expectancy for reactor steels and welds.	Document	RCRD&D	FY2013
Advanced Mechanistic 3D Spatial Modeling and Analysis Methods to Accurately Represent Nuclear Facility External Event Scenarios	The Ohio State University	$800,000	Reasearchers will develop three-dimensional characterization uncertainty analysis for commercial power plants. The project will involve combining experts from the fields of seismic structural modeling and advanced methods of risk assessment. This effort is expected to result in next generation tools that can be used for assessment of seismic risks.	Document	RCRD&D	FY2013
Tritium Mitigation/Control for Advanced Reactor Systems	The Ohio State University	$400,000	Reasearchers will develop a fluoride salt cooled high-temperature reactor featuring a specialized system to control tritium production. If successful, this will result in a significant reduction in size and cost in comparison to other reactor designs.	Document	RCRD&D	FY2013
A Pebble-Bed Breed and Burn Reactor	University of California, Berkeley	$400,000	Reasearchers will assess the feasibility of designing a type of metal cooled reactor able to establish and maintain operation when fueled with depleted uranium. If successful, this reactor will offer at least a 30-fold increase in the uranium ore utilization versus that achieved in contemporary light water reactors without the need for fuel reprocessing and recycling.	Document	RCRD&D	FY2013
Investigation of Thermal Aging Effects on the Evolution of Microstructure and Mechanical Properties of Cast Duplex Stainless Steels	University of Maryland, College Park	$799,966	This research will provide a better understanding of the microstructural evolution and simultaneous change in mechanical response during aging. The results of the research will provide data that can be used to estimate degraded mechanical properties for an 80-year service life of light water reactors.	Document	RCRD&D	FY2013
Model validation using CFD-grade experimental database for NGNP Reactor Cavity Cooling Systems with water and air	University of Michigan	$799,348	Reasearchers will use advanced innovative instrumentation to build a high-resolution experimental database and to use the novel experimental data to assess and further develop the predictive capabilities of computer codes for thermal hydraulics and computational fluid dynamics. The improved models developed by this project will also have the direct benefit of improving the predictive capability of the passive systems of third generation light water reactors and small modular reactor systems.	Document	RCRD&D	FY2013
Long-Term Prediction of Emissivity of Structural Material for High Temperature Reactor Systems	University of Missouri	$799,117	Reasearchers will study specific types of emissivity driven cooling from a variety of materials that are relevant to nuclear reactors. The research will provide a basis for numerical modeling to support reactor development.	Document	RCRD&D	FY2013
Advanced I&C for Fault-Tolerant Supervisory Control of Small Modular Reactors	University of Pittsburgh	$800,000	The purpose of this research is to develop advanced instrumentation and control techniques for supervisory control of advanced small modular reactors. This research supports the operational goals of small modular reactor concepts through the development of improved oversight and surveillance techniques.	Document	RCRD&D	FY2013
Corrosion of Structural Materials for Advanced Supercritical Carbon-Dioxide Brayton Cycle	University of Wisconsin-Madison	$798,672	Reasearchers will study a variety of materials for corrosion resistance under conditions that improve power conversion. In addition to studying the corrosion resistance of the materials, researchers will study the effect of additives to mitigate corrosion. Development of corrosion theories and modeling aimed at prediction of long-term corrosion will be the underlying theme throughout the project.	Document	RCRD&D	FY2013
Component and Technology Development for Advanced Liquid Metal Reactors	University of Wisconsin-Madison	$798,920	In support of liquid metal cooled reactors, the University of Wisconsin, Madison will evaluate advanced alloys and ceramics that come in contact with liquid metals. Additionally, a robust oxygen sensor and for use in liquid metals will be developed in order to better evaluate corrosion profiles in support of diagnostic testing.	Document	RCRD&D	FY2013
A New Paradigm for Understanding Multi-phase Ceramic Waste Form Performance	Clemson University	$800,000	Researchers will use advanced characterization tools to develop 3-D microstructural data that can be incorporated into computer-based simulations in order to predict the performance of waste forms. Materials system modeling will incorporate elemental release and the interconnected microstructural network of phases to better understand performance and degradation, which will accelerate waste form acceptance in repository settings.	Document	FCR&D	FY2014
Controlling Hexavalent Americium: A Centerpiece to a Compact Nuclear Fuel Cycle	Colorado School of Mines	$800,000	Researchers will develop and exploit the fundamental chemistry of Americium to enable an industrially viable means to co-recover the major and minor actinide elements from used nuclear fuel. The results would be a significant step forward in the development of aqueous separations approaches designed to recover the U-Am actinides based on the availability of the hexavalent oxidation state.	Document	FCR&D	FY2014
Zeolite Membranes for Krypton/Xenon Separation from Spent Nuclear Fuel Reprocessing Off-Gas	Georgia Institute of Technology	$400,000	Researchers will develop a high-performance, lower-cost zeolitic membrane process for Kr/Xe separations during spent nuclear fuel processing. Current separation methods are not considered economical and a membrane process would have relatively lower cost, equipment size, and ambient operating temperature. The process would form a sound basis for further development of this transformative separation technology for the nuclear fuel cycle.	Document	FCR&D	FY2014
Optimizing Polymer-Grafted Amidoxime-based Adsorbents for Uranium Uptake from Seawater	Georgia Institute of Technology	$399,999	Researchers will work to increase the adsorbent capacity and selectivity toward uranium by optimizing the adsorbent morphology, synthesis variables, and conditioning parameters and by investigating the rate-limiting variables through transport and reaction modeling. A novel adsorption/partition concept that has the potential to substantially increase the adsorbent capacity will be tested, making uranium from seawater extraction more economically viable.	Document	FCR&D	FY2014
Extraction of Uranium from Seawater: Design and Testing of a Symbiotic System	Massachusetts Institute of Technology	$400,000	Researchers will develop a seawater uranium extraction system that will work symbiotically with an offshore windmill by utilizing the structure, mooring and power of the windmill, while increasing the energy harvested by the installation. Uranium will be extracted by an adsorbent polymer belt, which will be cycled through the seawater and an elution plant located at the base of the windmill tower. Increasing the frequency of harvesting could overcome current economic barriers to seawater uranium extraction.	Document	FCR&D	FY2014
Imaging a Dry Storage Cask with Cosmic Ray Muons	Oregon State University	$799,871	Researchers will develop an imaging system to monitor the content of a dry storage cask with cosmic ray muons. A very large amount of plutonium under nuclear safeguards is contained in used fuel assemblies stored in dry storage casks. Muon imaging will allow a cost effective and reliable way to evaluate dry storage cask content and integrity before transport.	Document	FCR&D	FY2014
Apatite and sodalite based glass-bonded waste forms for immobilization of 129I and mixed halide radioactive wastes	Rutgers University	$800,000	Researchers will develop advanced and chemically durable waste forms for immobilizing 129I (aqueous based reprocessing of fuel) and mixed-halide wastes (molten-salt processing of fuel) by low temperature synthesis. Halide-containing sodalite and calcium phosphate-based apatite minerals will be synthesized, consolidated and tested for chemical durability. The project will provide needed baseline data for the development of advanced waste forms for immobilization of iodine and mixed-halide wastes.	Document	FCR&D	FY2014
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$350,000	Researchers will develop modeling tools supported by experiments for off-gas capture from future nuclear-fuel recycling facilities. Target species include tritium, iodine, krypton, and xenon. The models are intended to provide path forward recommendations to develop off-gas treatment adsorption processes. The project will contribute to the evaluation of options for environmentally acceptable recycle systems.	Document	FCR&D	FY2014
Development of high performance ODS alloys	Texas A&M University	$800,000	Researchers will study swelling, radiation hardening and changes in mechanical properties of ODS alloys to develop two sets of advanced ODS alloys. Two sets of first-round candidate alloys that have already undergone extensive development and testing will evaluate irradiation performance. The study will meet the need for high strength, radiation-tolerant cladding and core components that have enhanced resistance to void swelling.	Document	FCR&D	FY2014
Rare Earth Electrochemical Property Measurements and Phase Diagram Development in a Complex Molten Salt Mixture for Molten Salt Recycle	The Ohio State University	$800,000	Researchers will investigate rare earth (RE) properties in complex molten salt mixtures. In a molten salt recycle approach, the RE drawdown by electrolysis is a key step in which REs are separated from salt containing other fission products. Investigation of RE electrolysis must consider the electrochemical properties of the REs. We propose to conduct studies of detailed experiments and corresponding models to provide the physical properties and phase diagrams required to predict the performance of RE drawdown for processing complex molten salts.	Document	FCR&D	FY2014
Studies of Lanthanide Transport in Metallic Nuclear Fuels	The Ohio State University	$800,000	Researchers will study the redistribution of lanthanides and migration of lanthanides to the fuel surface. The mechanisms of lanthanide transport in metallic fuel based on the novel discovery of a Ôliquid-likeÕ transport mechanism will be studied analytically and experimentally. The project will develop a fundamental understanding of lanthanide fission product migration and redistribution in advanced metallic nuclear fuels, and theory and data to mitigate fuel-cladding chemical interactions.	Document	FCR&D	FY2014
Computational and Experimental Studies of Microstructure-Scale Porosity in Metallic Fuels for Improved Gas Swelling Behavior	University of Arkansas	$796,823	Researchers will study the microstructure of metallic uranium alloy fuels, and their resistance to densification, to minimize in-pile irradiation swelling through bimodal pore size distribution. The project will develop a predictive approach to design metallic fuel microstructures for optimal swelling resistance and fission gas retention.	Document	FCR&D	FY2014
Improved Hybrid Modeling of Spent Fuel Storage Facilities	University of California, Berkeley	$645,393	Researchers will develop a variance reduction method for computational transport that will improve the ability to design and operate monitoring systems for interim used fuel installations through enhanced modeling and simulation. This new tool will demonstrate that modeling calculations can be done more accurately in less time than with current tools and will perform studies characterizing how changes in material, cask configurations, and number of casks could impact monitoring systems.	Document	FCR&D	FY2014
Selective ligands for uranyl via combinatorial peptoid libraries: A synthetic, structural, thermodynamic and computational study	University of California, Berkeley	$400,000	Researchers will study how donor ligands bind to the uranyl ion, UO22+, with the longer-term goal of using this information to tackle selective recognition of uranyl in aqueous solution. The study will impact underlying approaches to controlling the behavior of uranium in these systems. The actinide separation technology could be used in several areas including uranium extraction from seawater, nuclear waste remediation and nuclear materials.	Document	FCR&D	FY2014
Combining Experiments and Simulations of Extraction Kinetics and Thermodynamics in Advanced Separation Processes for Used Nuclear Fuel	University of California, Irvine	$799,938	Researchers will study how the kinetics and thermodynamics of metal ion extraction in advanced separation processes for used nuclear fuel can be described by molecular dynamic (MD) simulations and how the simulations can be validated by experimental data. The project would have broad impacts on several separations processes including advanced TALSPEAK, ALSEP and GANEX by increasing the confidence and accuracy of computer modeling of metal ion extraction._	Document	FCR&D	FY2014
Effect of Metallic Li on the Behavior of Metals in Molten Salts	University of Nevada, Reno	$458,250	Researchers will identify the effect of metallic lithium on materials that are used in molten salt recycling. The study will try to understand how the presence of Li(0) in molten salts affects the degradation of alloys. Studying these changes will help accurately predict container material behavior and longevity.	Document	FCR&D	FY2014
Assessment of Corrosion Resistance of Promising Accident Tolerant Fuel Cladding under Reactor Conditions	University of Notre Dame	$800,000	Researchers will assess the corrosion behavior of accident tolerant fuel candidate iron-based alloys under normal LWR operating conditions consisting of high temperature, relevant water chemistry and irradiation. The assessment will produce data about possible irradiation-accelerated corrosion rates of iron-based alloys, and the mechanisms by which such corrosion rates are accelerated. The project will advance the selection of appropriate replacements for Zircaloy cladding.	Document	FCR&D	FY2014
Functionalized Porous Organic Polymers as Uranium Nano-Traps for Efficient Recovery of Uranium from Seawaterr	University of South Florida	$399,000	Researchers will develop functionalized porous organic polymers, or Ônano-trapsÕ for extraction of uranium from seawater. This technique allows for increased surface area and custom-designed pore size and chemistry to fit specific parameters. The adsorbent materials have high efficiency and effectiveness for uranium recovery from seawater, providing a potential supply for nuclear fuel.	Document	FCR&D	FY2014
Enhanced Accident-Tolerant Fuel Performance and Reliability for Aggressive iPWR/SMR Operation	University of Tennessee	$799,967	To develop a process that evaluates operational and safety performance of reactor-and-fuel combinations by integrating whole-core 3D neutronics with MOOSE/BISON fuel performance assessments via explicit time and space dependent fuel rod operational power histories. The project will be valuable in analyzing and evaluating accident tolerant fuel concepts and furthering the understanding of reactor physics and fuel performance aspects of key accident tolerant fuel concepts.	Document	FCR&D	FY2014
Nuclear Technology R&D Strategies in an Era of Energy Price Uncertainty	University of Texas, Austin	$799,112	Researchers will identify nuclear technology options that are competitive over a wide range of plausible future business environments. No single nuclear technology or business practice will be the best choice across all or even most future conditions. The study will focus on hybrid nuclear-fossil technologies, energy storage and conversion, which will result in an identification of nuclear strategies that can succeed under future market conditions.	Document	FCR&D	FY2014
Development and Optimization of Voltammetric Methods for Real Time Analysis of Electrorefiner Salt with High Concentrations of Actinides and Fission Products	University of Utah	$621,612	Researchers will develop an advanced voltammetry method to pursue the objective of real time monitoring of actinide concentrations in electrorefiner salt. This will include experimental measurement of key parameters such as activity coefficients and exchange current density. It will also involve simulation of voltammetry processes based on first principles. The project will allow for real time measurements that could support the commercialization of pyroprocessing.	Document	FCR&D	FY2014
Development of Self-Healing Zirconium-Silicide Coatings for Improved Performance of Zirconium-Alloy Fuel Cladding	University of Wisconsin, Madison	$798,621	Researchers will study the deposition of self-healing zirconium-silicide coatings on zirconium-alloy fuel cladding material to improve corrosion resistance under normal and accident conditions. Under these conditions, Zr-Si coating evolves into a highly protective functionally-graded multilayered system. The study will lead to improved performance of zirconium-alloy fuels._	Document	FCR&D	FY2014
Thermal Conductivity in Metallic Fuels	Virginia Polytechnic Institute and State University	$799,837	Researchers will calculate the thermal conductivity of metallic uranium and neptunium alloys, including the effects of noble gasses, using density functional theory. The experiments will validate the calculated effective thermal conductivity using the MARMOT code and by helping determine DFT simulation parameters. The study works to improve fuel lifetime by understanding its thermal behavior.	Document	FCR&D	FY2014
SiC-ODS Alloy Gradient Nanocomposites as Novel Cladding Materials	Virginia Polytechnic Institute and State University	$799,998	Researchers will combine nuclear nanomaterial design, processing, testing, and characterization efforts to develop revolutionary materials that can withstand neutron irradiation for long period of time using nanostructured SiC and oxide dispersion strengthened steel. The ultimate objective is to offer new cladding materials with increased corrosion resistance, strength, and creep resistance in both steady state and accident conditions.	Document	FCR&D	FY2014
Experimental Breeder Reactor II Benchmark Evaluation	Idaho State University	$400,000	Researchers will develop a benchmark evaluation of the Experimental Breeder Reactor II (EBR-II). During nearly 30 years of operation numerous experiments were conducted at EBR-II. The most significant of these experiments were conducted in 1986 demonstrating inherent safety features in loss of flow without reactor scram and loss of heat sink without reactor scram. Benchmark evaluation will be valuable for the reactor design efforts in the United States and South Korea.	Document	MSNE	FY2014
Integral full core multi-physics PWR benchmark with measured data	Massachusetts Institute of Technology	$400,000	Researchers will introduce BEAVRS, a new multi-cycle full-core Pressurized Water Reactor (PWR) depletion benchmark based on two operational cycles of a commercial nuclear power plant. This project aims at addressing the uncertainty quantification of the measured data and on making this benchmark a true non-proprietary international benchmark for the validation of high-fidelity multi-physics computational tools.	Document	MSNE	FY2014
Benchmark Evaluation of PROTEUS Gas-Cooled Reactor Experiments	University of Florida	$400,000	Researchers will create International Reactor Physics Experiment Evaluation Project (IRPhEP) benchmarks using data from 1970s experiments of the neutronics of gas-cooled fast reactor (GCFR) designs investigated in the PROTEUS reactor. The GCFR-PROTEUS experiments fill a gap in current integral benchmark data. These experiments can provide validation of computational models and nuclear data for next generation reactors.	Document	MSNE	FY2014
An Investigation To Establish Multiphysical Property Dataset Of Nuclear Materials Based On In-Situ Observations And Measurements	Purdue University	$800,000	Researchers will create an in-situ measurement based experimental approach to develop experimental validation dataset for NEAMS based code validation. Particular emphasis is on supplying data set for multiphysics simulations in extreme conditions as a function of material microstructure.	Document	NEAMS	FY2014
Experimental Validation of UO2 Microstructural Evolutions for NEAMS tool MARMOT	University of Florida	$798,000	Researchers will experimentally validate MARMOT for predicting the microstructural evolutions of UO2 oxide fuel under the driving forces of high temperatures and large temperature gradient in reactors. By performing the experiments and simulations simultaneously using precisely defined initial conditions, the experiment data will provide direct benchmarking of the MARMOT code.	Document	NEAMS	FY2014
High-resolution time-resolved experiments on mixing and entrainment of buoyant jets in stratified environments	University of Michigan	$799,983	Researchers will study high spatial and time-resolution experimental data of the fluid dynamics phenomena of flow jets interacting with a stratified layer. The issue plays an important role in the safety of several reactor designs, including sodium-cooled reactors. The data addresses the NEAMS needs for the validation of high fidelity computational fluid dynamics methodologies.	Document	NEAMS	FY2014
Fundamental study of key issues related to advanced S-CO2 Brayton Cycle: prototypic HX development and Cavitation	Georgia Institute of Technology	$799,000	Researchers will study scientific and operational issues pertinent to compact heat exchanger systems and turbo-machinery. The project will work to resolve issues with the fabrication of diffusion bonded compact heat exchangers, alternate heat exchange technology for recuperators, and resolution of issues with cavitation and fluid instabilities.	Document	RCRD&D	FY2014
Advanced Models for Nondestructive Evaluation of Aging Nuclear Power Plant Cables	Iowa State University	$787,291	Researchers will develop advanced models that relate environmentally induced microstructural and chemical changes in cable insulation polymers to their macroscopic electrical parameters. These parameters will be measured and modeled over a wide range of the electromagnetic spectrum, covering several potential nondestructive evaluation techniques, enabling identification of the most sensitive techniques for future development.	Document	RCRD&D	FY2014
Development of Novel Functionally Graded Transition Joints for Improving the Creep Strength of Dissimilar Metal Welds in Nuclear Applications	Lehigh University	$800,000	Researchers will develop graded transition joints and improved creep life models for increasing the life of dissimilar metal welds (DMWs) in nuclear reactors. The research represents the first application of functionally graded material concepts for solving the problem of DMW failures through an integrated approach of additive manufacturing, modeling, microstructural characterization, and advanced strain-sensing techniques.	Document	RCRD&D	FY2014
Feasibility Assessment of a Micro Modular Reactor (MMR)	North Carolina State University	$400,000	Researchers will develop an innovative compact reactor concept that integrates power production, power conversion and electricity generation in a single unit: the Micro Modular Reactor (MMR). It is designed to be absolutely melt-down proof (MDP) under all circumstances including complete loss of coolant scenarios with no possible release of radioactive material, to have a cycle length of greater than 10 years, and to be highly proliferation resistant.	Document	RCRD&D	FY2014
Scaling Studies for Advanced Gas Reactor Concepts	Oregon State University	$681,834	Researchers will expand the utilization of the Oregon State University High Temperature Test Facility (HTTF) to validate a broader range of advanced high temperature reactors and events. The facility will be revised to add a detailed scaling analysis of additional gas reactor concepts including advanced gas-cooled, molten salt, and sodium cooled reactors.	Document	RCRD&D	FY2014
Fluid Stratification Separate Effects Analysis, Testing and Benchmarking	Oregon State University	$800,000	Researchers will study fluid stratification in high temperature gas reactors. Coolant stratification is the result of incomplete mixing of one or more fluids, leading to a density gradient, which may or may not dissipate under diffusive or convective effects. This combined analytical and experimental project seeks to investigate stratification driven by diffusive and convective mechanisms and is expected to yield insight into this phenomenon.	Document	RCRD&D	FY2014
Probabilistic Economic Valuation of Safety Margin Management Analysis	Oregon State University	$795,364	Researchers will use RAVEN and develop a companion software package to facilitate economic analysis of safety margins. The project is a proof of concept that will use techniques to examine the cost of improving safety margins vs. the risk of accidents from not improving safety margins. This analysis can be used to evaluate the economic viability of various plant upgrades.	Document	RCRD&D	FY2014
Novel Dissimilar Joints Between Alloy 800H and 2.25%Cr and 1%Mo Steel	Pennsylvania State University	$800,000	Researchers will fabricate and test dissimilar metal joints between a nickel base alloy and a steel with gradual variations of chemical composition, microstructure and properties in a manner that reduces abrupt thermal expansion mismatch and the resulting residual stresses. Data on structure and properties will serve as valuable inputs for the initiation of an ASME code case.	Document	RCRD&D	FY2014
Multi-Phase Model Development to Assess RCIC System Capabilities under Severe Accident Conditions	Texas A&M University	$564,246	Researchers will develop physics-based models of the Reactor Core Isolation Cooling (RCIC) System and incorporating them into a multi-phase code for validation. The project will tackle the current major challenges in RCIC System analysis and enable evaluation of two-phase thermodynamic aspects.	Document	RCRD&D	FY2014
Experimental Investigation and CFD Analysis of Steam Ingress Accidents in HTGRs	The Ohio State University	$800,000	Researchers will study the steam ingress scenario for HTGRs. The study will investigate thermal-hydraulic behavior and graphite oxidation of stream ingress phenomena to validate predictive CFD models. This work will resolve concerns about possible steam generator tube ruptures in a HTGR He-Steam Rankine cycle.	Document	RCRD&D	FY2014
Coiled Tube Gas Heaters For Nuclear Gas-Brayton Power Conversion	University of California, Berkeley	$800,000	Researchers will develop heat exchangers for Brayton-cycle power conversion in reactors using sodium, NaK, or salt as intermediate coolants. The proposed coiled tube gas heaters (CTGHs) are expected to have excellent power density, thermal shock/creep, in-service inspection, and reparability characteristics.	Document	RCRD&D	FY2014
Fundamental Studies of Irradiation-Induced Modifications in Microstructural Evolution and Mechanical Properties of Advanced Alloys	University of Illinois, Urbana-Champaign	$800,000	Researchers will develop and test a mechanism for predicting neutron irradiation performance for optimized Grade 92 and Alloy 709 for applications in advanced reactor systems. The work will employ ion irradiations and available information from neutron irradiations of related alloys to develop a basis for predicting the neutron irradiation performance of the optimized alloys.	Document	RCRD&D	FY2014
Integrated Computational and Experimental Study of Radiation Damage Effects in Grade 92 Steel and Alloy 709	University of Tennessee	$800,000	Researchers will develop a mechanistic understanding and predictive models of irradiation-induced microstructural evolution and resulting mechanical properties in optimized ferritic-martensitic Grade 92 steel and austenitic alloy 709 using multiscale simulations coupled with rigorous experimental validation. The project will provide insights into the correlation between ion irradiation and fast neutron damage.	Document	RCRD&D	FY2014
Meta-Level Design Guidance and Operator Performance Measures for Hybrid Control Rooms	Vanderbilt University	$799,869	Researchers will apply human factors engineering methods and relevant expertise from non-nuclear high-risk high-consequence domains toward the measurement of operator performance in analog, digital, and hybrid main control rooms. Performance measures will be developed for evaluating the situation awareness and decision-making proficiencies to support the transition to digital or hybrid control room displays.	Document	RCRD&D	FY2014

FY 2016 Research and Development Awards

The Energy Department is awarding over $35.5 million through its Nuclear Energy University Programs (NEUP) to support 48 university-led nuclear energy research and development projects to develop innovative technologies and solutions. These projects will be led by 31 U.S. universities in 24 states.

A complete list of R&D projects with their associated abstracts is available below.

Title	Institution	Estimated Funding*	Project Description	Abstract	Project Type	Fiscal Year
Neutron Damage and MAX Phase Ternary Compounds	Drexel University			Document	IIR	FY2009
Atomistic Calculations of the Effect of Minor Actinides on Thermodynamic and Kinetic Properties of UO2+x	Georgia Institute of Technology			Document	IIR	FY2009
Maximum Fuel Utilization in Fast Reactors without Chemical Reprocessing	University of California, Berkeley			Document	IIR	FY2009
Developing a High Thermal Conductivity Fuel with Silicon Carbide Additives	University of Florida			Document	IIR	FY2009
Fabrication of Tungsten-Rhenium Cladding Materials via Spark Plasma Sintering for Ultra High Temperature Reactor Applications	University of Idaho			Document	IIR	FY2009
Ionic Liquid and Supercritical Fluid Hyphenated Techniques for Dissolution and Separation of Lanthanides, Actinides, and Fission Products	University of Idaho			Document	IIR	FY2009
Improved Fission Neutron Data Base for Active Interrogation of Actinides	University of Michigan			Document	IIR	FY2009
Utilization of Methacrylates and Polymer Matrices for the Synthesis of Ion Specific Resins	University of Nevada, Las Vegas			Document	IIR	FY2009
Improved LWR Cladding Performance by EPD Surface Modification Technique	University of Wisconsin, Madison			Document	IIR	FY2009
Advanced Models of LWR Pressure Vessel Embrittlement for Low Flux-High Fluence Conditions	University of California, Santa Barbara			Document	LWRS	FY2009
Irradiation Creep in Graphite	Boise State University			Document	NGNP	FY2009
Modeling the Stress Strain Relationships and Predicting Failure Probabilities For Graphite Core Components	Cleveland State University			Document	NGNP	FY2009
TRISO-Coated Fuel Durability Under Extreme Conditions	Colorado School of Mines			Document	NGNP	FY2009
An Innovative and Advanced Coupled Neutron Transport and Thermal Hydraulic Method (Tool) for the Design, Analysis and Optimization of VHTR/NGNP Prismatic Reactors	Georgia Institute of Technology			Document	NGNP	FY2009
Removal of 14C from Irradiated Graphite for Graphite Recycle and Waste Volume Reduction	Idaho State University			Document	NGNP	FY2009
Millimeter-Wave Thermal Analysis Development and Application to Gen IV Reactor Materials	Massachusetts Institute of Technology			Document	NGNP	FY2009
Accurate Development of Thermal Neutron Scattering Cross Section Libraries	North Carolina State University			Document	NGNP	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
Understanding Creep Mechanisms in Graphite with Experiments, Multiscale Simulations, and Modeling	North Carolina State University			Document	NGNP	FY2009
Simulations of the Thermodynamic and Diffusion Properties of Actinide Oxide Fuel Materials	University of Michigan			Document	AFCI	FY2009
Verification & Validation of High-Order Short-Characteristics-Based Deterministic Transport Methodology on Unstructured Grids	North Carolina State University			Document	NGNP	FY2009
Adsorptive Separation and Sequestration of Krypton, I and C14 on Diamond Nanoparticles	University of Missouri, Columbia			Document	AFCI	FY2009
Microscale Heat Conduction Models and Doppler Feedback	North Carolina State University			Document	NGNP	FY2009
Fundamental Understanding of Ambient and High-Temperature Plasticity Phenomena in Structural Materials in Advanced Reactors	Georgia Institute of Technology			Document	AFCI	FY2009
Development of Alternative Technetium Waste Forms	University of Nevada, Las Vegas			Document	AFCI	FY2009
Optimizing Neutron Thermal Scattering Effects in Very High Temperature Reactors	North Carolina State University			Document	NGNP	FY2009
Advanced Elastic/Inelastic Nuclear Data Development Project	Idaho State University			Document	AFCI	FY2009
Heterogeneous Recycling in Fast Reactors	Massachusetts Institute of Technology			Document	AFCI	FY2009
Quantification of UV-Visible and Laser Spectroscopic Techniques for Materials Accountability and Process Control	University of Nevada, Las Vegas			Document	AFCI	FY2009
Multiaxial Creep-Fatigue and CreepRatcheting Failures of Grade 91 and Haynes 230 Alloys Toward Addressing Design Issues of Gen IV Nuclear Power Plants	North Carolina State University			Document	NGNP	FY2009
Thermodynamic Development of Corrosion Rate Modeling in Iron Phosphate Glasses	Missouri University of Science and Technology			Document	AFCI	FY2009
Development of Subspace-Based Hybrid Monte Carlo-Deterministic Algorithms for Reactor Physics Calculations	North Carolina State University			Document	AFCI	FY2009
High-Fidelity Space-Time Adaptive Multiphysics Simulations in Nuclear Engineering	University of Nevada, Reno			Document	AFCI	FY2009
Improvements to Nuclear Data and Its Uncertainties by Theoretical Modeling	Rensselaer Polytechnic Institute			Document	AFCI	FY2009
Investigation of Countercurrent Helium-air Flows in Air-ingress Accidents for VHTRs	Ohio State University			Document	NGNP	FY2009
Sharp Interface Tracking in Rotating Microflows of Solvent Extraction	State University of New York at Stony Brook			Document	AFCI	FY2009
Bulk Nanostructured FCC Steels with Enhanced Radiation Tolerance	Texas A&M University			Document	AFCI	FY2009
Simulations of Failure via Three-Dimensional Cracking in Fuel Cladding for Advanced Nuclear Fuels	University of Texas, Dallas			Document	AFCI	FY2009
Testing of Performance of Optical Fibers Under Irradiation in Intense Radiation Fields, When Subjected to Very High Temperatures	Ohio State University			Document	NGNP	FY2009
Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels	Texas A&M University			Document	AFCI	FY2009
SiC Schottky Diode Detectors for Measurement of Actinide Concentrations from Alpha Activities in Molten Salt Electrolyte	The Ohio State University			Document	AFCI	FY2009
Computational Design of Advanced Nuclear Fuels	University of California, Davis			Document	AFCI	FY2009
Advanced Mesh-Enabled Monte Carlo Capability for Multi-Physics Reactor Analysis	University of Wisconsin, Madison			Document	AFCI	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
A Distributed Fiber Optic Sensor Network for Online 3-D Temperature and Neutron Fluence Mapping in a VHTR Environment	Texas A&M University			Document	NGNP	FY2009
Ab Initio Enhanced Calphad Modeling of Actinide Rich Nuclear Fuels	University of Wisconsin, Madison			Document	AFCI	FY2009
Investigation on the Core Bypass Flow in a Very High Temperature Reactor	Texas A&M University			Document	NGNP	FY2009
Development of Diffusion Barrier Coatings and Deposition Technologies for Mitigating Fuel Cladding Chemical Interactions (FCCI)	University of Wisconsin, Madison			Document	AFCI	FY2009
CFD Model Development and Validation for High Temperature Gas Cooled Reactor Cavity Cooling System (RCCS) Applications	Texas A&M University			Document	NGNP	FY2009
Thermal Properties of LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin, Madison			Document	AFCI	FY2009
Study of Air ingress across the duct during the accident conditions	Texas A&M University			Document	NGNP	FY2009
Verification of the CENTRM Module for Adaptation of the SCALE Code to NGNP Prismatic and PBR Core Designs	University of Arizona			Document	NGNP	FY2009
Integral and Separate Effects Tests for Thermal Hydraulics Code Validation for Liquid-Salt Cooled Nuclear Reactors	University of California, Berkeley			Document	NGNP	FY2009
Mechanisms Governing the Creep Behavior of High Temperature Alloys for Generation IV Nuclear Energy Systems	University of Cincinnati			Document	NGNP	FY2009
ALD Produced B2O3, Al2O3 and TiO2 Coatings on Gd2O3 Burnable Poison Nanoparticles	University of Colorado, Boulder			Document	NGNP	FY2009
Experimental Study and Computational Simulations of Key Pebble Bed Thermomechanics Issues for Design and Safety	University of Idaho			Document	NGNP	FY2009
Prediction and Monitoring Systems of Creep-Fracture Behavior of 9Cr-1Mo Steels for Reactor Pressure Vessels	University of Idaho			Document	NGNP	FY2009
Understanding Fundamental Material Degradation Processes in High Temperature Aggressive Chemomechanical Environments	University of Illinois, Urbana-Champaign			Document	NGNP	FY2009
Multi-Scale Multi-physics Methods Development for the Calculation of Hot-Spots in the NGNP	University of Michigan			Document	NGNP	FY2009
Corrosion and Creep of Candidate Alloys in High Temperature Helium and Steam Environments for the NGNP	University of Michigan			Document	NGNP	FY2009
Creation of a Full-Core HTR Benchmark with the Fort St. Vrain Initial Core and Validation of the DHF Method with Helios for NGNP Configurations	University of Michigan			Document	NGNP	FY2009
Fission Product Sorptivity in Graphite	University of Missouri, Columbia			Document	NGNP	FY2009
Identifying and Understanding Environment-Induced Crack Propagation Behavior in Ni-Based Superalloy INCONEL 617	University of Nevada, Las Vegas			Document	NGNP	FY2009
Graphite Oxidation Simulation in HTR Accident Conditions	University of New Mexico			Document	NGNP	FY2009
Non Destructive Thermal Analysis and In Situ Investigation of Creep Mechanism of Graphite and Ceramic Composites using Phase-sensitive THz Imaging & Nonlinear Resonant Ultrasonic Spectroscopy	University of Rochester			Document	NGNP	FY2009
Tritium Sequestration in Gen IV NGNP Gas Stream via Proton Conducting Ceramic Pumps	University of South Carolina			Document	NGNP	FY2009
Materials, Turbomachinery and Heat Exchangers for Supercritical CO2 Systems	University of Wisconsin, Madison			Document	NGNP	FY2009
Experimental Studies of NGNP Reactor Cavity Cooling System with Water	University of Wisconsin, Madison			Document	NGNP	FY2009
Assessment of Embrittlement of VHTR Structural Alloys in Impure Helium Environments	University of Wisconsin, Madison			Document	NGNP	FY2009
Modeling Fission Product Sorption in Graphite Structures	University of Wisconsin, Madison			Document	NGNP	FY2009
Liquid Salt Heat Exchanger Technology for VHTR Based Applications	University of Wisconsin, Madison			Document	NGNP	FY2009
Effect of Post-Weld Heat Treatment on Creep Rupture Properties of Grade 91 Steel Heavy Section Welds	Utah State University			Document	NGNP	FY2009
Alpha Radiolysis of Nuclear Solvent Extraction Ligands used for An(III) and Ln(III) Separations	California State University, Long Beach	$1,390,252		Document	FCR&D	FY2010
Predictive Maturity of Multi-Scale Simulation Models for Fuel Performance	Clemson University	$614,690		Document	FCR&D	FY2010
Freeze-casting as a Novel Manufacturing Process for Fast Reactor Fuels	Drexel University	$1,149,327		Document	FCR&D	FY2010
Fuel Performance Experiments on the Atomistic Level, Studying Fuel Through Engineered Single Crystal UO2	Idaho State University	$650,000		Document	FCR&D	FY2010
Development of A Self Biased High Efficiency Solid-State Neutron Detector for MPACT Applications	Rensselaer Polytechnic Institute	$810,141		Document	FCR&D	FY2010
Development of a Innovative High Thermal Conductivity UO 2 Ceramic Composites Fuel Pellets with Carbon Nano-Tubes Using Spark Plasma Sintering	University of Florida	$894,042		Document	FCR&D	FY2010
Exploration and Modeling of Structural Changes in Waste Glass under Corrosion	Pennsylvania State University	$1,377,444		Document	FCR&D	FY2010
Evaluation of materials for interim storage of spent fuel for more than 100 years	University of Michigan	$931,603		Document	FCR&D	FY2010
Implementation of On-the-Fly Doppler Broadening in MCNP5 for Multiphysics Simulation of Nuclear Reactors	University of Michigan	$406,712		Document	FCR&D	FY2010
Methods and tools to allow molecular flow simulations to be coupled to higher level continuum descriptions of flows in porous/fractured media and aerosol/dust dynamics	University of Missouri-Columbi	$541,286		Document	FCR&D	FY2010
Characterization and Modeling of Materials for Kr-Xe Separations	University of Nevada-Las Vegas	$989,800		Document	FCR&D	FY2010
Modeling Solute Thermokinetics in LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin-Madison	$616,073		Document	FCR&D	FY2010
Advanced Aqueous Separation Systems for Actinide Partitioning: Develop Fundamental Understanding of An(III)/Ln(III) Separation	Washington State University	$1,451,784		Document	FCR&D	FY2010
Consistent Multigroup Theory Enabling Accurate Coarse-Group Simulation of GenIV Reactors	Georgia Institute of Technology	$1,046,277		Document	GEN IV	FY2010
Studies of Deteriorated Heat Transfer in Prismatic Cores Stemming from Irradiation-Induced Geometry Distortion	Idaho State University	$1,287,921		Document	GEN IV	FY2010
Carbide Coatings for Nickel Alloys, Graphite, and Carbon/Carbon Composites to be Used in Fluoride Salt Valves	Johns Hopkins University	$1,183,239		Document	GEN IV	FY2010
Design, Testing, and Modeling of the Direct Reactor Auxiliary Cooling System for AHTRs	Ohio State University	$1,366,627		Document	GEN IV	FY2010
Monitoring microstructural evolution of Alloy 617 with nonlinear acoustics for remaining useful life prediction; multiaxial creep-fatigue and creep-ratcheting	Pennsylvania State University	$1,000,000		Document	GEN IV	FY2010
Development and Validation of Multidimensional Models of Supercritical CO 2 Energy Conversion Systems for Nuclear Power Reactors	Rensselaer Polytechnic Institute	$475,005		Document	GEN IV	FY2010
Multiscale Concrete Modeling for Aging Degradation	Mississippi State University	$345,941		Document	LWRS	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term and Elevated Temperature Irradiation: Modeling and Experimental Investigation	University of California-Berkeley	$1,320,667		Document	GEN IV	FY2010
Development of an advanced computational fluid dynamics technology for the next-generation nuclear reactor system analysis and safety margin characterization code	North Carolina State University	$418,199		Document	LWRS	FY2010
Development of Barrier Layers for the Protection of Candidate Alloys in the VHTR	University of California-Santa Barbara	$995,232		Document	GEN IV	FY2010
Precursor Derived Nanostructured Si-C-X Materials for Nuclear Applications	University of Washington	$899,518		Document	MRIIR	FY2010
Investigation of a Novel NDE Method for Monitoring Thermo-Mechanical Damage and Microstructure Evolution in Ferritic-Martensitic Steels for Generation IV Nuclear Energy Systems	University of Cincinnati	$833,109		Document	GEN IV	FY2010
Development and Testing of an Open-Loop Oscillator for Small Reactivity Worth Samples	Idaho State University	$597,252		Document	MRIIR	FY2010
Fission Product Transport in TRISO Particle Layers under Operating and Off-Normal Conditions	University of Michigan	$966,581		Document	GEN IV	FY2010
Understanding the Irradiation Behavior of Zirconium Carbide	Pennsylvania State University	$870,613		Document	MRIIR	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term Irradiation at Elevated Temperature: Critical Experiments	University of Michigan	$1,181,379		Document	GEN IV	FY2010
Modeling investigation of the stability and irradiation-induced evolution of nanoscale precipitates in advanced structural materials	University of Tennessee-Knoxville	$380,653		Document	MRIIR	FY2010
Three-dimensional NDE of VHTR Core Components via Simulation-based Testing	University of Minnesota	$1,366,163		Document	GEN IV	FY2010
Investigation of Laser Shock Peening for Enhancing Fatigue and Stress Corrosion Cracking Resistance of Nuclear Energy Materials	University of Cincinnati	$1,242,019		Document	MRIIR	FY2010
Failure Predictions for VHTR Core Components using a Probabilistic Continuum Damage Mechanics Model	University of Minnesota	$854,542		Document	GEN IV	FY2010
Irradiation Accelerated Corrosion of Reactor Core Materials	University of Michigan	$798,943		Document	MRIIR	FY2010
Development of a Scanning Microscale Fast Neutron Irradiation Platform for Examining the Correlation Between Local Neutron Damage and Graphite Microstructure	University of Missouri-Columbia	$703,064		Document	GEN IV	FY2010
Study of Interfacial Interactions using Thin Film Surface Modification: Radiation and Oxidation Effects in Materials	University of Wisconsin-Madison	$538,032		Document	MRIIR	FY2010
Development of Thermal Transient Flow Rate Sensors for High Temperature, Irradiation, Corrosive Environment	University of Nevada-Las Vegas	$451,269		Document	GEN IV	FY2010
Novel Engineered Refractory Materials for Advanced Reactor Applications	North Carolina State University	$1,129,304		Document	MRIIR	FY2010
Novel Methods of Tritium Sequestration: High Temperature Gettering and Separation Membrane Materials Discovery for Nuclear Energy Systems	University of South Carolina	$1,366,626		Document	GEN IV	FY2010
Heat Transfer Salts for Nuclear Reactor Systems - Chemistry Control, Corrosion Mitigation, and Modeling	University of Wisconsin-Madison	$1,352,040		Document	GEN IV	FY2010
Pulsed Magnetic Welding for Advanced Core and Cladding Steels	University of Wisconsin-Madison	$525,206		Document	GEN IV	FY2010
Corrosion in Supercritical Carbon Dioxide: Materials, Environmental Purity, Surface Treatments, and Flow Issues	University of Wisconsin-Madison	$651,447		Document	GEN IV	FY2010
Quantification of Cation Sorption to Engineered Barrier Materials Under Extreme Conditions	Clemson University	$1,171,380		Document	FCR&D	FY2011
In-Pile Instrumentation Multi-Parameter System Utilizing Photonic Fibers and Nanovision	Idaho State University	$1,199,990		Document	FCR&D	FY2011
Development of Plasmonically Cloaked Nanoparticles	Idaho State University	$800,000		Document	FCR&D	FY2011
Fission Product Transmutation in Mixed Radiation Fields	Idaho State University	$800,000		Document	FCR&D	FY2011
Life Prediction of Spent Fuel Storage Canister Material	Massachusetts Institute of Technology	$899,826		Document	FCR&D	FY2011
Active Interrogation using Photofission Technique for Nuclear Materials Control and Accountability	Oregon State University	$900,000		Document	FCR&D	FY2011
Anisotropic Azimuthal Power and Temperature Distribution on Fuel Rod: Impact of Hydride Distribution	Pennsylvania State University	$631,956		Document	FCR&D	FY2011
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$1,000,000		Document	FCR&D	FY2011
Recovery of Uranium from Seawater: Preparation and Development of Polymer-Supported Extractants	City College of New York, Hunter	$363,716		Document	MSTR	FY2011
Microemulsions and Aggregation Formation in Extraction Processes for Used Nuclear Fuel: Thermodynamics and Structural Studies	University of California, Irvine	$1,000,000		Document	FCR&D	FY2011
One-Dimensional Nanostructures for Neutron Detection	North Carolina State University	$455,629		Document	MSTR	FY2011
Optimized Processing Fabrication Paths for Larger Heats of Nanostructured Ferritic Alloys	University of California, Santa Barbara	$1,000,000		Document	FCR&D	FY2011
Feasibility and Safety Assessment for Advanced Reactor Concepts Using Vented Fuel	Oregon State University	$600,000		Document	MSTR	FY2011
Basic Physics Data: Measurement of Neutron Multiplicity from Induced Fission	University of Michigan	$973,364		Document	FCR&D	FY2011
Development of an Efficient Meso-Scale Multi-Phase Flow Solver in Nuclear Applications	City College of New York	$505,858		Document	NEAMS	FY2011
High Temperature Transducers for Online Monitoring of Microstructure Evolution	Pennsylvania State University	$455,628		Document	MSTR	FY2011
Radionuclide Incorporation and Long Term Performance of Apatite Waste Forms	University of Michigan	$862,500		Document	FCR&D	FY2011
Multiscale Modeling and Uncertainty Quantification for Nuclear Fuel Performance	Colorado State University	$1,098,250		Document	NEAMS	FY2011
Laser-Arc Hybrid Welding of Thick Section Ni-base Alloys- Advanced Modeling and Experiments	Pennsylvania State University	$536,117		Document	MSTR	FY2011
Actinide Foil Production for MPACT Research	University of Nevada-Las Vegas	$156,897		Document	FCR&D	FY2011
Fundamental Studies of the Role of Grain Boundaries on Uniform Corrosion of Advanced Nuclear Reactor Materials	Drexel University	$1,098,250		Document	NEAMS	FY2011
Correlates of Sensitive Technologies	Texas A&M University	$509,467		Document	MSTR	FY2011
Enriched Boron-Doped Amorphous Selenium Based Position-Sensitive Solid-State Thermal Neutron Detector for MPACT Applications	University of South Carolina	$1,000,000		Document	FCR&D	FY2011
Phenomena-based Uncertainty Quantification in Predictive Coupled-Physics Reactor Simulations	Texas A&M University	$1,098,250		Document	NEAMS	FY2011
Improved Safety Margin Characterization of Risk from Loss of Offsite Power	Texas A&M University	$600,000		Document	MSTR	FY2011
Development of Advanced High Uranium Density Fuels for Light Water Reactors	University of Wisconsin-Madison	$1,000,000		Document	FCR&D	FY2011
Characterization of Modeling of Grain Boundary Chemistry Evolution in Ferritic Steels Under Irradiation	University of Michigan	$1,098,250		Document	NEAMS	FY2011
Diffusion, Thermal Properties and chemical Compatibilities of Select MAX Phases with Materials for Advanced Nuclear Systems	Drexel University	$535,927		Document	NEET	FY2011
A High Temperature-Tolerant and Radiation-Resistant In-Core Neutron Sensor for Advanced Reactors	The Ohio State University	$455,629		Document	MSTR	FY2011
Developing the User Experience for a Next Generation Nuclear Fuel Cycle Simulator	University of Wisconsin-Madison	$1,200,000		Document	FCR&D	FY2011
Development of Multiscale Materials Modeling Techniques and Coarse-Graining Strategies for Predicting Materials Degradation in Extreme Irradiation Environments	University of Tennessee, Knoxville	$750,000		Document	NEAMS	FY2011
A New Light Weight Structural Material for Nuclear Structures	North Carolina State University	$399,490		Document	NEET	FY2011
Pathway Aggregation in the Risk Assessment of Proliferation Resistance and Physical Protection (PR&PP) of Nuclear Energy Systems	The Ohio State University	$534,471		Document	MSTR	FY2011
Experimental Investigation of Convection and Heat Transfer in the Reactor Core for a VHTR	City College of New York	$1,118,856		Document	RCRD&D	FY2011
Preparation of High Purity, High Molecular-Weight Chitin from Ionic Liquids for Use as an Adsorbate for the Extraction of Uranium from Seawater	University of Alabama	$338,260		Document	MSTR	FY2011
Graphite Microstructural Characterization Using Time-Domain and Correlation-Based Ultrasonics	Johns Hopkins University	$1,199,997		Document	RCRD&D	FY2011
Selectivity in Ligand Binding to Uranyl Compounds: A Synthetic, Structural, Thermodynamic and Computational Study	University of California-Berkeley	$500,000		Document	MSTR	FY2011
Methodology Development for Passive Component Reliability Modeling in a Multi-Physics Simulation Environment	The Ohio State University	$533,457		Document	RCRD&D	FY2011
Development of Seismic Isolation Systems Using Periodic Materials	University of Houston	$538,154		Document	MSTR	FY2011
Pebble Fuel Handling and Reactivity Control for Salt-Cooled High Temperature Reactors	University of California, Berkeley	$612,721		Document	RCRD&D	FY2011
Innovative Elution Processes for Recovering Uranium from Seawater	University of Idaho	$400,000		Document	MSTR	FY2011
Self-Sustaining Thorium Boiling Water Reactors	University of California, Berkeley	$1,145,932		Document	RCRD&D	FY2011
Development of Austenitic ODS Strengthened Alloys for Very High Temperature Applications	University of Illinois-Urbana Champaign	$538,154		Document	MSTR	FY2011
High Fluency Low Flux Embrittlement Models of LWR Reactor Pressure Vessel Embrittlement and a Supporting Database from the UCSB ATR-2 Irradiation Experiment	University of California, Santa Barbara	$1,199,607		Document	RCRD&D	FY2011
Enhancement of the Extraction of the Uranium from Seawater	University of Maryland	$400,000		Document	MSTR	FY2011
A Research Program for Fission Product/Dust Transport in HTGR's	University of Missouri-Columbia	$1,157,367		Document	RCRD&D	FY2011
Transient Safety Analysis of Fast Spectrum TRU Burning LWR with Internal Blankets	University of Michigan	$599,475		Document	MSTR	FY2011
Development and Validation of a Lifecycle-based Prognostics Architecture with Test Bed Validation	University of Tennessee, Knoxville	$846,315		Document	RCRD&D	FY2011
Development of Novel Sorbents for Uranium Extraction from Seawater	University of North Carolina, Chapel Hill	$400,000		Document	MSTR	FY2011
In-situ Condition Monitoring of Components in Small Modular Reactors Using Process and Electrical Signature Analysis	University of Tennessee, Knoxville	$650,000		Document	RCRD&D	FY2011
Radiation Behavior of High-Entropy Alloys for Advanced Reactors	University of Tennessee, Knoxville	$538,159		Document	MSTR	FY2011
Technical Development for S-CO2 Advanced Energy Conversion	University of Wisconsin	$815,000		Document	RCRD&D	FY2011
Rapid Computer Aided Ligand Design and Screening of Precious Metal Extractants from TRUEX Raffinate with Experimental Validation	Washington State University	$500,000		Document	MSTR	FY2011
Ag Transport Through Non-Irradiated and Irradiated SiC	University of Wisconsin-Madison	$1,055,456		Document	RCRD&D	FY2011
Critical Heat Flux Phenomena at High Pressure and Low Mass Fluxes: Tests and Models	University of Wisconsin-Madison	$1,199,781		Document	RCRD&D	FY2011
Modeling and Test Validation of a Reactor Cavity Cooling System with Air	University of Wisconsin-Madison	$1,199,988		Document	RCRD&D	FY2011
Transient Mixed Convection Validation for NGNP	Utah State University	$635,860		Document	RCRD&D	FY2011
Alternative High-Performance Ceramic Waste Forms	Alfred University	$840,000	This project aims to advance fundamental understanding of the kinetics of structural evolution of crystalline ceramic waste forms. The structure/property relationships will be identified and will reveal new formulations, improved processing routes, and strategies for improved performance or ceramic waste forms.	Document	FCR&D	FY2012
Surface Layer Bulk Glass Interface Evolution with Aqueous Corrosion	Alfred University	$880,000	This project will investigate the links between the morphology, structure and chemistry of surface layer-bulk glass interface and the long-term corrosion-reaction kinetics using in-situ and ex-situ experiments. The understanding will result in improved models for long-term predictive behavior of high-level-waste (HLW) glasses under repository conditions.	Document	FCR&D	FY2012
Improved Accident Tolerance of Austenitic Stainless Steel Cladding through Colossal Supersaturation with Interstitial Solutes	Case Western Reserve University	$850,000	This project aims to develop new case-hardened austenitic stainless steels by saturating them with materials that improve their mechanical properties, corrosion resistance and radiation resistance. This project, if successful, will result in safer, longer-lasting, and more accident tolerant fuel claddings.	Document	FCR&D	FY2012
Optimization of Deep Borehole Systems for HLW Disposal	Massachusetts Institute of Technology	$850,000	Researchers aim to carry out a comprehensive evaluation of the deep borehole option for disposal of used nuclear fuel and high livel waste. The models developed will predict potential movement of water through natural and engineered barriers and release of radionuclides to the biosphere which will aide in site selection.	Document	FCR&D	FY2012
Scholarship for Nuclear Communications and Methods for Evaluation of Nuclear Project Acceptability	Massachusetts Institute of Technology	$800,000	Researchers will work to develop a model to characterize the factors affecting social acceptance of nuclear projects with potential stakeholders. The resultant model will strengthen the ability to design and implement large projects more efficiently, leading to higher rates of success of future nuclear projects.	Document	FCR&D	FY2012
Accurate Holdup Calculations with Predictive Modeling and Data Integration	North Carolina State University	$875,000	Researchers will develop and use state-of-the-art radiation transport codes to account accurately for the fissile material in a nuclear materials processing facility. An accurate estimation of the materials will allow for ensured radiological safety, security, waste management and efficient plant operation.	Document	FCR&D	FY2012
Novel Metal Sulfides to Achieve Effective Capture and Durable Consolidation of Radionuclides	Northwestern University	$760,000	Researchers will evaluate the effectiveness of chalcogenide based materials design novel metal sulfides to effectively capture and store of radioisotopes released during reprocessing of used nuclear fuel. This project will focus on understanding structure-property relationships to enable refined and direct synthesis approaches for improved and cost-efficient nuclear waste forms.	Document	FCR&D	FY2012
Nonlinear Ultrasonic Diagnosis and Prognosis of ASR Damage in Dry Cask Storage	Northwestern University	$885,000	Researchers aim to use nondestructive damage characterization methods to detect, manage and mitigate the degradation/damage mechanisms of dry cask storage systems for nuclear fuels. This project, if successful, will provide tools that will allow the prediction of the reliability and the safety of concrete structures in dry cask storage systems.	Document	FCR&D	FY2012
Prototype Demonstration of Gamma-Blind Tensioned Metastable Fluid Neutron/Multiplicity/Alpha Detector- Real Time Methods for Advanced Fuel Cycle Applications	Texas A&M University	$875,000	This project aims to create a prototype demonstration of a novel neutron/alpha detector based on a technology that is blind to gamma field used fuel. The prototype, if successful, will enhance instrumentation for monitoring real-time material balance during various stages of the nuclear cycle.	Document	FCR&D	FY2012
Testing of Sapphire Optical Fiber and Sensors in Intense Radiation Fields, when Subjected to Very High Temperatures	The Ohio State University	$885,000	The researchers on this project will investigate the performance of sapphire optical fibers and sensors in reactor environments. The project, if successful, will result in improved instrumentation to understand the behavior and predict performance of nuclear fuel systems at the microstructural level.	Document	FCR&D	FY2012
Concrete Materials with Ultra-High Damage Resistance and Self-Sensing Capacity for Extended Nuclear Fuel Storage Systems	University of California, Irvine	$800,000	Researchers aim to design a new class of multifunctional concrete materials. This project, if successful, will result in a novel multifunctional concrete material that possesses inherent degradation monitoring capability and is suitable for an extended storage system for the used nuclear fuel.	Document	FCR&D	FY2012
Development of Innovative Accident Tolerant High Thermal Conductivity UO2 Fuel Pellets with a Diamond Dopant	University of Florida	$800,000	Researchers will evaluate the use of diamond nanoparticles composite material in innovative accident tolerant fuel pellets. This could significantly improve both the thermal conductivity of fuel pellets and light water reactors' efficiency safety.	Document	FCR&D	FY2012
Probabilistic Multi-Hazard Assessment of Dry Cask Structures	University of Houston	$865,000	This project aims to investigate the performance of dry cask storage systems under multiple hazard systems (earthquake, tornados, combined with aging effects) using a probabilistic multi-hazard framework. This framework will be validated based on experimental research and will provide improved models for safety and reliability of spent nuclear fuels during storage and transportation.	Document	FCR&D	FY2012
Measurement of Irradiated Pyroprocessing Samples via Laser Induced Breakdown Spectroscopy	University of Idaho	$820,000	This project aims to use advanced characterization techniques to investigate microstructural changes and the micromechanisms related to irradiation induced damage in used nuclear fuels and waste forms. This project, if successful, will result in enhanced models to predict the structural and chemical response of used fuel and waster forms during interim storage and permanent disposal.	Document	FCR&D	FY2012
Elastic/Inelastic Measurement Project	University of Kentucky	$880,523	Researchers will measure nuclear data for elastic/inelastic scattered neutrons on coolants and structural materials. The data generated, will be useful for future R&D programs that will study innovative next generation LWR and future fast systems.	Document	FCR&D	FY2012
Electrochemical Corrosion Studies for Modeling Metallic Waste Form Release Rates	University of Nevada- Las Vegas	$790,000	This project aims to use advanced electrochemical methods to investigate the corrosion related degradation of metal alloys used for housing fission products. The data obtained from this study will allow for the prediction of the long-term behavior of the metallic host phase materials over geological time-scales.	Document	FCR&D	FY2012
Thermodynamic and Microstructural Mechanisms in the Corrosion of Advanced Ceramic Tc-bearing Waste Forms and Thermophysical Properties	University of Nevada- Las Vegas	$795,000	This project team will harvest thermodynamic and microstructural data on the evolution of ceramic based waste forms. The data will be used to advance the current state-of-the-art methodology used for isolation and stabilization of fission products and improve on nuclear fuel recycling processes.	Document	FCR&D	FY2012
Development and Experimental Benchmark of Simulations to Predict Used Nuclear Fuel Cladding Temperatures during Drying and Transfer Operations	University of Nevada- Reno	$745,000	Researchers will conduct experiments to investigate and develop advanced computational models of heat transfer in post-pool-storage drying operations. This project, if successful, will result in tools that can be used to design efficient drying processes to as to ensure suitability for dry-cask systems for long-term storage and transport.	Document	FCR&D	FY2012
Better Radiation Response and Accident Tolerance of Nanostructured Ceramic Fuel Materials?	University of Tennessee	$815,000	Researchers will use novel experimental methods to investigate the links between microstructure, phase stability and damage evolution in nanostructured ceramic fuel materials. The project will study fuel materials at temperatures and irradiation conditions relevant to operation and accidental scenarios.	Document	FCR&D	FY2012
Radiation and Thermal Effects on Used Nuclear Fuel and Nuclear Waste Forms	University of Tennesssee	$770,000	This project aims to investigate the structural and chemical response of used nuclear fuel and waste forms during interim storage and permanent disposal. If successful, this project will generate models that will allow the prediction of structural evolution and hence the radiological safety and security of nuclear fuel and waste forms.	Document	FCR&D	FY2012
Seismic Performance of Dry Casks Storage for Long-Term Exposure	University of Utah	$873,319	Researchers will evaluate the mechanical performance of dry-cask storage under seismic loading for mid-term operational periods. Simulations will include scenarios for freestanding, anchored, and vaulted casks. The experimental tests will also evaluate the dynamic seismic response of freestanding and anchored dry-cask storage prototypes, providing recommendations for optimal Interim Spent Fuel Storage Installations (ISFSIs) design.	Document	FCR&D	FY2012
Validation Experiments for Spent-Fuel Dry-Cask In-Basket Convection	Utah State University	$690,000	Researchers in this project aim to conduct experiments that generate data on natural convection through a fuel assembly. The data will be used to validate the computational models being developed for nuclear safety and design.	Document	FCR&D	FY2012
Re-Branding the Nuclear Fuel Cycle	Virginia Commonwealth University	$850,000	This project will create a comprehensive framework for the evaluation of alternative fuel cycle systems that will be used to identify and analyze key elements related to long-term management of nuclear fuels , with the ultimate goal to develop a communications strategy to reach stakeholders.	Document	FCR&D	FY2012
Advanced Characterization of Molecular Interactions in TALSPEAK-like Separations Systems	Washington State University	$875,000	Researchers will use advanced characterization techniques (experimental and computational) to improve understanding of the molecular level processes/interactions during separation processes for advanced fuel cycles. The understanding of these interactions will be used to develop more robust and streamlined separation processes for advanced fuel cycles.	Document	FCR&D	FY2012
Coupling of Nuclear Waste Form Corrosion and Radionuclide Transport in Presence of Relevant Repository Sediments	Washington State University	$885,000	Researchers will conduct experiments to understand the mechanisms responsible for the corrosion of nuclear waste forms in realistic chemical environments. The data generated from these experiments will enable increased reliability of the models used to predict the waste form performance in repository environments.	Document	FCR&D	FY2012
Stationary Liquid Fuel Fast Reactor (SLFFR) Concept for TRU Burning	Purdue University	$450,000	Reasearchers will investigate a new type of molten metallic fuel reactor concept that will consume hazardous transuranic waste. The liquid fuel alloy has several advantages over solid fuel fast reactors that are used for the same purpose.	Document	MSTR	FY2012
ABR for TRU Transmutation with Breed & Burn Thorium Blanket for Improved Economics and Resource Utilization	University of California- Berkeley	$450,000	The research team will use detailed neutronic analysis for a new Advanced Burner Reactor concept with low conversion ratio. The concept will use a new core shape to improve the utilization of neutrons to perform breed and burn.	Document	MSTR	FY2012
New Materials for High Temperature Thermoelecric Power Generation	University of California, Davis	$450,000	Reasearchers will work to develop nanostructured and other new materials to support the development of higher efficiency thermoelectric devices. These devices convert thermal energy to electricity with no moving parts. The new materials will operate at higher efficiencies and over a wider temperature range than those currently available--an important quality for future nuclear-powered deep space exploration.	Document	MSTR	FY2012
Microscopic Fuel Particles Produced by Self-Assembly of Actinide Nanoclusters on Carbon Nanomaterials	University of Notre Dame	$440,000	Reasearchers will develop the mechanisms, conditions and protocols to prepare uranium-carbon nanocomposite materials to make them more flexible. This could result in the generation of wholesale electricity, providing process heat, and providing power for households.	Document	MSTR	FY2012
High Hydrogen Content Graphene Hydride Compounds & High Cross-Section Cladding Coatings for Fast Neutron Detection	University of South Carolina	$430,000	This project will exploit recent breakthroughs to grow epitaxial graphene on commercial SiC wafers. This will allow researchers to develop a new detection method for fast neutrons. In addition, it will lead to better and more compact neutron detection system.	Document	MSTR	FY2012
Reducing Actinide Production Using Inert Matrix Fuels	University of Texas- Austin	$435,000	Reasearchers will perform a neutronic analysis, a thermal-hydraulic analysis and a simulation of fuel decay heat as a functionof fuel burnup, to determine if inert matrix fuel in coventional reactors will continue to be licensable. If successful, the inert matrix fuel mixtures will reduce harmful transuranic components in the fuel discharge streams at a level comparable to a fast reactcor burner.	Document	MSTR	FY2012
An Integrated Fuel Depletion Calculator for Fuel Cycle Options Analysis	University of Texas- Austin	$395,000	Reasearchers use new analysis techniques to better predict nuclear fuel behavior. The new model will allow improved fuel cycle for a larger number of users.	Document	MSTR	FY2012
Atomic-Scale to Meso-Scale Simulation Studies of Thermal Ageing and Irradiation Effects in Fe-Cr Alloys	Boston University	$874,997	Reasearchers will develop predictive, multi-scale simulation tools for iron-chromium alloys, which are expected to be key components of advanced steels envisioned as fuel cladding and structural components for Generation IV reactors. Such modeling is necessary to avoid resource intensive and costly thermal and neutron irradiation experiments to obtain required performance data.	Document	NEAMS	FY2012
Validation Data and Model Development for Fuel Assembly Response to Seismic Loads	George Washington University	$862,435	Reasearchers will conduct experiments that will provide comprehensive data characterizing the dynamics of the fluid and the structure in Pressurized Water Reactors (PWR) fuel assemblies under seismic loads (earthquakes and loss of coolant accidents). Completion of their project will greatly benefit the safety of existing and future nuclear reactors.	Document	NEAMS	FY2012
Uncertainty Quantification and Management for Multiscale Nuclear Materials Modeling	Georgia Institute of Technology	$743,444	Reasearchers will address the question of uncertainty propogation and error estimates associated with model prediction of material behavior under irradiation. Their work will facilitate a better understanding of the connection of various unit processes to collective responses in a multiscale model chain enabling the development of high strength and high ductility materials.	Document	NEAMS	FY2012
Fuel and Core Design Options to Overcome the Heavy Metal Loading Limit and Improve Performance and Safety of Liquid Salt Cooled Reactors	Georgia Insitute of Technology	$784,689	Reasearchers will examine new options for fuel and core designs in liquid salt cooled reactors where the current standard of TRISO type fuel has limitations due to loading characteristics. The research could enable new, more feasible fuel-core-reload options that will improve safety and performance parameters.	Document	RCRD&D	FY2012
Nonlinear Ultrasonic Techniques to Monitor Radiation Damage in RPV and Internal Components	Georgia Institute of Technology	$877,000	Reasearchers will explore new nondestructive materials evaluation and monitoring techniques utilizing nonlinear ultrasonic measurements . This technique will allow researchers to assess remaining useful life of select reactor components. Breakthroughs in this area will lead to the ability to characterize radiation damage in reactor pressure vessels and other components-leading to a clearer definition of reactor safety margins.	Document	RCRD&D	FY2012
Intergral Reactor Containment Condensation Model and Experimental Validation	Oregon State University	$871,119	Reasearchers will conduct experiments to enhance the safety and efficiency of small modular reactors (SMRs). This project will assess the impact of high-pressure steam condensation on steel containment vessels to be used for SMR deigns.	Document	RCRD&D	FY2012
Investigation of Natural Circulation Instability and Transients in Passively Safe Small Modular Reactors	Purdue University	$871,100	Reasearchers will perform scaled experiments to study the thermal-hydraulic instabilities that can occur in Small Modular Reactors (SMR) which rely on natural circulation cooling during normal operation and accident conditions. Their work will not only improve our understanding of general natural circulation instability but also lead to the development of stability criteria and predictability in the operation of SMRÃs.	Document	RCRD&D	FY2012
Thermoelectric-Driven Sustainable Sensing and Actuation Systems for Fault-Tolerant Nuclear Incidents	State University of New York, Stony Brook	$599,802	Reasearchers will examine the use of solid-state thermoelectric generators to produce electricity to sense and opeate during both normal and abnormal situations. This will provide indefinite monitoring of key components during power outages or station blackouts.	Document	RCRD&D	FY2012
Experimental and CFD Studies of Coolant Flow Mixing within Scaled Models of the Upper and Lower Plenums of NGNP Gas-Cooled Reactors	Texas A&M University	$713,051	Reasearchers will model the internal coolant flow of a prismatic core very high temperature reactor (VHTR) by using large eddy simulation tools. This method will enable more accurate prediction of flow field characteristics and better evaluation of VHTR behavior under operational and accidental conditions.	Document	RCRD&D	FY2012
Demonstrating Hybrid Heat Transport and Energy Conversion System Performance Characterization Using Intelligent Control Systems	University of Idaho	$877,000	Reasearchers will demonstrate an intelligent control systems in a hybrid energy conversion loop for a next generation nuclear power plant. Hybrid energy systems are a method of optimizing the use of natural resources for energy production. Hybrid systems present an opportunity to develop domestic energy sources to improve energy security.	Document	RCRD&D	FY2012
Advanced Reactor-Intermediate Heat Exchanger (IHX) Coupling: Theoretical Modeling and Experimental Validation	University of Idaho	$869,997	Reasearchers will model the behavior of the Advanced Reactor Intermediate Heat Exchanger Chemical Process system and develop advanced control techniques that take into account abnormal scenarios. The data and information obtained will assist in the development of intelligent control systems for next generation nuclear reactor systems.	Document	RCRD&D	FY2012
Irradiation Performance of Fe-Cr Base Alloys	University of Illinois- Urbana Champaign	$876,332	Reasearchers will perform post-radiation analysis and develop tools for future development and application of the Fe-Cr class of alloys. The results of this research will lead to better modeling of performance and development of an alloy designated as the primary choice for reactor fuel cladding and structural applications in advanced systems.	Document	RCRD&D	FY2012
Accelerated Irradiations for High Dose Microstructures in Fast Reactor Alloys	University of Michigan	$831,876	Reasearchers will determine the extent to which high dose rate irradiation can be used as an irradiation damage tool to understand microstructure evolution at high doses and temperatures relevant to advanced fast reactors. The project will provide fundamental understanding of the effectiveness of this process and thus of microstructure development in irradiated materials.	Document	RCRD&D	FY2012
Mitigating IASCC of Reactor Core Internals by Post-Irradiation Annealing Advanced Mitigation Strategies	University of Michigan	$876,985	Reasearchers will determine the optimum Post-irradiation annealing (PIA)-driven mitigation strategy to extend the potential lifetime of light water reactors. Samples that have already been irradiated in a light water reactor will be used to test PIA treatments to understand IASCC initiation and propoagation, annealing kinetics, the role of microstructure features in irradation hardening and localized deformation, and the optimum mitigation strategy based on PIA.	Document	RCRD&D	FY2012
Experimentally Validated Numerical Models for Effects of Non-Isothermal Turbulent Mixing on Wall Stresses in High Temperature Reactors	University of Pittsburgh	$876,422	Reasearchers will develop a comprehensive experimentally validated computational framework for the turbulent mixing in the lower plenum of a very high temperature reactor (VHTR). Through CFD modeling and experimental validation, the results from this project will lay the groundwork for future stress analysis, failure and fatigue studies, and uncertainty quantification for the VHTR system.	Document	RCRD&D	FY2012
Role of Defects in Swelling and Creep of Irradiated SiC	University of Wisconsin- Madison	$875,350	Reasearchers will study mechanisms controlling both radiation swelling and radiation creep in silicon carbide. These two effects are crucial to understanding the issues associated with the brittle silicon carbide composite. Success in this project will ground progress in the adoption of silicon carbide for reactor solutions, particularly as fuel cladding.	Document	RCRD&D	FY2012
Advanced Supercritical Carbon Dioxide Brayton Cycle Development	University of Wisconsin, Madison	$877,000	Reasearchers will investigate the benefits of utilizing advanced Brayton cycles with supercritical carbon dioxide in new reactor systems and components. Benefits of this research include improvement of analysis and performance of components currently utilizing these cycles as well as the potential for a large scale advanced CO2 power system.	Document	RCRD&D	FY2012
Mechanical Behavior of UO2 at Sub-grain Length Scales: Quantification of Elastic, Plastic and Creep Properties via Microscale Testing	Arizona State University	$800,000	Reasearchers will develop techniques to measure properties at sub-grain scales using depleted Uranium Oxide samples. The project will provide a framework to measure sub-grain scale mechanical properties, as well as provide experimental data to improve the understanding of advanced oxide fuels.	Document	FCR&D	FY2013
The Impacts of Pore-Scale Physical and Chemical Heterogeneities on the Transport of Radionuclide-Carrying Colloids	Colorado School of Mines	$800,000	Reasearchers will identify the dominant transport mechanisms to develop models that predict radionuclide distribution in porous materials. Experimental and computational models will be created that couple pore-scale geometric and interfacial structures. Simulators such as these are a necessary step towards fully predictive models for field-scale applications in the future.	Document	FCR&D	FY2013
Recovery of Uranium from Seawater: Polymer-Supported Aminophosphinates as Selective Extractants	Hunter College, CUNY	$399,999	Reasearchers will prepare a polymer-supported extractant for the recovery of uranium from seawater. The project will focus on primary amines that could provide a 3-fold increase in uranium capture capacity than current methods.	Document	FCR&D	FY2013
In-pile Thermal Conductivity Characterization with Single-laser Heating/Time Resolved Raman	Iowa State University	$800,000	Reasearchers will develop a time-resolved Raman-based thermal conductivity measurement system to improve remote in-pile thermal conductivity measurement. These measurements will provide new insights into the behavior of materials exposed to extreme radiation and temperature environments. Understanding the behavior of materials at the microstructural level will support optimized fuel designs.	Document	FCR&D	FY2013
Organic Speciation and Interactions in ALSEP - One Step Partitioning Process of Minor Actinides, Lanthanides, and Fission Products	Oregon State University	$600,000	Reasearchers will investigate the Actinide-Lanthanide Separation (ALSEP) process organic phase prior to aqueous phase separation and after aqueous separation phases of bare and metal-loaded acids. Quantifying these effects can be used to determine how an engineering scale process will perform and generate an accurate chemical model for the system.	Document	FCR&D	FY2013
Glass Composition and Solution Speciation Effects on Stage III Dissolution	Pennsylvania State University	$700,000	Reasearchers will study the chemical and structural triggers of long-term vitrified nuclear waste form behavior. They will study a range of waste glass compositions in corrosive environments. The study will improve understanding of the long-term residual rate and may provide new options for environmental control of glass dissolution rates.	Document	FCR&D	FY2013
Correlating Thermal, Mechanical, and Electrical Coupling Based Multiphysics Behavior of Nuclear Materials Through In-Situ Measurements	Purdue University	$800,000	Reasearchers will use in-situ experimental techniques to monitor the influence of extreme conditions on fuel cladding. The project will establish an in-situ experimental setup that can predict change in thermal properties and their correlation with mechanical properties and correlate such changes to changes in microstructural and chemical features.	Document	FCR&D	FY2013
Creation of a Geant4 Muon Tomography Package for Imaging of Nuclear Fuel in Dry Cask Storage	Purdue University	$440,000	Reasearchers will develop a simulation and analysis package to aid in the non-destructive assessment of sealed used nuclear fuel dry casks using cosmic ray muons. Cosmic ray muon tomography allows for non-destructive assessment that can independently verify and identify weapons grade material sealed within dense dry casks.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Two-stage Fast Reactor Fuel Cycle Options for Optimum Resource Utilization and Waste Management	Purdue University	$400,000	Reasearchers will evaluate the two different two-stage fast reactor fuel cycle options that will offer efficient use of uranium resources and the ability to burn actinides and long-live fission products. Evaluation of these fast fuel cycle options will serve as a useful complement to the options currently being considered in the Fuel Cycle Options Campaign.	Document	FCR&D	FY2013
Mixed Metal Phosphonate-Phosphate Resins for Separation of Lanthanides from Actinides	Texas A&M University	$650,000	Reasearchers will use ion exchangers to cleanly separate lanthanides and curium from reusable actinides. The study will assist in the development of an inexpensive, simple way in which to separate lanthanides from actinides found in used nuclear fuel rods and to recover a large portion of the usable fuel.	Document	FCR&D	FY2013
Safeguards in Pyroprocessing: an Integrated Model Development and Measurement Data Analysis	The Ohio State University	$626,151	Reasearchers will develop a comprehensive and effective safeguards approach for a pyroprocessing facility to support safeguards for future fuel cycles in the United States. The new approach and design will focus directly on the special nuclear materials in the electrorefiner where actinides are separated from fission products through electrochemical process.	Document	FCR&D	FY2013
Using Ionic Liquids for the Development of Renewable Biopolymer-Based Adsorbents for the Extraction of Uranium from Seawater and Testing Under Marine Conditions	University of Alabama	$400,000	Reasearchers will explore the fundamental engineering parameters for a renewable high-performance adsorbent for the extraction of uranium from sweater based on a recently proven ionic liquid (IL)-chitin platform. The project will use the platform to develop a versatile, modifiable adsorbent and characterize its performance and degradation in marine conditions.	Document	FCR&D	FY2013
Developing Ultra-Small Scale Mechanical Testing Methods and Microstructural Investigation Procedures for Irradiated Materials.	University of California, Berkeley	$800,000	Reasearchers will develop new small-scale mechanical testing techniques to allow for the estimation or direct measurement of bulk properties. The combined experiments and modeling will significantly enhance the statistics and information that can be obtained on small radioactive archived samples, as well as new ion beam irradiated specimens.	Document	FCR&D	FY2013
Improved Delayed-Neutron Spectroscopy Using Trapped Ions	University of California, Berkeley	$400,000	Reasearchers will develop innovative spectroscopy techniques to measure the decay of fission fragments. The resulting data from these new techniques will be used to better understand reactor kinetics under accident conditions and failure scenarios.	Document	FCR&D	FY2013
Thermally and Chemically Responsive Nanoporous Materials for Efficient Capture of Fission Product Gases	University of California, Davis	$750,000	Reasearchers will create new nanoporous materials that will be highly effective at capturing fission product gases. These materials would be relevant to both reactor fuels applications and reprocessing operations. Tests will be performed in carbon based and nitride based nanostructures, with the most promising materials from the modeling perspective undergoing further testing.	Document	FCR&D	FY2013
Multiphase Nanocrystalline Ceramic Concept for Nuclear Fuel	University of California, Irvine	$800,000	Researchers will study the use of nanoparticles and nanostructured ceramics to create new materials that can extend the service life and increase efficiency for nuclear fuel. Multiphase nanocrystalline ceramics will be used to design simulated nuclear fuel that can provide added plasticity, better radiation tolerance and improved thermal conductivity.	Document	FCR&D	FY2013
Development of Novel Porous Sorbents for Extraction of Uranium from Seawater	University of Chicago	$400,000	Reasearchers will develop a highly porous sorbent for the extraction of uranium from seawater. Previous research has established sorbent performance. This project will use past foundational studies to design and investigate a new nanocomposites that will be processed into tacks or braids for field tests in seawater tests. The technology may also be used for other metals.	Document	FCR&D	FY2013
Microwave Readout Techniques for Very Large Arrays of Nuclear Sensors	University of Colorado, Boulder	$799,937	Reasearchers will develop a powerful readout technique based on microwave transmission and reflection. The technique will enable very large arrays of diverse sensor types for nuclear materials quantification and tracking. It will provide more accurate data on material composition and quantity.	Document	FCR&D	FY2013
BiI3 Gamma-Ray Spectrometers for Reliable Room-Temperature Nuclear Materials Safeguarding	University of Florida	$799,999	Reasearchers will develop gamma-ray spectrometers based on BiI3 single crystals for MPACT applications such as burnup validation quantification, improved assay of plutonium, determination of uranium enrichment and overall monitoring spent fuel within the fuel cycle. The project will improve energy resolution, efficiency and environmental performance with this new gamma-ray detector.	Document	FCR&D	FY2013
Innovative Coating of Nanostructured Vanadium Carbide on the F/M Cladding Tube Inner Surface for Mitigating the Fuel Cladding Chemical Interactions	University of Florida	$760,276	Researchers will develop barrier coatings on the inner surface of fuel cladding tubes to improve performance of materials at elevated temperatures and high neutron exposures in fast reactors. The project will develop and test a low temperature coating process of nanostructured vanadium carbide that will provide a benchmark for use in future studies.	Document	FCR&D	FY2013
Doubling the Life of Concrete Structures	University of Idaho	$800,000	Reasearchers will use nanoscale techniques to develop methods for doubling the service life of concrete structures. They will study the effect of temperature load and temperature cycling (freezing and thawing) on the durability of concrete with nanoscale viscosity modifiers. The project will benefit from non-destructive evaluation of concrete performance through electrochemical techniques.	Document	FCR&D	FY2013
Off-Gas Treatment: Evaluation of Nano-structured Sorbents for Selective Removal of Contaminants	University of Idaho	$785,910	Reasearchers will evaluate nanostructured sorbent materials for their effectiveness in removing and immobilizing radionuclides for the off-gas treatment from used nuclear fuel recycling operations. The project aims at achieving near-zero emissions of radionuclides by capturing them from the off-gas of recycling operations, allowing for the development of advanced fuel cycles.	Document	FCR&D	FY2013
Innovative Elution Processes for Recovering Uranium and Transition Metals from Amidoxime-Based Sorbents	University of Idaho	$399,864	Reasearchers will develop a new two-step elution process to achieve total recovery of uranium and effective recycling of the sorbent. The extraction process would selectively remove uranium from the sorbent with little or no damage. The process would then remove transition metals and regenerate the sorbent for repeated use, making uranium extraction from seawater economically viable.	Document	FCR&D	FY2013
Performance of a Steel/Oxide Composite Waste Form for Combined Waste Streams from Advanced Electrochemical Processes over Geologic Time Scales	University of Illinois at Chicago	$700,000	Reasearchers will develop and validate a mechanistically-based corrosion model for cermet-type waste forms, creating a testing protocol and modeling approach for predicting long-term performance. The study will apply novel electrochemical testing and modeling methods to the behavior of metal/oxide phase boundaries to evaluate waste form performance.	Document	FCR&D	FY2013
Enhancement of the Extraction of Uranium from Seawater	University of Maryland, College Park	$400,000	Reasearchers will develop and optimize novel adsorbents for uranium recovery from seawater. The team will use radiation-induced grafting of organic phosphates onto polymers. The experiments will use ocean water, with mechanistic analysis, to provide a solid basis for large-scale demonstration of the performance of the new adsorbents in ocean environments.	Document	FCR&D	FY2013
Improving the Understanding of the Coupled Thermal-Mechanical-Hydrologic Behavior of Consolidating Granular Salt	University of New Mexico	$800,000	Reasearchers will increase the understanding of granular salt seal materials for shafts, drifts and boreholes. By coupling thermal, mechanical and hydrological responses, the study will result in greater confidence in granular salt consolidation as a principal strategy for closure and isolation of long-term waste repositories.	Document	FCR&D	FY2013
Fission Fragment Yield Data in Support of Advanced Reactor Technology	University of New Mexico	$399,816	Reasearchers will produce a highly accurate data set for thermal fission. These precision data are necessary for high-accuracy simulations of nuclear criticality, transmutation rates, radiation effects and heating as well as for nuclear fuel, material accounting and identification needs.	Document	FCR&D	FY2013
Molecular dynamics-based simulations of bulk/interfacial structures and diffusion behaviors in nuclear waste glasses	University of North Texas	$700,000	Reasearchers will generate accurate atomic structural models for use in Monte Carlo simulations of the dissolution of nuclear waste glasses. Large-scale molecular dynamics-based computer simulations will be used to investigate self-diffusion behaviors, interfacial structure, and other structures formed during dissolution of these glasses.	Document	FCR&D	FY2013
U3Si2 Fabrication and Testing for Implementation into the BISON Fuel Performance Code	University of South Carolina	$800,000	Reasearchers will fabricate, test and model a high uranium density, advanced nuclear fuel that operates at a much lower temperature and stores less energy. The work will deliver key research data on creep and grain growth, improving economics, through possible power uprates, and advancing accident tolerant fuels research.	Document	FCR&D	FY2013
Structural Health Monitoring of Nuclear Spent Fuel Storage Facilities	University of South Carolina	$738,618	Reasearchers will develop a nuclear structural health monitoring system based on a sensing technology that monitors material degradation and aging for dry cask storage systems. The low-cost, low-profile sensors will perform on-demand monitoring of the structural integrity of individual components as well as the entire system.	Document	FCR&D	FY2013
ORIGEN-based Nuclear Fuel Depletion Module for Fuel Cycle Assessment	University of Tennessee at Knoxville	$755,181	Reasearchers will develop a flexible reactor analysis module for the CYCLUS fuel cycle simulator based on established tools for reactor fuel depletion and decay. They will use ORIGEN, a mature and experimentally validated code, affording greater flexibility and allowing for accurate evaluations of impacts of both present and future fuel cycle options.	Document	FCR&D	FY2013
Cost and System Analysis of Innovative Fuel Resources Concepts	University of Texas at Austin	$295,960	_This project will develop and test braided polymer fiber adsorbents that surpass the sorption capacity, selectivity and durability of the best existing technology to recover uranium from seawater.	Document	FCR&D	FY2013
Risk Assessment of Structural Integrity of Transportation Casks	University of Utah	$789,296	Reasearchers will assess the loss of structural integrity of transportation casks and fuel cladding after extended storage. This risk assessment will conduct experimental tests and simulations to evaluate the structural performance of fuel, fuel assemblies and cask components when subjected to vibration and impact loads during transport.	Document	FCR&D	FY2013
Market-Based and System-Wide Fuel Cycle Optimization	University of Wisconsin, Madison	$612,731	Reasearchers will create market and economic optimizers to improve calculations for the CYCLUS fuel cycle simulator. The team will leverage existing optimization software frameworks within the simulator to resolve top level policy questions. The optimizations will allow CYCLUS to move beyond static material compositions, providing a holistic view of the fuel cycle system.		FCR&D	FY2013
Optical Fiber Based System for Multiple Thermophysical Properties for Glove Box, Hot Cell and In-Pile Applications	Utah State University	$799,975	Reasearchers will use a small pressure vessel to develop a robust technique for the measurement of multiple thermophysical properties at very high temperatures. The technique will lead to a system design moving toward the eventual measurement of irradiated fuels in a glovebox and/or hot cell with all sensors and electronics outside of the glovebox and/or hot cell.	Document	FCR&D	FY2013
Development of a Nano-Modified Concrete for Next Generation of Storage Systems	Vanderbilt University	$796,268	Reasearchers will use nano-sized and nano-structured particles based on enhanced reactivity to develop a superior concrete for the long-term storage of used nuclear fuel. The project will use state-of-the-art experimental chemical and mechanical characterizations and computation analysis to assess the performance of nano-modified concretes.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Thorium Fuel Cycle Options	Vanderbilt University	$797,995	Reasearchers will develop six fuel cycle data packages for multi-stage, thermal fuel cycles which incorporate thorium. These new fuel cycle data packages will provide the opportunity to examine fuel cycle options beyond those which have traditionally been considered. A thorium fuel cycle database will also be assembled as a basis for thorium literature for future evaluations of the thorium fuel cycle.	Document	FCR&D	FY2013
Enhanced Shielding Performance of HLW Storage Packages via Multi-Component Coatings	Virginia Polytechnic Institute and State University	$796,947	Reasearchers will develop a multi-layer composite that will enhance long-term storage and facilitate safe transport of storage packages. This novel multi-layer, multi-component coating would create an outer shield material that is resistant to the corrosion, radiation, diffusion and thermal cycling processes that affect fuel packages during long term storage.	Document	FCR&D	FY2013
Managing Zirconium Chemistry and Phase Compatibility in Combined Process Separations for Minor Actinide Partitioning	Washington State University	$700,000	Reasearchers will address unique challenges for combining TRUEX and TALSPEAK processes for partitioning of lanthanides and minor actinides. The project will develop improved information on the thermodynamics of fission product zirconium and develop a framework for an organic phase solvation model. Combined process development could streamline separations processes.	Document	FCR&D	FY2013
Advances in the Recovery of Uranium from Seawater: Studies Under Real Ocean Conditions	Woods Hole Oceanographic Institution	$398,882	Reasearchers will provide infrastructure and expertise for marine testing of currently available adsorbents in real ocean conditions. The team will move adsorbent research from the lab to field testing in order to quantify sorptive properties and uranium uptake. The project will provide valuable field data that will show the potential of large scale applications of these technologies.	Document	FCR&D	FY2013
NEUP Project 20-19172: Irradiation of Sensors and Adhesive Couplants for Application in LWR Primary Loop Piping and Components		$497,881	Reasearchers paln to attach ultrasonic transducers to substrates using various adhesive couplants that will be irradiated at elevated temperature to simulate LWR primary loop conditions at the PULSTAR reactor at North Carolina State University. Ultrasonic data will be taken in-situ. Subsequently, the sensors and couplant interfaces will be characterized using the LAMDA facility at ORNL. The results will be used to benefit a parallel EPRI project on online monitoring of cracks in LWR primary loop piping._	Document	R&D NSUF	FY2013
NEUP Project 20-19404: Extension of MSTDB to Provide a High-Quality, Validated Thermochemical Database for Predicting/Simulating Corrosion in Molten Salt Reactor SystemsUniversity of South Carolina		$600,000	Reasearchers will generate a validated, consistent database of initial fuel compositions and potential corrossion products of fluoride and chloride salts, allowing for important phenomena predictions in molten salt reactors to guide confident decisions. The database will be integral to the currently being developed Molten Salt Thermochemical Database (MSTDB), structured to allow use by commercial and open source codes._	Document	NEAMS	FY2013
Lower Length Scale Characterization and Validation of Formation and Stability of Helium Bubbles in Nano-structured Ferritic Alloys under Irradiation	Clemson University	$399,870	Reasearchers will provide a fundamental knowledge about the formation and stability of ultra-fine helium bubbles within 14YWT after neutron/ion irradiation for further design of new advanced structural materials with a characteristic high density nanoparticles feature which can increase the mechanical strength, hardness, irradiation resistance and the operational temperature range of materials.	Document	NEAMS	FY2013
Three-Dimensional Fuel Pin Model Validation by Prediction of Hydrogen Distribution in Cladding and Comparison with Experiment	Pennsylvania State University	$800,000	Reasearchers will validate important three-dimensional aspects of the fuel pin modeling by using specialized numerical modeling techniques coupled with laboratory experiments to validate existing models for predicting fuel performance in light water reactors.	Document	NEAMS	FY2013
Collocation-Based Surrogate Models for Uncertainty Quantification and Validation of Coupled, Multiphysics Fuel Performance Simulation Tools	University of Michigan	$596,835	Reasearchers will provide the necessary high fidelity, coupled, multiphysics fuel performance simulator for computational modeling and develop surrogates which will accelerate and focus the validation of the coupled codes. This will be achieved by utilizing the high fidelity coupled fuel performance, thermal-hydraulics and neutronics codes BISON/STAR-CCM+/MPACT and an innovative collocation-based surrogate methodology.	Document	NEAMS	FY2013
Multi-Resolution In-Situ Testing and Mutliscale Simulation for Creep Damage Fatigue Damage Analysis of Alloy 617	Arizona State University	$800,000	This project will develop novel testing and experimentally validated prediction methodologies for micro-structural damage mechanisms of structural materials for advanced reactor systems. The investigations will focus on the characterization and testing of specific metal alloys, but the proposed testing and life-prediction methodologies are applicable to other structural materials as well.	Document	RCRD&D	FY2013
Novel High Temperature and Radiation Resistant Infrared Glasses and Optical Fibers for Sensing in Advanced Small Modular Reactors	Clemson University	$800,000	Clemson University, in partnership with the Iowa State University and the Pacific Northwest National Laboratory, will develop novel optical materials with improved heat and radiation exposure resistance in order to enable in-vessel fiber optic sensing for advanced Small Modular Reactors.	Document	RCRD&D	FY2013
Validation Data Acquisition in HTTF during PCC Events	George Washington University	$800,000	Reasearchers at the George Washington University and Oregon State University will collaborate with NASA Langley Research Center to measure flow velocities in a high temperature test facility. This work supports the development of very-high temperature reactors with passive safety systems.	Document	RCRD&D	FY2013
Advanced High Temperature Inspection Capabilities for Small Modular Reactors	Iowa State University	$790,822	The objective of this project is to develop non-destructive evaluation techniques for advanced small modular reactors. The research will provide key enabling inspection technologies needed to support the design and the reactor component performance validation process for advanced small modular reactors.	Document	RCRD&D	FY2013
Experimental and Computational Investigations of Plenum-to-Plenum Heat Transfer under Natural Circulation in a Prismatic Very High Temperature Reactor	Missouri University of Science and Technology	$799,999	Reasearchers will perform experimental and computational investigations to study heat transfer and natural circulation phenomena in very-high temperature reactors. The study will assist in the ability to predict and analyze passive safety systems.	Document	RCRD&D	FY2013
New Mechanistic Models of Creep-Fatigue Crack Growth Interactions for Advanced High Temperature Reactor Components	Oregon State University	$790,790	Reasearchers will create and validate a robust, multi-scale, numerical model to predict material degradation in nickel-based reactor alloys. If successful, this project will provide better numerical tools for reactor designers and greatly improve their capability to design against material failures for reactor alloys in the long term.	Document	RCRD&D	FY2013
Self-Powered Wireless Dual-mode Langasite Sensor for Pressure/Temperature Monitoring of Nuclear Reactors	State University of New York, Stony Brook	$800,000	This research will develop a novel self-powered wireless hybrid sensor that can accurately monitor both pressure and temperature using a single device without requiring external electricity, even in extreme harsh environments.	Document	RCRD&D	FY2013
Compact Heat Exchanger Design and Testing for Advanced Nuclear Reactors and Advanced Power Cycles	The Ohio State University	$800,000	The goal of this project is to investigate optimal heat exchanger designs for advanced reactors. The research will study the optimization of printed circuit heat exchangers for specific fluids under a variety of conditions as well as perform numerical modeling. Experiments will focus on thermal performance and heat stress during extreme conditions.	Document	RCRD&D	FY2013
Fundamental Understanding of Creep-Fatigue Interactions in 9Cr-1MoV Steel Welds	The Ohio State University	$798,000	This project will advance the state of knowledge and fundamental understanding of deforming materials and welds under loading conditions. Specifically, new integrated testing procedures will be evaluated and applied for conditions that are most detrimental to material stability leading to improved predictions of life expectancy for reactor steels and welds.	Document	RCRD&D	FY2013
Advanced Mechanistic 3D Spatial Modeling and Analysis Methods to Accurately Represent Nuclear Facility External Event Scenarios	The Ohio State University	$800,000	Reasearchers will develop three-dimensional characterization uncertainty analysis for commercial power plants. The project will involve combining experts from the fields of seismic structural modeling and advanced methods of risk assessment. This effort is expected to result in next generation tools that can be used for assessment of seismic risks.	Document	RCRD&D	FY2013
Tritium Mitigation/Control for Advanced Reactor Systems	The Ohio State University	$400,000	Reasearchers will develop a fluoride salt cooled high-temperature reactor featuring a specialized system to control tritium production. If successful, this will result in a significant reduction in size and cost in comparison to other reactor designs.	Document	RCRD&D	FY2013
A Pebble-Bed Breed and Burn Reactor	University of California, Berkeley	$400,000	Reasearchers will assess the feasibility of designing a type of metal cooled reactor able to establish and maintain operation when fueled with depleted uranium. If successful, this reactor will offer at least a 30-fold increase in the uranium ore utilization versus that achieved in contemporary light water reactors without the need for fuel reprocessing and recycling.	Document	RCRD&D	FY2013
Investigation of Thermal Aging Effects on the Evolution of Microstructure and Mechanical Properties of Cast Duplex Stainless Steels	University of Maryland, College Park	$799,966	This research will provide a better understanding of the microstructural evolution and simultaneous change in mechanical response during aging. The results of the research will provide data that can be used to estimate degraded mechanical properties for an 80-year service life of light water reactors.	Document	RCRD&D	FY2013
Model validation using CFD-grade experimental database for NGNP Reactor Cavity Cooling Systems with water and air	University of Michigan	$799,348	Reasearchers will use advanced innovative instrumentation to build a high-resolution experimental database and to use the novel experimental data to assess and further develop the predictive capabilities of computer codes for thermal hydraulics and computational fluid dynamics. The improved models developed by this project will also have the direct benefit of improving the predictive capability of the passive systems of third generation light water reactors and small modular reactor systems.	Document	RCRD&D	FY2013
Long-Term Prediction of Emissivity of Structural Material for High Temperature Reactor Systems	University of Missouri	$799,117	Reasearchers will study specific types of emissivity driven cooling from a variety of materials that are relevant to nuclear reactors. The research will provide a basis for numerical modeling to support reactor development.	Document	RCRD&D	FY2013
Advanced I&C for Fault-Tolerant Supervisory Control of Small Modular Reactors	University of Pittsburgh	$800,000	The purpose of this research is to develop advanced instrumentation and control techniques for supervisory control of advanced small modular reactors. This research supports the operational goals of small modular reactor concepts through the development of improved oversight and surveillance techniques.	Document	RCRD&D	FY2013
Corrosion of Structural Materials for Advanced Supercritical Carbon-Dioxide Brayton Cycle	University of Wisconsin-Madison	$798,672	Reasearchers will study a variety of materials for corrosion resistance under conditions that improve power conversion. In addition to studying the corrosion resistance of the materials, researchers will study the effect of additives to mitigate corrosion. Development of corrosion theories and modeling aimed at prediction of long-term corrosion will be the underlying theme throughout the project.	Document	RCRD&D	FY2013
Component and Technology Development for Advanced Liquid Metal Reactors	University of Wisconsin-Madison	$798,920	In support of liquid metal cooled reactors, the University of Wisconsin, Madison will evaluate advanced alloys and ceramics that come in contact with liquid metals. Additionally, a robust oxygen sensor and for use in liquid metals will be developed in order to better evaluate corrosion profiles in support of diagnostic testing.	Document	RCRD&D	FY2013
A New Paradigm for Understanding Multi-phase Ceramic Waste Form Performance	Clemson University	$800,000	Researchers will use advanced characterization tools to develop 3-D microstructural data that can be incorporated into computer-based simulations in order to predict the performance of waste forms. Materials system modeling will incorporate elemental release and the interconnected microstructural network of phases to better understand performance and degradation, which will accelerate waste form acceptance in repository settings.	Document	FCR&D	FY2014
Controlling Hexavalent Americium: A Centerpiece to a Compact Nuclear Fuel Cycle	Colorado School of Mines	$800,000	Researchers will develop and exploit the fundamental chemistry of Americium to enable an industrially viable means to co-recover the major and minor actinide elements from used nuclear fuel. The results would be a significant step forward in the development of aqueous separations approaches designed to recover the U-Am actinides based on the availability of the hexavalent oxidation state.	Document	FCR&D	FY2014
Zeolite Membranes for Krypton/Xenon Separation from Spent Nuclear Fuel Reprocessing Off-Gas	Georgia Institute of Technology	$400,000	Researchers will develop a high-performance, lower-cost zeolitic membrane process for Kr/Xe separations during spent nuclear fuel processing. Current separation methods are not considered economical and a membrane process would have relatively lower cost, equipment size, and ambient operating temperature. The process would form a sound basis for further development of this transformative separation technology for the nuclear fuel cycle.	Document	FCR&D	FY2014
Optimizing Polymer-Grafted Amidoxime-based Adsorbents for Uranium Uptake from Seawater	Georgia Institute of Technology	$399,999	Researchers will work to increase the adsorbent capacity and selectivity toward uranium by optimizing the adsorbent morphology, synthesis variables, and conditioning parameters and by investigating the rate-limiting variables through transport and reaction modeling. A novel adsorption/partition concept that has the potential to substantially increase the adsorbent capacity will be tested, making uranium from seawater extraction more economically viable.	Document	FCR&D	FY2014
Extraction of Uranium from Seawater: Design and Testing of a Symbiotic System	Massachusetts Institute of Technology	$400,000	Researchers will develop a seawater uranium extraction system that will work symbiotically with an offshore windmill by utilizing the structure, mooring and power of the windmill, while increasing the energy harvested by the installation. Uranium will be extracted by an adsorbent polymer belt, which will be cycled through the seawater and an elution plant located at the base of the windmill tower. Increasing the frequency of harvesting could overcome current economic barriers to seawater uranium extraction.	Document	FCR&D	FY2014
Imaging a Dry Storage Cask with Cosmic Ray Muons	Oregon State University	$799,871	Researchers will develop an imaging system to monitor the content of a dry storage cask with cosmic ray muons. A very large amount of plutonium under nuclear safeguards is contained in used fuel assemblies stored in dry storage casks. Muon imaging will allow a cost effective and reliable way to evaluate dry storage cask content and integrity before transport.	Document	FCR&D	FY2014
Apatite and sodalite based glass-bonded waste forms for immobilization of 129I and mixed halide radioactive wastes	Rutgers University	$800,000	Researchers will develop advanced and chemically durable waste forms for immobilizing 129I (aqueous based reprocessing of fuel) and mixed-halide wastes (molten-salt processing of fuel) by low temperature synthesis. Halide-containing sodalite and calcium phosphate-based apatite minerals will be synthesized, consolidated and tested for chemical durability. The project will provide needed baseline data for the development of advanced waste forms for immobilization of iodine and mixed-halide wastes.	Document	FCR&D	FY2014
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$350,000	Researchers will develop modeling tools supported by experiments for off-gas capture from future nuclear-fuel recycling facilities. Target species include tritium, iodine, krypton, and xenon. The models are intended to provide path forward recommendations to develop off-gas treatment adsorption processes. The project will contribute to the evaluation of options for environmentally acceptable recycle systems.	Document	FCR&D	FY2014
Development of high performance ODS alloys	Texas A&M University	$800,000	Researchers will study swelling, radiation hardening and changes in mechanical properties of ODS alloys to develop two sets of advanced ODS alloys. Two sets of first-round candidate alloys that have already undergone extensive development and testing will evaluate irradiation performance. The study will meet the need for high strength, radiation-tolerant cladding and core components that have enhanced resistance to void swelling.	Document	FCR&D	FY2014
Rare Earth Electrochemical Property Measurements and Phase Diagram Development in a Complex Molten Salt Mixture for Molten Salt Recycle	The Ohio State University	$800,000	Researchers will investigate rare earth (RE) properties in complex molten salt mixtures. In a molten salt recycle approach, the RE drawdown by electrolysis is a key step in which REs are separated from salt containing other fission products. Investigation of RE electrolysis must consider the electrochemical properties of the REs. We propose to conduct studies of detailed experiments and corresponding models to provide the physical properties and phase diagrams required to predict the performance of RE drawdown for processing complex molten salts.	Document	FCR&D	FY2014
Studies of Lanthanide Transport in Metallic Nuclear Fuels	The Ohio State University	$800,000	Researchers will study the redistribution of lanthanides and migration of lanthanides to the fuel surface. The mechanisms of lanthanide transport in metallic fuel based on the novel discovery of a Ôliquid-likeÕ transport mechanism will be studied analytically and experimentally. The project will develop a fundamental understanding of lanthanide fission product migration and redistribution in advanced metallic nuclear fuels, and theory and data to mitigate fuel-cladding chemical interactions.	Document	FCR&D	FY2014
Computational and Experimental Studies of Microstructure-Scale Porosity in Metallic Fuels for Improved Gas Swelling Behavior	University of Arkansas	$796,823	Researchers will study the microstructure of metallic uranium alloy fuels, and their resistance to densification, to minimize in-pile irradiation swelling through bimodal pore size distribution. The project will develop a predictive approach to design metallic fuel microstructures for optimal swelling resistance and fission gas retention.	Document	FCR&D	FY2014
Improved Hybrid Modeling of Spent Fuel Storage Facilities	University of California, Berkeley	$645,393	Researchers will develop a variance reduction method for computational transport that will improve the ability to design and operate monitoring systems for interim used fuel installations through enhanced modeling and simulation. This new tool will demonstrate that modeling calculations can be done more accurately in less time than with current tools and will perform studies characterizing how changes in material, cask configurations, and number of casks could impact monitoring systems.	Document	FCR&D	FY2014
Selective ligands for uranyl via combinatorial peptoid libraries: A synthetic, structural, thermodynamic and computational study	University of California, Berkeley	$400,000	Researchers will study how donor ligands bind to the uranyl ion, UO22+, with the longer-term goal of using this information to tackle selective recognition of uranyl in aqueous solution. The study will impact underlying approaches to controlling the behavior of uranium in these systems. The actinide separation technology could be used in several areas including uranium extraction from seawater, nuclear waste remediation and nuclear materials.	Document	FCR&D	FY2014
Combining Experiments and Simulations of Extraction Kinetics and Thermodynamics in Advanced Separation Processes for Used Nuclear Fuel	University of California, Irvine	$799,938	Researchers will study how the kinetics and thermodynamics of metal ion extraction in advanced separation processes for used nuclear fuel can be described by molecular dynamic (MD) simulations and how the simulations can be validated by experimental data. The project would have broad impacts on several separations processes including advanced TALSPEAK, ALSEP and GANEX by increasing the confidence and accuracy of computer modeling of metal ion extraction._	Document	FCR&D	FY2014
Effect of Metallic Li on the Behavior of Metals in Molten Salts	University of Nevada, Reno	$458,250	Researchers will identify the effect of metallic lithium on materials that are used in molten salt recycling. The study will try to understand how the presence of Li(0) in molten salts affects the degradation of alloys. Studying these changes will help accurately predict container material behavior and longevity.	Document	FCR&D	FY2014
Assessment of Corrosion Resistance of Promising Accident Tolerant Fuel Cladding under Reactor Conditions	University of Notre Dame	$800,000	Researchers will assess the corrosion behavior of accident tolerant fuel candidate iron-based alloys under normal LWR operating conditions consisting of high temperature, relevant water chemistry and irradiation. The assessment will produce data about possible irradiation-accelerated corrosion rates of iron-based alloys, and the mechanisms by which such corrosion rates are accelerated. The project will advance the selection of appropriate replacements for Zircaloy cladding.	Document	FCR&D	FY2014
Functionalized Porous Organic Polymers as Uranium Nano-Traps for Efficient Recovery of Uranium from Seawaterr	University of South Florida	$399,000	Researchers will develop functionalized porous organic polymers, or Ônano-trapsÕ for extraction of uranium from seawater. This technique allows for increased surface area and custom-designed pore size and chemistry to fit specific parameters. The adsorbent materials have high efficiency and effectiveness for uranium recovery from seawater, providing a potential supply for nuclear fuel.	Document	FCR&D	FY2014
Enhanced Accident-Tolerant Fuel Performance and Reliability for Aggressive iPWR/SMR Operation	University of Tennessee	$799,967	To develop a process that evaluates operational and safety performance of reactor-and-fuel combinations by integrating whole-core 3D neutronics with MOOSE/BISON fuel performance assessments via explicit time and space dependent fuel rod operational power histories. The project will be valuable in analyzing and evaluating accident tolerant fuel concepts and furthering the understanding of reactor physics and fuel performance aspects of key accident tolerant fuel concepts.	Document	FCR&D	FY2014
Nuclear Technology R&D Strategies in an Era of Energy Price Uncertainty	University of Texas, Austin	$799,112	Researchers will identify nuclear technology options that are competitive over a wide range of plausible future business environments. No single nuclear technology or business practice will be the best choice across all or even most future conditions. The study will focus on hybrid nuclear-fossil technologies, energy storage and conversion, which will result in an identification of nuclear strategies that can succeed under future market conditions.	Document	FCR&D	FY2014
Development and Optimization of Voltammetric Methods for Real Time Analysis of Electrorefiner Salt with High Concentrations of Actinides and Fission Products	University of Utah	$621,612	Researchers will develop an advanced voltammetry method to pursue the objective of real time monitoring of actinide concentrations in electrorefiner salt. This will include experimental measurement of key parameters such as activity coefficients and exchange current density. It will also involve simulation of voltammetry processes based on first principles. The project will allow for real time measurements that could support the commercialization of pyroprocessing.	Document	FCR&D	FY2014
Development of Self-Healing Zirconium-Silicide Coatings for Improved Performance of Zirconium-Alloy Fuel Cladding	University of Wisconsin, Madison	$798,621	Researchers will study the deposition of self-healing zirconium-silicide coatings on zirconium-alloy fuel cladding material to improve corrosion resistance under normal and accident conditions. Under these conditions, Zr-Si coating evolves into a highly protective functionally-graded multilayered system. The study will lead to improved performance of zirconium-alloy fuels._	Document	FCR&D	FY2014
Thermal Conductivity in Metallic Fuels	Virginia Polytechnic Institute and State University	$799,837	Researchers will calculate the thermal conductivity of metallic uranium and neptunium alloys, including the effects of noble gasses, using density functional theory. The experiments will validate the calculated effective thermal conductivity using the MARMOT code and by helping determine DFT simulation parameters. The study works to improve fuel lifetime by understanding its thermal behavior.	Document	FCR&D	FY2014
SiC-ODS Alloy Gradient Nanocomposites as Novel Cladding Materials	Virginia Polytechnic Institute and State University	$799,998	Researchers will combine nuclear nanomaterial design, processing, testing, and characterization efforts to develop revolutionary materials that can withstand neutron irradiation for long period of time using nanostructured SiC and oxide dispersion strengthened steel. The ultimate objective is to offer new cladding materials with increased corrosion resistance, strength, and creep resistance in both steady state and accident conditions.	Document	FCR&D	FY2014
Experimental Breeder Reactor II Benchmark Evaluation	Idaho State University	$400,000	Researchers will develop a benchmark evaluation of the Experimental Breeder Reactor II (EBR-II). During nearly 30 years of operation numerous experiments were conducted at EBR-II. The most significant of these experiments were conducted in 1986 demonstrating inherent safety features in loss of flow without reactor scram and loss of heat sink without reactor scram. Benchmark evaluation will be valuable for the reactor design efforts in the United States and South Korea.	Document	MSNE	FY2014
Integral full core multi-physics PWR benchmark with measured data	Massachusetts Institute of Technology	$400,000	Researchers will introduce BEAVRS, a new multi-cycle full-core Pressurized Water Reactor (PWR) depletion benchmark based on two operational cycles of a commercial nuclear power plant. This project aims at addressing the uncertainty quantification of the measured data and on making this benchmark a true non-proprietary international benchmark for the validation of high-fidelity multi-physics computational tools.	Document	MSNE	FY2014
Benchmark Evaluation of PROTEUS Gas-Cooled Reactor Experiments	University of Florida	$400,000	Researchers will create International Reactor Physics Experiment Evaluation Project (IRPhEP) benchmarks using data from 1970s experiments of the neutronics of gas-cooled fast reactor (GCFR) designs investigated in the PROTEUS reactor. The GCFR-PROTEUS experiments fill a gap in current integral benchmark data. These experiments can provide validation of computational models and nuclear data for next generation reactors.	Document	MSNE	FY2014
An Investigation To Establish Multiphysical Property Dataset Of Nuclear Materials Based On In-Situ Observations And Measurements	Purdue University	$800,000	Researchers will create an in-situ measurement based experimental approach to develop experimental validation dataset for NEAMS based code validation. Particular emphasis is on supplying data set for multiphysics simulations in extreme conditions as a function of material microstructure.	Document	NEAMS	FY2014
Experimental Validation of UO2 Microstructural Evolutions for NEAMS tool MARMOT	University of Florida	$798,000	Researchers will experimentally validate MARMOT for predicting the microstructural evolutions of UO2 oxide fuel under the driving forces of high temperatures and large temperature gradient in reactors. By performing the experiments and simulations simultaneously using precisely defined initial conditions, the experiment data will provide direct benchmarking of the MARMOT code.	Document	NEAMS	FY2014
High-resolution time-resolved experiments on mixing and entrainment of buoyant jets in stratified environments	University of Michigan	$799,983	Researchers will study high spatial and time-resolution experimental data of the fluid dynamics phenomena of flow jets interacting with a stratified layer. The issue plays an important role in the safety of several reactor designs, including sodium-cooled reactors. The data addresses the NEAMS needs for the validation of high fidelity computational fluid dynamics methodologies.	Document	NEAMS	FY2014
Fundamental study of key issues related to advanced S-CO2 Brayton Cycle: prototypic HX development and Cavitation	Georgia Institute of Technology	$799,000	Researchers will study scientific and operational issues pertinent to compact heat exchanger systems and turbo-machinery. The project will work to resolve issues with the fabrication of diffusion bonded compact heat exchangers, alternate heat exchange technology for recuperators, and resolution of issues with cavitation and fluid instabilities.	Document	RCRD&D	FY2014
Advanced Models for Nondestructive Evaluation of Aging Nuclear Power Plant Cables	Iowa State University	$787,291	Researchers will develop advanced models that relate environmentally induced microstructural and chemical changes in cable insulation polymers to their macroscopic electrical parameters. These parameters will be measured and modeled over a wide range of the electromagnetic spectrum, covering several potential nondestructive evaluation techniques, enabling identification of the most sensitive techniques for future development.	Document	RCRD&D	FY2014
Development of Novel Functionally Graded Transition Joints for Improving the Creep Strength of Dissimilar Metal Welds in Nuclear Applications	Lehigh University	$800,000	Researchers will develop graded transition joints and improved creep life models for increasing the life of dissimilar metal welds (DMWs) in nuclear reactors. The research represents the first application of functionally graded material concepts for solving the problem of DMW failures through an integrated approach of additive manufacturing, modeling, microstructural characterization, and advanced strain-sensing techniques.	Document	RCRD&D	FY2014
Feasibility Assessment of a Micro Modular Reactor (MMR)	North Carolina State University	$400,000	Researchers will develop an innovative compact reactor concept that integrates power production, power conversion and electricity generation in a single unit: the Micro Modular Reactor (MMR). It is designed to be absolutely melt-down proof (MDP) under all circumstances including complete loss of coolant scenarios with no possible release of radioactive material, to have a cycle length of greater than 10 years, and to be highly proliferation resistant.	Document	RCRD&D	FY2014
Scaling Studies for Advanced Gas Reactor Concepts	Oregon State University	$681,834	Researchers will expand the utilization of the Oregon State University High Temperature Test Facility (HTTF) to validate a broader range of advanced high temperature reactors and events. The facility will be revised to add a detailed scaling analysis of additional gas reactor concepts including advanced gas-cooled, molten salt, and sodium cooled reactors.	Document	RCRD&D	FY2014
Fluid Stratification Separate Effects Analysis, Testing and Benchmarking	Oregon State University	$800,000	Researchers will study fluid stratification in high temperature gas reactors. Coolant stratification is the result of incomplete mixing of one or more fluids, leading to a density gradient, which may or may not dissipate under diffusive or convective effects. This combined analytical and experimental project seeks to investigate stratification driven by diffusive and convective mechanisms and is expected to yield insight into this phenomenon.	Document	RCRD&D	FY2014
Probabilistic Economic Valuation of Safety Margin Management Analysis	Oregon State University	$795,364	Researchers will use RAVEN and develop a companion software package to facilitate economic analysis of safety margins. The project is a proof of concept that will use techniques to examine the cost of improving safety margins vs. the risk of accidents from not improving safety margins. This analysis can be used to evaluate the economic viability of various plant upgrades.	Document	RCRD&D	FY2014
Novel Dissimilar Joints Between Alloy 800H and 2.25%Cr and 1%Mo Steel	Pennsylvania State University	$800,000	Researchers will fabricate and test dissimilar metal joints between a nickel base alloy and a steel with gradual variations of chemical composition, microstructure and properties in a manner that reduces abrupt thermal expansion mismatch and the resulting residual stresses. Data on structure and properties will serve as valuable inputs for the initiation of an ASME code case.	Document	RCRD&D	FY2014
Multi-Phase Model Development to Assess RCIC System Capabilities under Severe Accident Conditions	Texas A&M University	$564,246	Researchers will develop physics-based models of the Reactor Core Isolation Cooling (RCIC) System and incorporating them into a multi-phase code for validation. The project will tackle the current major challenges in RCIC System analysis and enable evaluation of two-phase thermodynamic aspects.	Document	RCRD&D	FY2014
Experimental Investigation and CFD Analysis of Steam Ingress Accidents in HTGRs	The Ohio State University	$800,000	Researchers will study the steam ingress scenario for HTGRs. The study will investigate thermal-hydraulic behavior and graphite oxidation of stream ingress phenomena to validate predictive CFD models. This work will resolve concerns about possible steam generator tube ruptures in a HTGR He-Steam Rankine cycle.	Document	RCRD&D	FY2014
Coiled Tube Gas Heaters For Nuclear Gas-Brayton Power Conversion	University of California, Berkeley	$800,000	Researchers will develop heat exchangers for Brayton-cycle power conversion in reactors using sodium, NaK, or salt as intermediate coolants. The proposed coiled tube gas heaters (CTGHs) are expected to have excellent power density, thermal shock/creep, in-service inspection, and reparability characteristics.	Document	RCRD&D	FY2014
Fundamental Studies of Irradiation-Induced Modifications in Microstructural Evolution and Mechanical Properties of Advanced Alloys	University of Illinois, Urbana-Champaign	$800,000	Researchers will develop and test a mechanism for predicting neutron irradiation performance for optimized Grade 92 and Alloy 709 for applications in advanced reactor systems. The work will employ ion irradiations and available information from neutron irradiations of related alloys to develop a basis for predicting the neutron irradiation performance of the optimized alloys.	Document	RCRD&D	FY2014
Integrated Computational and Experimental Study of Radiation Damage Effects in Grade 92 Steel and Alloy 709	University of Tennessee	$800,000	Researchers will develop a mechanistic understanding and predictive models of irradiation-induced microstructural evolution and resulting mechanical properties in optimized ferritic-martensitic Grade 92 steel and austenitic alloy 709 using multiscale simulations coupled with rigorous experimental validation. The project will provide insights into the correlation between ion irradiation and fast neutron damage.	Document	RCRD&D	FY2014
Meta-Level Design Guidance and Operator Performance Measures for Hybrid Control Rooms	Vanderbilt University	$799,869	Researchers will apply human factors engineering methods and relevant expertise from non-nuclear high-risk high-consequence domains toward the measurement of operator performance in analog, digital, and hybrid main control rooms. Performance measures will be developed for evaluating the situation awareness and decision-making proficiencies to support the transition to digital or hybrid control room displays.	Document	RCRD&D	FY2014

FY 2015 Research and Development Awards

The Energy Department is awarding over $30 million through its Nuclear Energy University Programs (NEUP) to support 43 university-led nuclear energy research and development projects to develop innovative technologies and solutions. These projects will be led by 31 U.S. universities in 23 states.

A complete list of R&D projects with their associated abstracts is available below.

Title	Institution	Estimated Funding*	Project Description	Abstract	Project Type	Fiscal Year
Neutron Damage and MAX Phase Ternary Compounds	Drexel University			Document	IIR	FY2009
Atomistic Calculations of the Effect of Minor Actinides on Thermodynamic and Kinetic Properties of UO2+x	Georgia Institute of Technology			Document	IIR	FY2009
Maximum Fuel Utilization in Fast Reactors without Chemical Reprocessing	University of California, Berkeley			Document	IIR	FY2009
Developing a High Thermal Conductivity Fuel with Silicon Carbide Additives	University of Florida			Document	IIR	FY2009
Fabrication of Tungsten-Rhenium Cladding Materials via Spark Plasma Sintering for Ultra High Temperature Reactor Applications	University of Idaho			Document	IIR	FY2009
Ionic Liquid and Supercritical Fluid Hyphenated Techniques for Dissolution and Separation of Lanthanides, Actinides, and Fission Products	University of Idaho			Document	IIR	FY2009
Improved Fission Neutron Data Base for Active Interrogation of Actinides	University of Michigan			Document	IIR	FY2009
Utilization of Methacrylates and Polymer Matrices for the Synthesis of Ion Specific Resins	University of Nevada, Las Vegas			Document	IIR	FY2009
Improved LWR Cladding Performance by EPD Surface Modification Technique	University of Wisconsin, Madison			Document	IIR	FY2009
Advanced Models of LWR Pressure Vessel Embrittlement for Low Flux-High Fluence Conditions	University of California, Santa Barbara			Document	LWRS	FY2009
Irradiation Creep in Graphite	Boise State University			Document	NGNP	FY2009
Modeling the Stress Strain Relationships and Predicting Failure Probabilities For Graphite Core Components	Cleveland State University			Document	NGNP	FY2009
TRISO-Coated Fuel Durability Under Extreme Conditions	Colorado School of Mines			Document	NGNP	FY2009
An Innovative and Advanced Coupled Neutron Transport and Thermal Hydraulic Method (Tool) for the Design, Analysis and Optimization of VHTR/NGNP Prismatic Reactors	Georgia Institute of Technology			Document	NGNP	FY2009
Removal of 14C from Irradiated Graphite for Graphite Recycle and Waste Volume Reduction	Idaho State University			Document	NGNP	FY2009
Millimeter-Wave Thermal Analysis Development and Application to Gen IV Reactor Materials	Massachusetts Institute of Technology			Document	NGNP	FY2009
Accurate Development of Thermal Neutron Scattering Cross Section Libraries	North Carolina State University			Document	NGNP	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
Understanding Creep Mechanisms in Graphite with Experiments, Multiscale Simulations, and Modeling	North Carolina State University			Document	NGNP	FY2009
Simulations of the Thermodynamic and Diffusion Properties of Actinide Oxide Fuel Materials	University of Michigan			Document	AFCI	FY2009
Verification & Validation of High-Order Short-Characteristics-Based Deterministic Transport Methodology on Unstructured Grids	North Carolina State University			Document	NGNP	FY2009
Adsorptive Separation and Sequestration of Krypton, I and C14 on Diamond Nanoparticles	University of Missouri, Columbia			Document	AFCI	FY2009
Microscale Heat Conduction Models and Doppler Feedback	North Carolina State University			Document	NGNP	FY2009
Fundamental Understanding of Ambient and High-Temperature Plasticity Phenomena in Structural Materials in Advanced Reactors	Georgia Institute of Technology			Document	AFCI	FY2009
Development of Alternative Technetium Waste Forms	University of Nevada, Las Vegas			Document	AFCI	FY2009
Optimizing Neutron Thermal Scattering Effects in Very High Temperature Reactors	North Carolina State University			Document	NGNP	FY2009
Advanced Elastic/Inelastic Nuclear Data Development Project	Idaho State University			Document	AFCI	FY2009
Heterogeneous Recycling in Fast Reactors	Massachusetts Institute of Technology			Document	AFCI	FY2009
Quantification of UV-Visible and Laser Spectroscopic Techniques for Materials Accountability and Process Control	University of Nevada, Las Vegas			Document	AFCI	FY2009
Multiaxial Creep-Fatigue and CreepRatcheting Failures of Grade 91 and Haynes 230 Alloys Toward Addressing Design Issues of Gen IV Nuclear Power Plants	North Carolina State University			Document	NGNP	FY2009
Thermodynamic Development of Corrosion Rate Modeling in Iron Phosphate Glasses	Missouri University of Science and Technology			Document	AFCI	FY2009
Development of Subspace-Based Hybrid Monte Carlo-Deterministic Algorithms for Reactor Physics Calculations	North Carolina State University			Document	AFCI	FY2009
High-Fidelity Space-Time Adaptive Multiphysics Simulations in Nuclear Engineering	University of Nevada, Reno			Document	AFCI	FY2009
Improvements to Nuclear Data and Its Uncertainties by Theoretical Modeling	Rensselaer Polytechnic Institute			Document	AFCI	FY2009
Investigation of Countercurrent Helium-air Flows in Air-ingress Accidents for VHTRs	Ohio State University			Document	NGNP	FY2009
Sharp Interface Tracking in Rotating Microflows of Solvent Extraction	State University of New York at Stony Brook			Document	AFCI	FY2009
Bulk Nanostructured FCC Steels with Enhanced Radiation Tolerance	Texas A&M University			Document	AFCI	FY2009
Simulations of Failure via Three-Dimensional Cracking in Fuel Cladding for Advanced Nuclear Fuels	University of Texas, Dallas			Document	AFCI	FY2009
Testing of Performance of Optical Fibers Under Irradiation in Intense Radiation Fields, When Subjected to Very High Temperatures	Ohio State University			Document	NGNP	FY2009
Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels	Texas A&M University			Document	AFCI	FY2009
SiC Schottky Diode Detectors for Measurement of Actinide Concentrations from Alpha Activities in Molten Salt Electrolyte	The Ohio State University			Document	AFCI	FY2009
Computational Design of Advanced Nuclear Fuels	University of California, Davis			Document	AFCI	FY2009
Advanced Mesh-Enabled Monte Carlo Capability for Multi-Physics Reactor Analysis	University of Wisconsin, Madison			Document	AFCI	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
A Distributed Fiber Optic Sensor Network for Online 3-D Temperature and Neutron Fluence Mapping in a VHTR Environment	Texas A&M University			Document	NGNP	FY2009
Ab Initio Enhanced Calphad Modeling of Actinide Rich Nuclear Fuels	University of Wisconsin, Madison			Document	AFCI	FY2009
Investigation on the Core Bypass Flow in a Very High Temperature Reactor	Texas A&M University			Document	NGNP	FY2009
Development of Diffusion Barrier Coatings and Deposition Technologies for Mitigating Fuel Cladding Chemical Interactions (FCCI)	University of Wisconsin, Madison			Document	AFCI	FY2009
CFD Model Development and Validation for High Temperature Gas Cooled Reactor Cavity Cooling System (RCCS) Applications	Texas A&M University			Document	NGNP	FY2009
Thermal Properties of LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin, Madison			Document	AFCI	FY2009
Study of Air ingress across the duct during the accident conditions	Texas A&M University			Document	NGNP	FY2009
Verification of the CENTRM Module for Adaptation of the SCALE Code to NGNP Prismatic and PBR Core Designs	University of Arizona			Document	NGNP	FY2009
Integral and Separate Effects Tests for Thermal Hydraulics Code Validation for Liquid-Salt Cooled Nuclear Reactors	University of California, Berkeley			Document	NGNP	FY2009
Mechanisms Governing the Creep Behavior of High Temperature Alloys for Generation IV Nuclear Energy Systems	University of Cincinnati			Document	NGNP	FY2009
ALD Produced B2O3, Al2O3 and TiO2 Coatings on Gd2O3 Burnable Poison Nanoparticles	University of Colorado, Boulder			Document	NGNP	FY2009
Experimental Study and Computational Simulations of Key Pebble Bed Thermomechanics Issues for Design and Safety	University of Idaho			Document	NGNP	FY2009
Prediction and Monitoring Systems of Creep-Fracture Behavior of 9Cr-1Mo Steels for Reactor Pressure Vessels	University of Idaho			Document	NGNP	FY2009
Understanding Fundamental Material Degradation Processes in High Temperature Aggressive Chemomechanical Environments	University of Illinois, Urbana-Champaign			Document	NGNP	FY2009
Multi-Scale Multi-physics Methods Development for the Calculation of Hot-Spots in the NGNP	University of Michigan			Document	NGNP	FY2009
Corrosion and Creep of Candidate Alloys in High Temperature Helium and Steam Environments for the NGNP	University of Michigan			Document	NGNP	FY2009
Creation of a Full-Core HTR Benchmark with the Fort St. Vrain Initial Core and Validation of the DHF Method with Helios for NGNP Configurations	University of Michigan			Document	NGNP	FY2009
Fission Product Sorptivity in Graphite	University of Missouri, Columbia			Document	NGNP	FY2009
Identifying and Understanding Environment-Induced Crack Propagation Behavior in Ni-Based Superalloy INCONEL 617	University of Nevada, Las Vegas			Document	NGNP	FY2009
Graphite Oxidation Simulation in HTR Accident Conditions	University of New Mexico			Document	NGNP	FY2009
Non Destructive Thermal Analysis and In Situ Investigation of Creep Mechanism of Graphite and Ceramic Composites using Phase-sensitive THz Imaging & Nonlinear Resonant Ultrasonic Spectroscopy	University of Rochester			Document	NGNP	FY2009
Tritium Sequestration in Gen IV NGNP Gas Stream via Proton Conducting Ceramic Pumps	University of South Carolina			Document	NGNP	FY2009
Materials, Turbomachinery and Heat Exchangers for Supercritical CO2 Systems	University of Wisconsin, Madison			Document	NGNP	FY2009
Experimental Studies of NGNP Reactor Cavity Cooling System with Water	University of Wisconsin, Madison			Document	NGNP	FY2009
Assessment of Embrittlement of VHTR Structural Alloys in Impure Helium Environments	University of Wisconsin, Madison			Document	NGNP	FY2009
Modeling Fission Product Sorption in Graphite Structures	University of Wisconsin, Madison			Document	NGNP	FY2009
Liquid Salt Heat Exchanger Technology for VHTR Based Applications	University of Wisconsin, Madison			Document	NGNP	FY2009
Effect of Post-Weld Heat Treatment on Creep Rupture Properties of Grade 91 Steel Heavy Section Welds	Utah State University			Document	NGNP	FY2009
Alpha Radiolysis of Nuclear Solvent Extraction Ligands used for An(III) and Ln(III) Separations	California State University, Long Beach	$1,390,252		Document	FCR&D	FY2010
Predictive Maturity of Multi-Scale Simulation Models for Fuel Performance	Clemson University	$614,690		Document	FCR&D	FY2010
Freeze-casting as a Novel Manufacturing Process for Fast Reactor Fuels	Drexel University	$1,149,327		Document	FCR&D	FY2010
Fuel Performance Experiments on the Atomistic Level, Studying Fuel Through Engineered Single Crystal UO2	Idaho State University	$650,000		Document	FCR&D	FY2010
Development of A Self Biased High Efficiency Solid-State Neutron Detector for MPACT Applications	Rensselaer Polytechnic Institute	$810,141		Document	FCR&D	FY2010
Development of a Innovative High Thermal Conductivity UO 2 Ceramic Composites Fuel Pellets with Carbon Nano-Tubes Using Spark Plasma Sintering	University of Florida	$894,042		Document	FCR&D	FY2010
Exploration and Modeling of Structural Changes in Waste Glass under Corrosion	Pennsylvania State University	$1,377,444		Document	FCR&D	FY2010
Evaluation of materials for interim storage of spent fuel for more than 100 years	University of Michigan	$931,603		Document	FCR&D	FY2010
Implementation of On-the-Fly Doppler Broadening in MCNP5 for Multiphysics Simulation of Nuclear Reactors	University of Michigan	$406,712		Document	FCR&D	FY2010
Methods and tools to allow molecular flow simulations to be coupled to higher level continuum descriptions of flows in porous/fractured media and aerosol/dust dynamics	University of Missouri-Columbi	$541,286		Document	FCR&D	FY2010
Characterization and Modeling of Materials for Kr-Xe Separations	University of Nevada-Las Vegas	$989,800		Document	FCR&D	FY2010
Modeling Solute Thermokinetics in LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin-Madison	$616,073		Document	FCR&D	FY2010
Advanced Aqueous Separation Systems for Actinide Partitioning: Develop Fundamental Understanding of An(III)/Ln(III) Separation	Washington State University	$1,451,784		Document	FCR&D	FY2010
Consistent Multigroup Theory Enabling Accurate Coarse-Group Simulation of GenIV Reactors	Georgia Institute of Technology	$1,046,277		Document	GEN IV	FY2010
Studies of Deteriorated Heat Transfer in Prismatic Cores Stemming from Irradiation-Induced Geometry Distortion	Idaho State University	$1,287,921		Document	GEN IV	FY2010
Carbide Coatings for Nickel Alloys, Graphite, and Carbon/Carbon Composites to be Used in Fluoride Salt Valves	Johns Hopkins University	$1,183,239		Document	GEN IV	FY2010
Design, Testing, and Modeling of the Direct Reactor Auxiliary Cooling System for AHTRs	Ohio State University	$1,366,627		Document	GEN IV	FY2010
Monitoring microstructural evolution of Alloy 617 with nonlinear acoustics for remaining useful life prediction; multiaxial creep-fatigue and creep-ratcheting	Pennsylvania State University	$1,000,000		Document	GEN IV	FY2010
Development and Validation of Multidimensional Models of Supercritical CO 2 Energy Conversion Systems for Nuclear Power Reactors	Rensselaer Polytechnic Institute	$475,005		Document	GEN IV	FY2010
Multiscale Concrete Modeling for Aging Degradation	Mississippi State University	$345,941		Document	LWRS	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term and Elevated Temperature Irradiation: Modeling and Experimental Investigation	University of California-Berkeley	$1,320,667		Document	GEN IV	FY2010
Development of an advanced computational fluid dynamics technology for the next-generation nuclear reactor system analysis and safety margin characterization code	North Carolina State University	$418,199		Document	LWRS	FY2010
Development of Barrier Layers for the Protection of Candidate Alloys in the VHTR	University of California-Santa Barbara	$995,232		Document	GEN IV	FY2010
Precursor Derived Nanostructured Si-C-X Materials for Nuclear Applications	University of Washington	$899,518		Document	MRIIR	FY2010
Investigation of a Novel NDE Method for Monitoring Thermo-Mechanical Damage and Microstructure Evolution in Ferritic-Martensitic Steels for Generation IV Nuclear Energy Systems	University of Cincinnati	$833,109		Document	GEN IV	FY2010
Development and Testing of an Open-Loop Oscillator for Small Reactivity Worth Samples	Idaho State University	$597,252		Document	MRIIR	FY2010
Fission Product Transport in TRISO Particle Layers under Operating and Off-Normal Conditions	University of Michigan	$966,581		Document	GEN IV	FY2010
Understanding the Irradiation Behavior of Zirconium Carbide	Pennsylvania State University	$870,613		Document	MRIIR	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term Irradiation at Elevated Temperature: Critical Experiments	University of Michigan	$1,181,379		Document	GEN IV	FY2010
Modeling investigation of the stability and irradiation-induced evolution of nanoscale precipitates in advanced structural materials	University of Tennessee-Knoxville	$380,653		Document	MRIIR	FY2010
Three-dimensional NDE of VHTR Core Components via Simulation-based Testing	University of Minnesota	$1,366,163		Document	GEN IV	FY2010
Investigation of Laser Shock Peening for Enhancing Fatigue and Stress Corrosion Cracking Resistance of Nuclear Energy Materials	University of Cincinnati	$1,242,019		Document	MRIIR	FY2010
Failure Predictions for VHTR Core Components using a Probabilistic Continuum Damage Mechanics Model	University of Minnesota	$854,542		Document	GEN IV	FY2010
Irradiation Accelerated Corrosion of Reactor Core Materials	University of Michigan	$798,943		Document	MRIIR	FY2010
Development of a Scanning Microscale Fast Neutron Irradiation Platform for Examining the Correlation Between Local Neutron Damage and Graphite Microstructure	University of Missouri-Columbia	$703,064		Document	GEN IV	FY2010
Study of Interfacial Interactions using Thin Film Surface Modification: Radiation and Oxidation Effects in Materials	University of Wisconsin-Madison	$538,032		Document	MRIIR	FY2010
Development of Thermal Transient Flow Rate Sensors for High Temperature, Irradiation, Corrosive Environment	University of Nevada-Las Vegas	$451,269		Document	GEN IV	FY2010
Novel Engineered Refractory Materials for Advanced Reactor Applications	North Carolina State University	$1,129,304		Document	MRIIR	FY2010
Novel Methods of Tritium Sequestration: High Temperature Gettering and Separation Membrane Materials Discovery for Nuclear Energy Systems	University of South Carolina	$1,366,626		Document	GEN IV	FY2010
Heat Transfer Salts for Nuclear Reactor Systems - Chemistry Control, Corrosion Mitigation, and Modeling	University of Wisconsin-Madison	$1,352,040		Document	GEN IV	FY2010
Pulsed Magnetic Welding for Advanced Core and Cladding Steels	University of Wisconsin-Madison	$525,206		Document	GEN IV	FY2010
Corrosion in Supercritical Carbon Dioxide: Materials, Environmental Purity, Surface Treatments, and Flow Issues	University of Wisconsin-Madison	$651,447		Document	GEN IV	FY2010
Quantification of Cation Sorption to Engineered Barrier Materials Under Extreme Conditions	Clemson University	$1,171,380		Document	FCR&D	FY2011
In-Pile Instrumentation Multi-Parameter System Utilizing Photonic Fibers and Nanovision	Idaho State University	$1,199,990		Document	FCR&D	FY2011
Development of Plasmonically Cloaked Nanoparticles	Idaho State University	$800,000		Document	FCR&D	FY2011
Fission Product Transmutation in Mixed Radiation Fields	Idaho State University	$800,000		Document	FCR&D	FY2011
Life Prediction of Spent Fuel Storage Canister Material	Massachusetts Institute of Technology	$899,826		Document	FCR&D	FY2011
Active Interrogation using Photofission Technique for Nuclear Materials Control and Accountability	Oregon State University	$900,000		Document	FCR&D	FY2011
Anisotropic Azimuthal Power and Temperature Distribution on Fuel Rod: Impact of Hydride Distribution	Pennsylvania State University	$631,956		Document	FCR&D	FY2011
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$1,000,000		Document	FCR&D	FY2011
Recovery of Uranium from Seawater: Preparation and Development of Polymer-Supported Extractants	City College of New York, Hunter	$363,716		Document	MSTR	FY2011
Microemulsions and Aggregation Formation in Extraction Processes for Used Nuclear Fuel: Thermodynamics and Structural Studies	University of California, Irvine	$1,000,000		Document	FCR&D	FY2011
One-Dimensional Nanostructures for Neutron Detection	North Carolina State University	$455,629		Document	MSTR	FY2011
Optimized Processing Fabrication Paths for Larger Heats of Nanostructured Ferritic Alloys	University of California, Santa Barbara	$1,000,000		Document	FCR&D	FY2011
Feasibility and Safety Assessment for Advanced Reactor Concepts Using Vented Fuel	Oregon State University	$600,000		Document	MSTR	FY2011
Basic Physics Data: Measurement of Neutron Multiplicity from Induced Fission	University of Michigan	$973,364		Document	FCR&D	FY2011
Development of an Efficient Meso-Scale Multi-Phase Flow Solver in Nuclear Applications	City College of New York	$505,858		Document	NEAMS	FY2011
High Temperature Transducers for Online Monitoring of Microstructure Evolution	Pennsylvania State University	$455,628		Document	MSTR	FY2011
Radionuclide Incorporation and Long Term Performance of Apatite Waste Forms	University of Michigan	$862,500		Document	FCR&D	FY2011
Multiscale Modeling and Uncertainty Quantification for Nuclear Fuel Performance	Colorado State University	$1,098,250		Document	NEAMS	FY2011
Laser-Arc Hybrid Welding of Thick Section Ni-base Alloys- Advanced Modeling and Experiments	Pennsylvania State University	$536,117		Document	MSTR	FY2011
Actinide Foil Production for MPACT Research	University of Nevada-Las Vegas	$156,897		Document	FCR&D	FY2011
Fundamental Studies of the Role of Grain Boundaries on Uniform Corrosion of Advanced Nuclear Reactor Materials	Drexel University	$1,098,250		Document	NEAMS	FY2011
Correlates of Sensitive Technologies	Texas A&M University	$509,467		Document	MSTR	FY2011
Enriched Boron-Doped Amorphous Selenium Based Position-Sensitive Solid-State Thermal Neutron Detector for MPACT Applications	University of South Carolina	$1,000,000		Document	FCR&D	FY2011
Phenomena-based Uncertainty Quantification in Predictive Coupled-Physics Reactor Simulations	Texas A&M University	$1,098,250		Document	NEAMS	FY2011
Improved Safety Margin Characterization of Risk from Loss of Offsite Power	Texas A&M University	$600,000		Document	MSTR	FY2011
Development of Advanced High Uranium Density Fuels for Light Water Reactors	University of Wisconsin-Madison	$1,000,000		Document	FCR&D	FY2011
Characterization of Modeling of Grain Boundary Chemistry Evolution in Ferritic Steels Under Irradiation	University of Michigan	$1,098,250		Document	NEAMS	FY2011
Diffusion, Thermal Properties and chemical Compatibilities of Select MAX Phases with Materials for Advanced Nuclear Systems	Drexel University	$535,927		Document	NEET	FY2011
A High Temperature-Tolerant and Radiation-Resistant In-Core Neutron Sensor for Advanced Reactors	The Ohio State University	$455,629		Document	MSTR	FY2011
Developing the User Experience for a Next Generation Nuclear Fuel Cycle Simulator	University of Wisconsin-Madison	$1,200,000		Document	FCR&D	FY2011
Development of Multiscale Materials Modeling Techniques and Coarse-Graining Strategies for Predicting Materials Degradation in Extreme Irradiation Environments	University of Tennessee, Knoxville	$750,000		Document	NEAMS	FY2011
A New Light Weight Structural Material for Nuclear Structures	North Carolina State University	$399,490		Document	NEET	FY2011
Pathway Aggregation in the Risk Assessment of Proliferation Resistance and Physical Protection (PR&PP) of Nuclear Energy Systems	The Ohio State University	$534,471		Document	MSTR	FY2011
Experimental Investigation of Convection and Heat Transfer in the Reactor Core for a VHTR	City College of New York	$1,118,856		Document	RCRD&D	FY2011
Preparation of High Purity, High Molecular-Weight Chitin from Ionic Liquids for Use as an Adsorbate for the Extraction of Uranium from Seawater	University of Alabama	$338,260		Document	MSTR	FY2011
Graphite Microstructural Characterization Using Time-Domain and Correlation-Based Ultrasonics	Johns Hopkins University	$1,199,997		Document	RCRD&D	FY2011
Selectivity in Ligand Binding to Uranyl Compounds: A Synthetic, Structural, Thermodynamic and Computational Study	University of California-Berkeley	$500,000		Document	MSTR	FY2011
Methodology Development for Passive Component Reliability Modeling in a Multi-Physics Simulation Environment	The Ohio State University	$533,457		Document	RCRD&D	FY2011
Development of Seismic Isolation Systems Using Periodic Materials	University of Houston	$538,154		Document	MSTR	FY2011
Pebble Fuel Handling and Reactivity Control for Salt-Cooled High Temperature Reactors	University of California, Berkeley	$612,721		Document	RCRD&D	FY2011
Innovative Elution Processes for Recovering Uranium from Seawater	University of Idaho	$400,000		Document	MSTR	FY2011
Self-Sustaining Thorium Boiling Water Reactors	University of California, Berkeley	$1,145,932		Document	RCRD&D	FY2011
Development of Austenitic ODS Strengthened Alloys for Very High Temperature Applications	University of Illinois-Urbana Champaign	$538,154		Document	MSTR	FY2011
High Fluency Low Flux Embrittlement Models of LWR Reactor Pressure Vessel Embrittlement and a Supporting Database from the UCSB ATR-2 Irradiation Experiment	University of California, Santa Barbara	$1,199,607		Document	RCRD&D	FY2011
Enhancement of the Extraction of the Uranium from Seawater	University of Maryland	$400,000		Document	MSTR	FY2011
A Research Program for Fission Product/Dust Transport in HTGR's	University of Missouri-Columbia	$1,157,367		Document	RCRD&D	FY2011
Transient Safety Analysis of Fast Spectrum TRU Burning LWR with Internal Blankets	University of Michigan	$599,475		Document	MSTR	FY2011
Development and Validation of a Lifecycle-based Prognostics Architecture with Test Bed Validation	University of Tennessee, Knoxville	$846,315		Document	RCRD&D	FY2011
Development of Novel Sorbents for Uranium Extraction from Seawater	University of North Carolina, Chapel Hill	$400,000		Document	MSTR	FY2011
In-situ Condition Monitoring of Components in Small Modular Reactors Using Process and Electrical Signature Analysis	University of Tennessee, Knoxville	$650,000		Document	RCRD&D	FY2011
Radiation Behavior of High-Entropy Alloys for Advanced Reactors	University of Tennessee, Knoxville	$538,159		Document	MSTR	FY2011
Technical Development for S-CO2 Advanced Energy Conversion	University of Wisconsin	$815,000		Document	RCRD&D	FY2011
Rapid Computer Aided Ligand Design and Screening of Precious Metal Extractants from TRUEX Raffinate with Experimental Validation	Washington State University	$500,000		Document	MSTR	FY2011
Ag Transport Through Non-Irradiated and Irradiated SiC	University of Wisconsin-Madison	$1,055,456		Document	RCRD&D	FY2011
Critical Heat Flux Phenomena at High Pressure and Low Mass Fluxes: Tests and Models	University of Wisconsin-Madison	$1,199,781		Document	RCRD&D	FY2011
Modeling and Test Validation of a Reactor Cavity Cooling System with Air	University of Wisconsin-Madison	$1,199,988		Document	RCRD&D	FY2011
Transient Mixed Convection Validation for NGNP	Utah State University	$635,860		Document	RCRD&D	FY2011
Alternative High-Performance Ceramic Waste Forms	Alfred University	$840,000	This project aims to advance fundamental understanding of the kinetics of structural evolution of crystalline ceramic waste forms. The structure/property relationships will be identified and will reveal new formulations, improved processing routes, and strategies for improved performance or ceramic waste forms.	Document	FCR&D	FY2012
Surface Layer Bulk Glass Interface Evolution with Aqueous Corrosion	Alfred University	$880,000	This project will investigate the links between the morphology, structure and chemistry of surface layer-bulk glass interface and the long-term corrosion-reaction kinetics using in-situ and ex-situ experiments. The understanding will result in improved models for long-term predictive behavior of high-level-waste (HLW) glasses under repository conditions.	Document	FCR&D	FY2012
Improved Accident Tolerance of Austenitic Stainless Steel Cladding through Colossal Supersaturation with Interstitial Solutes	Case Western Reserve University	$850,000	This project aims to develop new case-hardened austenitic stainless steels by saturating them with materials that improve their mechanical properties, corrosion resistance and radiation resistance. This project, if successful, will result in safer, longer-lasting, and more accident tolerant fuel claddings.	Document	FCR&D	FY2012
Optimization of Deep Borehole Systems for HLW Disposal	Massachusetts Institute of Technology	$850,000	Researchers aim to carry out a comprehensive evaluation of the deep borehole option for disposal of used nuclear fuel and high livel waste. The models developed will predict potential movement of water through natural and engineered barriers and release of radionuclides to the biosphere which will aide in site selection.	Document	FCR&D	FY2012
Scholarship for Nuclear Communications and Methods for Evaluation of Nuclear Project Acceptability	Massachusetts Institute of Technology	$800,000	Researchers will work to develop a model to characterize the factors affecting social acceptance of nuclear projects with potential stakeholders. The resultant model will strengthen the ability to design and implement large projects more efficiently, leading to higher rates of success of future nuclear projects.	Document	FCR&D	FY2012
Accurate Holdup Calculations with Predictive Modeling and Data Integration	North Carolina State University	$875,000	Researchers will develop and use state-of-the-art radiation transport codes to account accurately for the fissile material in a nuclear materials processing facility. An accurate estimation of the materials will allow for ensured radiological safety, security, waste management and efficient plant operation.	Document	FCR&D	FY2012
Novel Metal Sulfides to Achieve Effective Capture and Durable Consolidation of Radionuclides	Northwestern University	$760,000	Researchers will evaluate the effectiveness of chalcogenide based materials design novel metal sulfides to effectively capture and store of radioisotopes released during reprocessing of used nuclear fuel. This project will focus on understanding structure-property relationships to enable refined and direct synthesis approaches for improved and cost-efficient nuclear waste forms.	Document	FCR&D	FY2012
Nonlinear Ultrasonic Diagnosis and Prognosis of ASR Damage in Dry Cask Storage	Northwestern University	$885,000	Researchers aim to use nondestructive damage characterization methods to detect, manage and mitigate the degradation/damage mechanisms of dry cask storage systems for nuclear fuels. This project, if successful, will provide tools that will allow the prediction of the reliability and the safety of concrete structures in dry cask storage systems.	Document	FCR&D	FY2012
Prototype Demonstration of Gamma-Blind Tensioned Metastable Fluid Neutron/Multiplicity/Alpha Detector- Real Time Methods for Advanced Fuel Cycle Applications	Texas A&M University	$875,000	This project aims to create a prototype demonstration of a novel neutron/alpha detector based on a technology that is blind to gamma field used fuel. The prototype, if successful, will enhance instrumentation for monitoring real-time material balance during various stages of the nuclear cycle.	Document	FCR&D	FY2012
Testing of Sapphire Optical Fiber and Sensors in Intense Radiation Fields, when Subjected to Very High Temperatures	The Ohio State University	$885,000	The researchers on this project will investigate the performance of sapphire optical fibers and sensors in reactor environments. The project, if successful, will result in improved instrumentation to understand the behavior and predict performance of nuclear fuel systems at the microstructural level.	Document	FCR&D	FY2012
Concrete Materials with Ultra-High Damage Resistance and Self-Sensing Capacity for Extended Nuclear Fuel Storage Systems	University of California, Irvine	$800,000	Researchers aim to design a new class of multifunctional concrete materials. This project, if successful, will result in a novel multifunctional concrete material that possesses inherent degradation monitoring capability and is suitable for an extended storage system for the used nuclear fuel.	Document	FCR&D	FY2012
Development of Innovative Accident Tolerant High Thermal Conductivity UO2 Fuel Pellets with a Diamond Dopant	University of Florida	$800,000	Researchers will evaluate the use of diamond nanoparticles composite material in innovative accident tolerant fuel pellets. This could significantly improve both the thermal conductivity of fuel pellets and light water reactors' efficiency safety.	Document	FCR&D	FY2012
Probabilistic Multi-Hazard Assessment of Dry Cask Structures	University of Houston	$865,000	This project aims to investigate the performance of dry cask storage systems under multiple hazard systems (earthquake, tornados, combined with aging effects) using a probabilistic multi-hazard framework. This framework will be validated based on experimental research and will provide improved models for safety and reliability of spent nuclear fuels during storage and transportation.	Document	FCR&D	FY2012
Measurement of Irradiated Pyroprocessing Samples via Laser Induced Breakdown Spectroscopy	University of Idaho	$820,000	This project aims to use advanced characterization techniques to investigate microstructural changes and the micromechanisms related to irradiation induced damage in used nuclear fuels and waste forms. This project, if successful, will result in enhanced models to predict the structural and chemical response of used fuel and waster forms during interim storage and permanent disposal.	Document	FCR&D	FY2012
Elastic/Inelastic Measurement Project	University of Kentucky	$880,523	Researchers will measure nuclear data for elastic/inelastic scattered neutrons on coolants and structural materials. The data generated, will be useful for future R&D programs that will study innovative next generation LWR and future fast systems.	Document	FCR&D	FY2012
Electrochemical Corrosion Studies for Modeling Metallic Waste Form Release Rates	University of Nevada- Las Vegas	$790,000	This project aims to use advanced electrochemical methods to investigate the corrosion related degradation of metal alloys used for housing fission products. The data obtained from this study will allow for the prediction of the long-term behavior of the metallic host phase materials over geological time-scales.	Document	FCR&D	FY2012
Thermodynamic and Microstructural Mechanisms in the Corrosion of Advanced Ceramic Tc-bearing Waste Forms and Thermophysical Properties	University of Nevada- Las Vegas	$795,000	This project team will harvest thermodynamic and microstructural data on the evolution of ceramic based waste forms. The data will be used to advance the current state-of-the-art methodology used for isolation and stabilization of fission products and improve on nuclear fuel recycling processes.	Document	FCR&D	FY2012
Development and Experimental Benchmark of Simulations to Predict Used Nuclear Fuel Cladding Temperatures during Drying and Transfer Operations	University of Nevada- Reno	$745,000	Researchers will conduct experiments to investigate and develop advanced computational models of heat transfer in post-pool-storage drying operations. This project, if successful, will result in tools that can be used to design efficient drying processes to as to ensure suitability for dry-cask systems for long-term storage and transport.	Document	FCR&D	FY2012
Better Radiation Response and Accident Tolerance of Nanostructured Ceramic Fuel Materials?	University of Tennessee	$815,000	Researchers will use novel experimental methods to investigate the links between microstructure, phase stability and damage evolution in nanostructured ceramic fuel materials. The project will study fuel materials at temperatures and irradiation conditions relevant to operation and accidental scenarios.	Document	FCR&D	FY2012
Radiation and Thermal Effects on Used Nuclear Fuel and Nuclear Waste Forms	University of Tennesssee	$770,000	This project aims to investigate the structural and chemical response of used nuclear fuel and waste forms during interim storage and permanent disposal. If successful, this project will generate models that will allow the prediction of structural evolution and hence the radiological safety and security of nuclear fuel and waste forms.	Document	FCR&D	FY2012
Seismic Performance of Dry Casks Storage for Long-Term Exposure	University of Utah	$873,319	Researchers will evaluate the mechanical performance of dry-cask storage under seismic loading for mid-term operational periods. Simulations will include scenarios for freestanding, anchored, and vaulted casks. The experimental tests will also evaluate the dynamic seismic response of freestanding and anchored dry-cask storage prototypes, providing recommendations for optimal Interim Spent Fuel Storage Installations (ISFSIs) design.	Document	FCR&D	FY2012
Validation Experiments for Spent-Fuel Dry-Cask In-Basket Convection	Utah State University	$690,000	Researchers in this project aim to conduct experiments that generate data on natural convection through a fuel assembly. The data will be used to validate the computational models being developed for nuclear safety and design.	Document	FCR&D	FY2012
Re-Branding the Nuclear Fuel Cycle	Virginia Commonwealth University	$850,000	This project will create a comprehensive framework for the evaluation of alternative fuel cycle systems that will be used to identify and analyze key elements related to long-term management of nuclear fuels , with the ultimate goal to develop a communications strategy to reach stakeholders.	Document	FCR&D	FY2012
Advanced Characterization of Molecular Interactions in TALSPEAK-like Separations Systems	Washington State University	$875,000	Researchers will use advanced characterization techniques (experimental and computational) to improve understanding of the molecular level processes/interactions during separation processes for advanced fuel cycles. The understanding of these interactions will be used to develop more robust and streamlined separation processes for advanced fuel cycles.	Document	FCR&D	FY2012
Coupling of Nuclear Waste Form Corrosion and Radionuclide Transport in Presence of Relevant Repository Sediments	Washington State University	$885,000	Researchers will conduct experiments to understand the mechanisms responsible for the corrosion of nuclear waste forms in realistic chemical environments. The data generated from these experiments will enable increased reliability of the models used to predict the waste form performance in repository environments.	Document	FCR&D	FY2012
Stationary Liquid Fuel Fast Reactor (SLFFR) Concept for TRU Burning	Purdue University	$450,000	Reasearchers will investigate a new type of molten metallic fuel reactor concept that will consume hazardous transuranic waste. The liquid fuel alloy has several advantages over solid fuel fast reactors that are used for the same purpose.	Document	MSTR	FY2012
ABR for TRU Transmutation with Breed & Burn Thorium Blanket for Improved Economics and Resource Utilization	University of California- Berkeley	$450,000	The research team will use detailed neutronic analysis for a new Advanced Burner Reactor concept with low conversion ratio. The concept will use a new core shape to improve the utilization of neutrons to perform breed and burn.	Document	MSTR	FY2012
New Materials for High Temperature Thermoelecric Power Generation	University of California, Davis	$450,000	Reasearchers will work to develop nanostructured and other new materials to support the development of higher efficiency thermoelectric devices. These devices convert thermal energy to electricity with no moving parts. The new materials will operate at higher efficiencies and over a wider temperature range than those currently available--an important quality for future nuclear-powered deep space exploration.	Document	MSTR	FY2012
Microscopic Fuel Particles Produced by Self-Assembly of Actinide Nanoclusters on Carbon Nanomaterials	University of Notre Dame	$440,000	Reasearchers will develop the mechanisms, conditions and protocols to prepare uranium-carbon nanocomposite materials to make them more flexible. This could result in the generation of wholesale electricity, providing process heat, and providing power for households.	Document	MSTR	FY2012
High Hydrogen Content Graphene Hydride Compounds & High Cross-Section Cladding Coatings for Fast Neutron Detection	University of South Carolina	$430,000	This project will exploit recent breakthroughs to grow epitaxial graphene on commercial SiC wafers. This will allow researchers to develop a new detection method for fast neutrons. In addition, it will lead to better and more compact neutron detection system.	Document	MSTR	FY2012
Reducing Actinide Production Using Inert Matrix Fuels	University of Texas- Austin	$435,000	Reasearchers will perform a neutronic analysis, a thermal-hydraulic analysis and a simulation of fuel decay heat as a functionof fuel burnup, to determine if inert matrix fuel in coventional reactors will continue to be licensable. If successful, the inert matrix fuel mixtures will reduce harmful transuranic components in the fuel discharge streams at a level comparable to a fast reactcor burner.	Document	MSTR	FY2012
An Integrated Fuel Depletion Calculator for Fuel Cycle Options Analysis	University of Texas- Austin	$395,000	Reasearchers use new analysis techniques to better predict nuclear fuel behavior. The new model will allow improved fuel cycle for a larger number of users.	Document	MSTR	FY2012
Atomic-Scale to Meso-Scale Simulation Studies of Thermal Ageing and Irradiation Effects in Fe-Cr Alloys	Boston University	$874,997	Reasearchers will develop predictive, multi-scale simulation tools for iron-chromium alloys, which are expected to be key components of advanced steels envisioned as fuel cladding and structural components for Generation IV reactors. Such modeling is necessary to avoid resource intensive and costly thermal and neutron irradiation experiments to obtain required performance data.	Document	NEAMS	FY2012
Validation Data and Model Development for Fuel Assembly Response to Seismic Loads	George Washington University	$862,435	Reasearchers will conduct experiments that will provide comprehensive data characterizing the dynamics of the fluid and the structure in Pressurized Water Reactors (PWR) fuel assemblies under seismic loads (earthquakes and loss of coolant accidents). Completion of their project will greatly benefit the safety of existing and future nuclear reactors.	Document	NEAMS	FY2012
Uncertainty Quantification and Management for Multiscale Nuclear Materials Modeling	Georgia Institute of Technology	$743,444	Reasearchers will address the question of uncertainty propogation and error estimates associated with model prediction of material behavior under irradiation. Their work will facilitate a better understanding of the connection of various unit processes to collective responses in a multiscale model chain enabling the development of high strength and high ductility materials.	Document	NEAMS	FY2012
Fuel and Core Design Options to Overcome the Heavy Metal Loading Limit and Improve Performance and Safety of Liquid Salt Cooled Reactors	Georgia Insitute of Technology	$784,689	Reasearchers will examine new options for fuel and core designs in liquid salt cooled reactors where the current standard of TRISO type fuel has limitations due to loading characteristics. The research could enable new, more feasible fuel-core-reload options that will improve safety and performance parameters.	Document	RCRD&D	FY2012
Nonlinear Ultrasonic Techniques to Monitor Radiation Damage in RPV and Internal Components	Georgia Institute of Technology	$877,000	Reasearchers will explore new nondestructive materials evaluation and monitoring techniques utilizing nonlinear ultrasonic measurements . This technique will allow researchers to assess remaining useful life of select reactor components. Breakthroughs in this area will lead to the ability to characterize radiation damage in reactor pressure vessels and other components-leading to a clearer definition of reactor safety margins.	Document	RCRD&D	FY2012
Intergral Reactor Containment Condensation Model and Experimental Validation	Oregon State University	$871,119	Reasearchers will conduct experiments to enhance the safety and efficiency of small modular reactors (SMRs). This project will assess the impact of high-pressure steam condensation on steel containment vessels to be used for SMR deigns.	Document	RCRD&D	FY2012
Investigation of Natural Circulation Instability and Transients in Passively Safe Small Modular Reactors	Purdue University	$871,100	Reasearchers will perform scaled experiments to study the thermal-hydraulic instabilities that can occur in Small Modular Reactors (SMR) which rely on natural circulation cooling during normal operation and accident conditions. Their work will not only improve our understanding of general natural circulation instability but also lead to the development of stability criteria and predictability in the operation of SMRÃs.	Document	RCRD&D	FY2012
Thermoelectric-Driven Sustainable Sensing and Actuation Systems for Fault-Tolerant Nuclear Incidents	State University of New York, Stony Brook	$599,802	Reasearchers will examine the use of solid-state thermoelectric generators to produce electricity to sense and opeate during both normal and abnormal situations. This will provide indefinite monitoring of key components during power outages or station blackouts.	Document	RCRD&D	FY2012
Experimental and CFD Studies of Coolant Flow Mixing within Scaled Models of the Upper and Lower Plenums of NGNP Gas-Cooled Reactors	Texas A&M University	$713,051	Reasearchers will model the internal coolant flow of a prismatic core very high temperature reactor (VHTR) by using large eddy simulation tools. This method will enable more accurate prediction of flow field characteristics and better evaluation of VHTR behavior under operational and accidental conditions.	Document	RCRD&D	FY2012
Demonstrating Hybrid Heat Transport and Energy Conversion System Performance Characterization Using Intelligent Control Systems	University of Idaho	$877,000	Reasearchers will demonstrate an intelligent control systems in a hybrid energy conversion loop for a next generation nuclear power plant. Hybrid energy systems are a method of optimizing the use of natural resources for energy production. Hybrid systems present an opportunity to develop domestic energy sources to improve energy security.	Document	RCRD&D	FY2012
Advanced Reactor-Intermediate Heat Exchanger (IHX) Coupling: Theoretical Modeling and Experimental Validation	University of Idaho	$869,997	Reasearchers will model the behavior of the Advanced Reactor Intermediate Heat Exchanger Chemical Process system and develop advanced control techniques that take into account abnormal scenarios. The data and information obtained will assist in the development of intelligent control systems for next generation nuclear reactor systems.	Document	RCRD&D	FY2012
Irradiation Performance of Fe-Cr Base Alloys	University of Illinois- Urbana Champaign	$876,332	Reasearchers will perform post-radiation analysis and develop tools for future development and application of the Fe-Cr class of alloys. The results of this research will lead to better modeling of performance and development of an alloy designated as the primary choice for reactor fuel cladding and structural applications in advanced systems.	Document	RCRD&D	FY2012
Accelerated Irradiations for High Dose Microstructures in Fast Reactor Alloys	University of Michigan	$831,876	Reasearchers will determine the extent to which high dose rate irradiation can be used as an irradiation damage tool to understand microstructure evolution at high doses and temperatures relevant to advanced fast reactors. The project will provide fundamental understanding of the effectiveness of this process and thus of microstructure development in irradiated materials.	Document	RCRD&D	FY2012
Mitigating IASCC of Reactor Core Internals by Post-Irradiation Annealing Advanced Mitigation Strategies	University of Michigan	$876,985	Reasearchers will determine the optimum Post-irradiation annealing (PIA)-driven mitigation strategy to extend the potential lifetime of light water reactors. Samples that have already been irradiated in a light water reactor will be used to test PIA treatments to understand IASCC initiation and propoagation, annealing kinetics, the role of microstructure features in irradation hardening and localized deformation, and the optimum mitigation strategy based on PIA.	Document	RCRD&D	FY2012
Experimentally Validated Numerical Models for Effects of Non-Isothermal Turbulent Mixing on Wall Stresses in High Temperature Reactors	University of Pittsburgh	$876,422	Reasearchers will develop a comprehensive experimentally validated computational framework for the turbulent mixing in the lower plenum of a very high temperature reactor (VHTR). Through CFD modeling and experimental validation, the results from this project will lay the groundwork for future stress analysis, failure and fatigue studies, and uncertainty quantification for the VHTR system.	Document	RCRD&D	FY2012
Role of Defects in Swelling and Creep of Irradiated SiC	University of Wisconsin- Madison	$875,350	Reasearchers will study mechanisms controlling both radiation swelling and radiation creep in silicon carbide. These two effects are crucial to understanding the issues associated with the brittle silicon carbide composite. Success in this project will ground progress in the adoption of silicon carbide for reactor solutions, particularly as fuel cladding.	Document	RCRD&D	FY2012
Advanced Supercritical Carbon Dioxide Brayton Cycle Development	University of Wisconsin, Madison	$877,000	Reasearchers will investigate the benefits of utilizing advanced Brayton cycles with supercritical carbon dioxide in new reactor systems and components. Benefits of this research include improvement of analysis and performance of components currently utilizing these cycles as well as the potential for a large scale advanced CO2 power system.	Document	RCRD&D	FY2012
Mechanical Behavior of UO2 at Sub-grain Length Scales: Quantification of Elastic, Plastic and Creep Properties via Microscale Testing	Arizona State University	$800,000	Reasearchers will develop techniques to measure properties at sub-grain scales using depleted Uranium Oxide samples. The project will provide a framework to measure sub-grain scale mechanical properties, as well as provide experimental data to improve the understanding of advanced oxide fuels.	Document	FCR&D	FY2013
The Impacts of Pore-Scale Physical and Chemical Heterogeneities on the Transport of Radionuclide-Carrying Colloids	Colorado School of Mines	$800,000	Reasearchers will identify the dominant transport mechanisms to develop models that predict radionuclide distribution in porous materials. Experimental and computational models will be created that couple pore-scale geometric and interfacial structures. Simulators such as these are a necessary step towards fully predictive models for field-scale applications in the future.	Document	FCR&D	FY2013
Recovery of Uranium from Seawater: Polymer-Supported Aminophosphinates as Selective Extractants	Hunter College, CUNY	$399,999	Reasearchers will prepare a polymer-supported extractant for the recovery of uranium from seawater. The project will focus on primary amines that could provide a 3-fold increase in uranium capture capacity than current methods.	Document	FCR&D	FY2013
In-pile Thermal Conductivity Characterization with Single-laser Heating/Time Resolved Raman	Iowa State University	$800,000	Reasearchers will develop a time-resolved Raman-based thermal conductivity measurement system to improve remote in-pile thermal conductivity measurement. These measurements will provide new insights into the behavior of materials exposed to extreme radiation and temperature environments. Understanding the behavior of materials at the microstructural level will support optimized fuel designs.	Document	FCR&D	FY2013
Organic Speciation and Interactions in ALSEP - One Step Partitioning Process of Minor Actinides, Lanthanides, and Fission Products	Oregon State University	$600,000	Reasearchers will investigate the Actinide-Lanthanide Separation (ALSEP) process organic phase prior to aqueous phase separation and after aqueous separation phases of bare and metal-loaded acids. Quantifying these effects can be used to determine how an engineering scale process will perform and generate an accurate chemical model for the system.	Document	FCR&D	FY2013
Glass Composition and Solution Speciation Effects on Stage III Dissolution	Pennsylvania State University	$700,000	Reasearchers will study the chemical and structural triggers of long-term vitrified nuclear waste form behavior. They will study a range of waste glass compositions in corrosive environments. The study will improve understanding of the long-term residual rate and may provide new options for environmental control of glass dissolution rates.	Document	FCR&D	FY2013
Correlating Thermal, Mechanical, and Electrical Coupling Based Multiphysics Behavior of Nuclear Materials Through In-Situ Measurements	Purdue University	$800,000	Reasearchers will use in-situ experimental techniques to monitor the influence of extreme conditions on fuel cladding. The project will establish an in-situ experimental setup that can predict change in thermal properties and their correlation with mechanical properties and correlate such changes to changes in microstructural and chemical features.	Document	FCR&D	FY2013
Creation of a Geant4 Muon Tomography Package for Imaging of Nuclear Fuel in Dry Cask Storage	Purdue University	$440,000	Reasearchers will develop a simulation and analysis package to aid in the non-destructive assessment of sealed used nuclear fuel dry casks using cosmic ray muons. Cosmic ray muon tomography allows for non-destructive assessment that can independently verify and identify weapons grade material sealed within dense dry casks.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Two-stage Fast Reactor Fuel Cycle Options for Optimum Resource Utilization and Waste Management	Purdue University	$400,000	Reasearchers will evaluate the two different two-stage fast reactor fuel cycle options that will offer efficient use of uranium resources and the ability to burn actinides and long-live fission products. Evaluation of these fast fuel cycle options will serve as a useful complement to the options currently being considered in the Fuel Cycle Options Campaign.	Document	FCR&D	FY2013
Mixed Metal Phosphonate-Phosphate Resins for Separation of Lanthanides from Actinides	Texas A&M University	$650,000	Reasearchers will use ion exchangers to cleanly separate lanthanides and curium from reusable actinides. The study will assist in the development of an inexpensive, simple way in which to separate lanthanides from actinides found in used nuclear fuel rods and to recover a large portion of the usable fuel.	Document	FCR&D	FY2013
Safeguards in Pyroprocessing: an Integrated Model Development and Measurement Data Analysis	The Ohio State University	$626,151	Reasearchers will develop a comprehensive and effective safeguards approach for a pyroprocessing facility to support safeguards for future fuel cycles in the United States. The new approach and design will focus directly on the special nuclear materials in the electrorefiner where actinides are separated from fission products through electrochemical process.	Document	FCR&D	FY2013
Using Ionic Liquids for the Development of Renewable Biopolymer-Based Adsorbents for the Extraction of Uranium from Seawater and Testing Under Marine Conditions	University of Alabama	$400,000	Reasearchers will explore the fundamental engineering parameters for a renewable high-performance adsorbent for the extraction of uranium from sweater based on a recently proven ionic liquid (IL)-chitin platform. The project will use the platform to develop a versatile, modifiable adsorbent and characterize its performance and degradation in marine conditions.	Document	FCR&D	FY2013
Developing Ultra-Small Scale Mechanical Testing Methods and Microstructural Investigation Procedures for Irradiated Materials.	University of California, Berkeley	$800,000	Reasearchers will develop new small-scale mechanical testing techniques to allow for the estimation or direct measurement of bulk properties. The combined experiments and modeling will significantly enhance the statistics and information that can be obtained on small radioactive archived samples, as well as new ion beam irradiated specimens.	Document	FCR&D	FY2013
Improved Delayed-Neutron Spectroscopy Using Trapped Ions	University of California, Berkeley	$400,000	Reasearchers will develop innovative spectroscopy techniques to measure the decay of fission fragments. The resulting data from these new techniques will be used to better understand reactor kinetics under accident conditions and failure scenarios.	Document	FCR&D	FY2013
Thermally and Chemically Responsive Nanoporous Materials for Efficient Capture of Fission Product Gases	University of California, Davis	$750,000	Reasearchers will create new nanoporous materials that will be highly effective at capturing fission product gases. These materials would be relevant to both reactor fuels applications and reprocessing operations. Tests will be performed in carbon based and nitride based nanostructures, with the most promising materials from the modeling perspective undergoing further testing.	Document	FCR&D	FY2013
Multiphase Nanocrystalline Ceramic Concept for Nuclear Fuel	University of California, Irvine	$800,000	Researchers will study the use of nanoparticles and nanostructured ceramics to create new materials that can extend the service life and increase efficiency for nuclear fuel. Multiphase nanocrystalline ceramics will be used to design simulated nuclear fuel that can provide added plasticity, better radiation tolerance and improved thermal conductivity.	Document	FCR&D	FY2013
Development of Novel Porous Sorbents for Extraction of Uranium from Seawater	University of Chicago	$400,000	Reasearchers will develop a highly porous sorbent for the extraction of uranium from seawater. Previous research has established sorbent performance. This project will use past foundational studies to design and investigate a new nanocomposites that will be processed into tacks or braids for field tests in seawater tests. The technology may also be used for other metals.	Document	FCR&D	FY2013
Microwave Readout Techniques for Very Large Arrays of Nuclear Sensors	University of Colorado, Boulder	$799,937	Reasearchers will develop a powerful readout technique based on microwave transmission and reflection. The technique will enable very large arrays of diverse sensor types for nuclear materials quantification and tracking. It will provide more accurate data on material composition and quantity.	Document	FCR&D	FY2013
BiI3 Gamma-Ray Spectrometers for Reliable Room-Temperature Nuclear Materials Safeguarding	University of Florida	$799,999	Reasearchers will develop gamma-ray spectrometers based on BiI3 single crystals for MPACT applications such as burnup validation quantification, improved assay of plutonium, determination of uranium enrichment and overall monitoring spent fuel within the fuel cycle. The project will improve energy resolution, efficiency and environmental performance with this new gamma-ray detector.	Document	FCR&D	FY2013
Innovative Coating of Nanostructured Vanadium Carbide on the F/M Cladding Tube Inner Surface for Mitigating the Fuel Cladding Chemical Interactions	University of Florida	$760,276	Researchers will develop barrier coatings on the inner surface of fuel cladding tubes to improve performance of materials at elevated temperatures and high neutron exposures in fast reactors. The project will develop and test a low temperature coating process of nanostructured vanadium carbide that will provide a benchmark for use in future studies.	Document	FCR&D	FY2013
Doubling the Life of Concrete Structures	University of Idaho	$800,000	Reasearchers will use nanoscale techniques to develop methods for doubling the service life of concrete structures. They will study the effect of temperature load and temperature cycling (freezing and thawing) on the durability of concrete with nanoscale viscosity modifiers. The project will benefit from non-destructive evaluation of concrete performance through electrochemical techniques.	Document	FCR&D	FY2013
Off-Gas Treatment: Evaluation of Nano-structured Sorbents for Selective Removal of Contaminants	University of Idaho	$785,910	Reasearchers will evaluate nanostructured sorbent materials for their effectiveness in removing and immobilizing radionuclides for the off-gas treatment from used nuclear fuel recycling operations. The project aims at achieving near-zero emissions of radionuclides by capturing them from the off-gas of recycling operations, allowing for the development of advanced fuel cycles.	Document	FCR&D	FY2013
Innovative Elution Processes for Recovering Uranium and Transition Metals from Amidoxime-Based Sorbents	University of Idaho	$399,864	Reasearchers will develop a new two-step elution process to achieve total recovery of uranium and effective recycling of the sorbent. The extraction process would selectively remove uranium from the sorbent with little or no damage. The process would then remove transition metals and regenerate the sorbent for repeated use, making uranium extraction from seawater economically viable.	Document	FCR&D	FY2013
Performance of a Steel/Oxide Composite Waste Form for Combined Waste Streams from Advanced Electrochemical Processes over Geologic Time Scales	University of Illinois at Chicago	$700,000	Reasearchers will develop and validate a mechanistically-based corrosion model for cermet-type waste forms, creating a testing protocol and modeling approach for predicting long-term performance. The study will apply novel electrochemical testing and modeling methods to the behavior of metal/oxide phase boundaries to evaluate waste form performance.	Document	FCR&D	FY2013
Enhancement of the Extraction of Uranium from Seawater	University of Maryland, College Park	$400,000	Reasearchers will develop and optimize novel adsorbents for uranium recovery from seawater. The team will use radiation-induced grafting of organic phosphates onto polymers. The experiments will use ocean water, with mechanistic analysis, to provide a solid basis for large-scale demonstration of the performance of the new adsorbents in ocean environments.	Document	FCR&D	FY2013
Improving the Understanding of the Coupled Thermal-Mechanical-Hydrologic Behavior of Consolidating Granular Salt	University of New Mexico	$800,000	Reasearchers will increase the understanding of granular salt seal materials for shafts, drifts and boreholes. By coupling thermal, mechanical and hydrological responses, the study will result in greater confidence in granular salt consolidation as a principal strategy for closure and isolation of long-term waste repositories.	Document	FCR&D	FY2013
Fission Fragment Yield Data in Support of Advanced Reactor Technology	University of New Mexico	$399,816	Reasearchers will produce a highly accurate data set for thermal fission. These precision data are necessary for high-accuracy simulations of nuclear criticality, transmutation rates, radiation effects and heating as well as for nuclear fuel, material accounting and identification needs.	Document	FCR&D	FY2013
Molecular dynamics-based simulations of bulk/interfacial structures and diffusion behaviors in nuclear waste glasses	University of North Texas	$700,000	Reasearchers will generate accurate atomic structural models for use in Monte Carlo simulations of the dissolution of nuclear waste glasses. Large-scale molecular dynamics-based computer simulations will be used to investigate self-diffusion behaviors, interfacial structure, and other structures formed during dissolution of these glasses.	Document	FCR&D	FY2013
U3Si2 Fabrication and Testing for Implementation into the BISON Fuel Performance Code	University of South Carolina	$800,000	Reasearchers will fabricate, test and model a high uranium density, advanced nuclear fuel that operates at a much lower temperature and stores less energy. The work will deliver key research data on creep and grain growth, improving economics, through possible power uprates, and advancing accident tolerant fuels research.	Document	FCR&D	FY2013
Structural Health Monitoring of Nuclear Spent Fuel Storage Facilities	University of South Carolina	$738,618	Reasearchers will develop a nuclear structural health monitoring system based on a sensing technology that monitors material degradation and aging for dry cask storage systems. The low-cost, low-profile sensors will perform on-demand monitoring of the structural integrity of individual components as well as the entire system.	Document	FCR&D	FY2013
ORIGEN-based Nuclear Fuel Depletion Module for Fuel Cycle Assessment	University of Tennessee at Knoxville	$755,181	Reasearchers will develop a flexible reactor analysis module for the CYCLUS fuel cycle simulator based on established tools for reactor fuel depletion and decay. They will use ORIGEN, a mature and experimentally validated code, affording greater flexibility and allowing for accurate evaluations of impacts of both present and future fuel cycle options.	Document	FCR&D	FY2013
Cost and System Analysis of Innovative Fuel Resources Concepts	University of Texas at Austin	$295,960	_This project will develop and test braided polymer fiber adsorbents that surpass the sorption capacity, selectivity and durability of the best existing technology to recover uranium from seawater.	Document	FCR&D	FY2013
Risk Assessment of Structural Integrity of Transportation Casks	University of Utah	$789,296	Reasearchers will assess the loss of structural integrity of transportation casks and fuel cladding after extended storage. This risk assessment will conduct experimental tests and simulations to evaluate the structural performance of fuel, fuel assemblies and cask components when subjected to vibration and impact loads during transport.	Document	FCR&D	FY2013
Market-Based and System-Wide Fuel Cycle Optimization	University of Wisconsin, Madison	$612,731	Reasearchers will create market and economic optimizers to improve calculations for the CYCLUS fuel cycle simulator. The team will leverage existing optimization software frameworks within the simulator to resolve top level policy questions. The optimizations will allow CYCLUS to move beyond static material compositions, providing a holistic view of the fuel cycle system.		FCR&D	FY2013
Optical Fiber Based System for Multiple Thermophysical Properties for Glove Box, Hot Cell and In-Pile Applications	Utah State University	$799,975	Reasearchers will use a small pressure vessel to develop a robust technique for the measurement of multiple thermophysical properties at very high temperatures. The technique will lead to a system design moving toward the eventual measurement of irradiated fuels in a glovebox and/or hot cell with all sensors and electronics outside of the glovebox and/or hot cell.	Document	FCR&D	FY2013
Development of a Nano-Modified Concrete for Next Generation of Storage Systems	Vanderbilt University	$796,268	Reasearchers will use nano-sized and nano-structured particles based on enhanced reactivity to develop a superior concrete for the long-term storage of used nuclear fuel. The project will use state-of-the-art experimental chemical and mechanical characterizations and computation analysis to assess the performance of nano-modified concretes.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Thorium Fuel Cycle Options	Vanderbilt University	$797,995	Reasearchers will develop six fuel cycle data packages for multi-stage, thermal fuel cycles which incorporate thorium. These new fuel cycle data packages will provide the opportunity to examine fuel cycle options beyond those which have traditionally been considered. A thorium fuel cycle database will also be assembled as a basis for thorium literature for future evaluations of the thorium fuel cycle.	Document	FCR&D	FY2013
Enhanced Shielding Performance of HLW Storage Packages via Multi-Component Coatings	Virginia Polytechnic Institute and State University	$796,947	Reasearchers will develop a multi-layer composite that will enhance long-term storage and facilitate safe transport of storage packages. This novel multi-layer, multi-component coating would create an outer shield material that is resistant to the corrosion, radiation, diffusion and thermal cycling processes that affect fuel packages during long term storage.	Document	FCR&D	FY2013
Managing Zirconium Chemistry and Phase Compatibility in Combined Process Separations for Minor Actinide Partitioning	Washington State University	$700,000	Reasearchers will address unique challenges for combining TRUEX and TALSPEAK processes for partitioning of lanthanides and minor actinides. The project will develop improved information on the thermodynamics of fission product zirconium and develop a framework for an organic phase solvation model. Combined process development could streamline separations processes.	Document	FCR&D	FY2013
Advances in the Recovery of Uranium from Seawater: Studies Under Real Ocean Conditions	Woods Hole Oceanographic Institution	$398,882	Reasearchers will provide infrastructure and expertise for marine testing of currently available adsorbents in real ocean conditions. The team will move adsorbent research from the lab to field testing in order to quantify sorptive properties and uranium uptake. The project will provide valuable field data that will show the potential of large scale applications of these technologies.	Document	FCR&D	FY2013
NEUP Project 20-19172: Irradiation of Sensors and Adhesive Couplants for Application in LWR Primary Loop Piping and Components		$497,881	Reasearchers paln to attach ultrasonic transducers to substrates using various adhesive couplants that will be irradiated at elevated temperature to simulate LWR primary loop conditions at the PULSTAR reactor at North Carolina State University. Ultrasonic data will be taken in-situ. Subsequently, the sensors and couplant interfaces will be characterized using the LAMDA facility at ORNL. The results will be used to benefit a parallel EPRI project on online monitoring of cracks in LWR primary loop piping._	Document	R&D NSUF	FY2013
NEUP Project 20-19404: Extension of MSTDB to Provide a High-Quality, Validated Thermochemical Database for Predicting/Simulating Corrosion in Molten Salt Reactor SystemsUniversity of South Carolina		$600,000	Reasearchers will generate a validated, consistent database of initial fuel compositions and potential corrossion products of fluoride and chloride salts, allowing for important phenomena predictions in molten salt reactors to guide confident decisions. The database will be integral to the currently being developed Molten Salt Thermochemical Database (MSTDB), structured to allow use by commercial and open source codes._	Document	NEAMS	FY2013
Lower Length Scale Characterization and Validation of Formation and Stability of Helium Bubbles in Nano-structured Ferritic Alloys under Irradiation	Clemson University	$399,870	Reasearchers will provide a fundamental knowledge about the formation and stability of ultra-fine helium bubbles within 14YWT after neutron/ion irradiation for further design of new advanced structural materials with a characteristic high density nanoparticles feature which can increase the mechanical strength, hardness, irradiation resistance and the operational temperature range of materials.	Document	NEAMS	FY2013
Three-Dimensional Fuel Pin Model Validation by Prediction of Hydrogen Distribution in Cladding and Comparison with Experiment	Pennsylvania State University	$800,000	Reasearchers will validate important three-dimensional aspects of the fuel pin modeling by using specialized numerical modeling techniques coupled with laboratory experiments to validate existing models for predicting fuel performance in light water reactors.	Document	NEAMS	FY2013
Collocation-Based Surrogate Models for Uncertainty Quantification and Validation of Coupled, Multiphysics Fuel Performance Simulation Tools	University of Michigan	$596,835	Reasearchers will provide the necessary high fidelity, coupled, multiphysics fuel performance simulator for computational modeling and develop surrogates which will accelerate and focus the validation of the coupled codes. This will be achieved by utilizing the high fidelity coupled fuel performance, thermal-hydraulics and neutronics codes BISON/STAR-CCM+/MPACT and an innovative collocation-based surrogate methodology.	Document	NEAMS	FY2013
Multi-Resolution In-Situ Testing and Mutliscale Simulation for Creep Damage Fatigue Damage Analysis of Alloy 617	Arizona State University	$800,000	This project will develop novel testing and experimentally validated prediction methodologies for micro-structural damage mechanisms of structural materials for advanced reactor systems. The investigations will focus on the characterization and testing of specific metal alloys, but the proposed testing and life-prediction methodologies are applicable to other structural materials as well.	Document	RCRD&D	FY2013
Novel High Temperature and Radiation Resistant Infrared Glasses and Optical Fibers for Sensing in Advanced Small Modular Reactors	Clemson University	$800,000	Clemson University, in partnership with the Iowa State University and the Pacific Northwest National Laboratory, will develop novel optical materials with improved heat and radiation exposure resistance in order to enable in-vessel fiber optic sensing for advanced Small Modular Reactors.	Document	RCRD&D	FY2013
Validation Data Acquisition in HTTF during PCC Events	George Washington University	$800,000	Reasearchers at the George Washington University and Oregon State University will collaborate with NASA Langley Research Center to measure flow velocities in a high temperature test facility. This work supports the development of very-high temperature reactors with passive safety systems.	Document	RCRD&D	FY2013
Advanced High Temperature Inspection Capabilities for Small Modular Reactors	Iowa State University	$790,822	The objective of this project is to develop non-destructive evaluation techniques for advanced small modular reactors. The research will provide key enabling inspection technologies needed to support the design and the reactor component performance validation process for advanced small modular reactors.	Document	RCRD&D	FY2013
Experimental and Computational Investigations of Plenum-to-Plenum Heat Transfer under Natural Circulation in a Prismatic Very High Temperature Reactor	Missouri University of Science and Technology	$799,999	Reasearchers will perform experimental and computational investigations to study heat transfer and natural circulation phenomena in very-high temperature reactors. The study will assist in the ability to predict and analyze passive safety systems.	Document	RCRD&D	FY2013
New Mechanistic Models of Creep-Fatigue Crack Growth Interactions for Advanced High Temperature Reactor Components	Oregon State University	$790,790	Reasearchers will create and validate a robust, multi-scale, numerical model to predict material degradation in nickel-based reactor alloys. If successful, this project will provide better numerical tools for reactor designers and greatly improve their capability to design against material failures for reactor alloys in the long term.	Document	RCRD&D	FY2013
Self-Powered Wireless Dual-mode Langasite Sensor for Pressure/Temperature Monitoring of Nuclear Reactors	State University of New York, Stony Brook	$800,000	This research will develop a novel self-powered wireless hybrid sensor that can accurately monitor both pressure and temperature using a single device without requiring external electricity, even in extreme harsh environments.	Document	RCRD&D	FY2013
Compact Heat Exchanger Design and Testing for Advanced Nuclear Reactors and Advanced Power Cycles	The Ohio State University	$800,000	The goal of this project is to investigate optimal heat exchanger designs for advanced reactors. The research will study the optimization of printed circuit heat exchangers for specific fluids under a variety of conditions as well as perform numerical modeling. Experiments will focus on thermal performance and heat stress during extreme conditions.	Document	RCRD&D	FY2013
Fundamental Understanding of Creep-Fatigue Interactions in 9Cr-1MoV Steel Welds	The Ohio State University	$798,000	This project will advance the state of knowledge and fundamental understanding of deforming materials and welds under loading conditions. Specifically, new integrated testing procedures will be evaluated and applied for conditions that are most detrimental to material stability leading to improved predictions of life expectancy for reactor steels and welds.	Document	RCRD&D	FY2013
Advanced Mechanistic 3D Spatial Modeling and Analysis Methods to Accurately Represent Nuclear Facility External Event Scenarios	The Ohio State University	$800,000	Reasearchers will develop three-dimensional characterization uncertainty analysis for commercial power plants. The project will involve combining experts from the fields of seismic structural modeling and advanced methods of risk assessment. This effort is expected to result in next generation tools that can be used for assessment of seismic risks.	Document	RCRD&D	FY2013
Tritium Mitigation/Control for Advanced Reactor Systems	The Ohio State University	$400,000	Reasearchers will develop a fluoride salt cooled high-temperature reactor featuring a specialized system to control tritium production. If successful, this will result in a significant reduction in size and cost in comparison to other reactor designs.	Document	RCRD&D	FY2013
A Pebble-Bed Breed and Burn Reactor	University of California, Berkeley	$400,000	Reasearchers will assess the feasibility of designing a type of metal cooled reactor able to establish and maintain operation when fueled with depleted uranium. If successful, this reactor will offer at least a 30-fold increase in the uranium ore utilization versus that achieved in contemporary light water reactors without the need for fuel reprocessing and recycling.	Document	RCRD&D	FY2013
Investigation of Thermal Aging Effects on the Evolution of Microstructure and Mechanical Properties of Cast Duplex Stainless Steels	University of Maryland, College Park	$799,966	This research will provide a better understanding of the microstructural evolution and simultaneous change in mechanical response during aging. The results of the research will provide data that can be used to estimate degraded mechanical properties for an 80-year service life of light water reactors.	Document	RCRD&D	FY2013
Model validation using CFD-grade experimental database for NGNP Reactor Cavity Cooling Systems with water and air	University of Michigan	$799,348	Reasearchers will use advanced innovative instrumentation to build a high-resolution experimental database and to use the novel experimental data to assess and further develop the predictive capabilities of computer codes for thermal hydraulics and computational fluid dynamics. The improved models developed by this project will also have the direct benefit of improving the predictive capability of the passive systems of third generation light water reactors and small modular reactor systems.	Document	RCRD&D	FY2013
Long-Term Prediction of Emissivity of Structural Material for High Temperature Reactor Systems	University of Missouri	$799,117	Reasearchers will study specific types of emissivity driven cooling from a variety of materials that are relevant to nuclear reactors. The research will provide a basis for numerical modeling to support reactor development.	Document	RCRD&D	FY2013
Advanced I&C for Fault-Tolerant Supervisory Control of Small Modular Reactors	University of Pittsburgh	$800,000	The purpose of this research is to develop advanced instrumentation and control techniques for supervisory control of advanced small modular reactors. This research supports the operational goals of small modular reactor concepts through the development of improved oversight and surveillance techniques.	Document	RCRD&D	FY2013
Corrosion of Structural Materials for Advanced Supercritical Carbon-Dioxide Brayton Cycle	University of Wisconsin-Madison	$798,672	Reasearchers will study a variety of materials for corrosion resistance under conditions that improve power conversion. In addition to studying the corrosion resistance of the materials, researchers will study the effect of additives to mitigate corrosion. Development of corrosion theories and modeling aimed at prediction of long-term corrosion will be the underlying theme throughout the project.	Document	RCRD&D	FY2013
Component and Technology Development for Advanced Liquid Metal Reactors	University of Wisconsin-Madison	$798,920	In support of liquid metal cooled reactors, the University of Wisconsin, Madison will evaluate advanced alloys and ceramics that come in contact with liquid metals. Additionally, a robust oxygen sensor and for use in liquid metals will be developed in order to better evaluate corrosion profiles in support of diagnostic testing.	Document	RCRD&D	FY2013
A New Paradigm for Understanding Multi-phase Ceramic Waste Form Performance	Clemson University	$800,000	Researchers will use advanced characterization tools to develop 3-D microstructural data that can be incorporated into computer-based simulations in order to predict the performance of waste forms. Materials system modeling will incorporate elemental release and the interconnected microstructural network of phases to better understand performance and degradation, which will accelerate waste form acceptance in repository settings.	Document	FCR&D	FY2014
Controlling Hexavalent Americium: A Centerpiece to a Compact Nuclear Fuel Cycle	Colorado School of Mines	$800,000	Researchers will develop and exploit the fundamental chemistry of Americium to enable an industrially viable means to co-recover the major and minor actinide elements from used nuclear fuel. The results would be a significant step forward in the development of aqueous separations approaches designed to recover the U-Am actinides based on the availability of the hexavalent oxidation state.	Document	FCR&D	FY2014
Zeolite Membranes for Krypton/Xenon Separation from Spent Nuclear Fuel Reprocessing Off-Gas	Georgia Institute of Technology	$400,000	Researchers will develop a high-performance, lower-cost zeolitic membrane process for Kr/Xe separations during spent nuclear fuel processing. Current separation methods are not considered economical and a membrane process would have relatively lower cost, equipment size, and ambient operating temperature. The process would form a sound basis for further development of this transformative separation technology for the nuclear fuel cycle.	Document	FCR&D	FY2014
Optimizing Polymer-Grafted Amidoxime-based Adsorbents for Uranium Uptake from Seawater	Georgia Institute of Technology	$399,999	Researchers will work to increase the adsorbent capacity and selectivity toward uranium by optimizing the adsorbent morphology, synthesis variables, and conditioning parameters and by investigating the rate-limiting variables through transport and reaction modeling. A novel adsorption/partition concept that has the potential to substantially increase the adsorbent capacity will be tested, making uranium from seawater extraction more economically viable.	Document	FCR&D	FY2014
Extraction of Uranium from Seawater: Design and Testing of a Symbiotic System	Massachusetts Institute of Technology	$400,000	Researchers will develop a seawater uranium extraction system that will work symbiotically with an offshore windmill by utilizing the structure, mooring and power of the windmill, while increasing the energy harvested by the installation. Uranium will be extracted by an adsorbent polymer belt, which will be cycled through the seawater and an elution plant located at the base of the windmill tower. Increasing the frequency of harvesting could overcome current economic barriers to seawater uranium extraction.	Document	FCR&D	FY2014
Imaging a Dry Storage Cask with Cosmic Ray Muons	Oregon State University	$799,871	Researchers will develop an imaging system to monitor the content of a dry storage cask with cosmic ray muons. A very large amount of plutonium under nuclear safeguards is contained in used fuel assemblies stored in dry storage casks. Muon imaging will allow a cost effective and reliable way to evaluate dry storage cask content and integrity before transport.	Document	FCR&D	FY2014
Apatite and sodalite based glass-bonded waste forms for immobilization of 129I and mixed halide radioactive wastes	Rutgers University	$800,000	Researchers will develop advanced and chemically durable waste forms for immobilizing 129I (aqueous based reprocessing of fuel) and mixed-halide wastes (molten-salt processing of fuel) by low temperature synthesis. Halide-containing sodalite and calcium phosphate-based apatite minerals will be synthesized, consolidated and tested for chemical durability. The project will provide needed baseline data for the development of advanced waste forms for immobilization of iodine and mixed-halide wastes.	Document	FCR&D	FY2014
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$350,000	Researchers will develop modeling tools supported by experiments for off-gas capture from future nuclear-fuel recycling facilities. Target species include tritium, iodine, krypton, and xenon. The models are intended to provide path forward recommendations to develop off-gas treatment adsorption processes. The project will contribute to the evaluation of options for environmentally acceptable recycle systems.	Document	FCR&D	FY2014
Development of high performance ODS alloys	Texas A&M University	$800,000	Researchers will study swelling, radiation hardening and changes in mechanical properties of ODS alloys to develop two sets of advanced ODS alloys. Two sets of first-round candidate alloys that have already undergone extensive development and testing will evaluate irradiation performance. The study will meet the need for high strength, radiation-tolerant cladding and core components that have enhanced resistance to void swelling.	Document	FCR&D	FY2014
Rare Earth Electrochemical Property Measurements and Phase Diagram Development in a Complex Molten Salt Mixture for Molten Salt Recycle	The Ohio State University	$800,000	Researchers will investigate rare earth (RE) properties in complex molten salt mixtures. In a molten salt recycle approach, the RE drawdown by electrolysis is a key step in which REs are separated from salt containing other fission products. Investigation of RE electrolysis must consider the electrochemical properties of the REs. We propose to conduct studies of detailed experiments and corresponding models to provide the physical properties and phase diagrams required to predict the performance of RE drawdown for processing complex molten salts.	Document	FCR&D	FY2014
Studies of Lanthanide Transport in Metallic Nuclear Fuels	The Ohio State University	$800,000	Researchers will study the redistribution of lanthanides and migration of lanthanides to the fuel surface. The mechanisms of lanthanide transport in metallic fuel based on the novel discovery of a Ôliquid-likeÕ transport mechanism will be studied analytically and experimentally. The project will develop a fundamental understanding of lanthanide fission product migration and redistribution in advanced metallic nuclear fuels, and theory and data to mitigate fuel-cladding chemical interactions.	Document	FCR&D	FY2014
Computational and Experimental Studies of Microstructure-Scale Porosity in Metallic Fuels for Improved Gas Swelling Behavior	University of Arkansas	$796,823	Researchers will study the microstructure of metallic uranium alloy fuels, and their resistance to densification, to minimize in-pile irradiation swelling through bimodal pore size distribution. The project will develop a predictive approach to design metallic fuel microstructures for optimal swelling resistance and fission gas retention.	Document	FCR&D	FY2014
Improved Hybrid Modeling of Spent Fuel Storage Facilities	University of California, Berkeley	$645,393	Researchers will develop a variance reduction method for computational transport that will improve the ability to design and operate monitoring systems for interim used fuel installations through enhanced modeling and simulation. This new tool will demonstrate that modeling calculations can be done more accurately in less time than with current tools and will perform studies characterizing how changes in material, cask configurations, and number of casks could impact monitoring systems.	Document	FCR&D	FY2014
Selective ligands for uranyl via combinatorial peptoid libraries: A synthetic, structural, thermodynamic and computational study	University of California, Berkeley	$400,000	Researchers will study how donor ligands bind to the uranyl ion, UO22+, with the longer-term goal of using this information to tackle selective recognition of uranyl in aqueous solution. The study will impact underlying approaches to controlling the behavior of uranium in these systems. The actinide separation technology could be used in several areas including uranium extraction from seawater, nuclear waste remediation and nuclear materials.	Document	FCR&D	FY2014
Combining Experiments and Simulations of Extraction Kinetics and Thermodynamics in Advanced Separation Processes for Used Nuclear Fuel	University of California, Irvine	$799,938	Researchers will study how the kinetics and thermodynamics of metal ion extraction in advanced separation processes for used nuclear fuel can be described by molecular dynamic (MD) simulations and how the simulations can be validated by experimental data. The project would have broad impacts on several separations processes including advanced TALSPEAK, ALSEP and GANEX by increasing the confidence and accuracy of computer modeling of metal ion extraction._	Document	FCR&D	FY2014
Effect of Metallic Li on the Behavior of Metals in Molten Salts	University of Nevada, Reno	$458,250	Researchers will identify the effect of metallic lithium on materials that are used in molten salt recycling. The study will try to understand how the presence of Li(0) in molten salts affects the degradation of alloys. Studying these changes will help accurately predict container material behavior and longevity.	Document	FCR&D	FY2014
Assessment of Corrosion Resistance of Promising Accident Tolerant Fuel Cladding under Reactor Conditions	University of Notre Dame	$800,000	Researchers will assess the corrosion behavior of accident tolerant fuel candidate iron-based alloys under normal LWR operating conditions consisting of high temperature, relevant water chemistry and irradiation. The assessment will produce data about possible irradiation-accelerated corrosion rates of iron-based alloys, and the mechanisms by which such corrosion rates are accelerated. The project will advance the selection of appropriate replacements for Zircaloy cladding.	Document	FCR&D	FY2014
Functionalized Porous Organic Polymers as Uranium Nano-Traps for Efficient Recovery of Uranium from Seawaterr	University of South Florida	$399,000	Researchers will develop functionalized porous organic polymers, or Ônano-trapsÕ for extraction of uranium from seawater. This technique allows for increased surface area and custom-designed pore size and chemistry to fit specific parameters. The adsorbent materials have high efficiency and effectiveness for uranium recovery from seawater, providing a potential supply for nuclear fuel.	Document	FCR&D	FY2014
Enhanced Accident-Tolerant Fuel Performance and Reliability for Aggressive iPWR/SMR Operation	University of Tennessee	$799,967	To develop a process that evaluates operational and safety performance of reactor-and-fuel combinations by integrating whole-core 3D neutronics with MOOSE/BISON fuel performance assessments via explicit time and space dependent fuel rod operational power histories. The project will be valuable in analyzing and evaluating accident tolerant fuel concepts and furthering the understanding of reactor physics and fuel performance aspects of key accident tolerant fuel concepts.	Document	FCR&D	FY2014
Nuclear Technology R&D Strategies in an Era of Energy Price Uncertainty	University of Texas, Austin	$799,112	Researchers will identify nuclear technology options that are competitive over a wide range of plausible future business environments. No single nuclear technology or business practice will be the best choice across all or even most future conditions. The study will focus on hybrid nuclear-fossil technologies, energy storage and conversion, which will result in an identification of nuclear strategies that can succeed under future market conditions.	Document	FCR&D	FY2014
Development and Optimization of Voltammetric Methods for Real Time Analysis of Electrorefiner Salt with High Concentrations of Actinides and Fission Products	University of Utah	$621,612	Researchers will develop an advanced voltammetry method to pursue the objective of real time monitoring of actinide concentrations in electrorefiner salt. This will include experimental measurement of key parameters such as activity coefficients and exchange current density. It will also involve simulation of voltammetry processes based on first principles. The project will allow for real time measurements that could support the commercialization of pyroprocessing.	Document	FCR&D	FY2014
Development of Self-Healing Zirconium-Silicide Coatings for Improved Performance of Zirconium-Alloy Fuel Cladding	University of Wisconsin, Madison	$798,621	Researchers will study the deposition of self-healing zirconium-silicide coatings on zirconium-alloy fuel cladding material to improve corrosion resistance under normal and accident conditions. Under these conditions, Zr-Si coating evolves into a highly protective functionally-graded multilayered system. The study will lead to improved performance of zirconium-alloy fuels._	Document	FCR&D	FY2014
Thermal Conductivity in Metallic Fuels	Virginia Polytechnic Institute and State University	$799,837	Researchers will calculate the thermal conductivity of metallic uranium and neptunium alloys, including the effects of noble gasses, using density functional theory. The experiments will validate the calculated effective thermal conductivity using the MARMOT code and by helping determine DFT simulation parameters. The study works to improve fuel lifetime by understanding its thermal behavior.	Document	FCR&D	FY2014
SiC-ODS Alloy Gradient Nanocomposites as Novel Cladding Materials	Virginia Polytechnic Institute and State University	$799,998	Researchers will combine nuclear nanomaterial design, processing, testing, and characterization efforts to develop revolutionary materials that can withstand neutron irradiation for long period of time using nanostructured SiC and oxide dispersion strengthened steel. The ultimate objective is to offer new cladding materials with increased corrosion resistance, strength, and creep resistance in both steady state and accident conditions.	Document	FCR&D	FY2014
Experimental Breeder Reactor II Benchmark Evaluation	Idaho State University	$400,000	Researchers will develop a benchmark evaluation of the Experimental Breeder Reactor II (EBR-II). During nearly 30 years of operation numerous experiments were conducted at EBR-II. The most significant of these experiments were conducted in 1986 demonstrating inherent safety features in loss of flow without reactor scram and loss of heat sink without reactor scram. Benchmark evaluation will be valuable for the reactor design efforts in the United States and South Korea.	Document	MSNE	FY2014
Integral full core multi-physics PWR benchmark with measured data	Massachusetts Institute of Technology	$400,000	Researchers will introduce BEAVRS, a new multi-cycle full-core Pressurized Water Reactor (PWR) depletion benchmark based on two operational cycles of a commercial nuclear power plant. This project aims at addressing the uncertainty quantification of the measured data and on making this benchmark a true non-proprietary international benchmark for the validation of high-fidelity multi-physics computational tools.	Document	MSNE	FY2014
Benchmark Evaluation of PROTEUS Gas-Cooled Reactor Experiments	University of Florida	$400,000	Researchers will create International Reactor Physics Experiment Evaluation Project (IRPhEP) benchmarks using data from 1970s experiments of the neutronics of gas-cooled fast reactor (GCFR) designs investigated in the PROTEUS reactor. The GCFR-PROTEUS experiments fill a gap in current integral benchmark data. These experiments can provide validation of computational models and nuclear data for next generation reactors.	Document	MSNE	FY2014
An Investigation To Establish Multiphysical Property Dataset Of Nuclear Materials Based On In-Situ Observations And Measurements	Purdue University	$800,000	Researchers will create an in-situ measurement based experimental approach to develop experimental validation dataset for NEAMS based code validation. Particular emphasis is on supplying data set for multiphysics simulations in extreme conditions as a function of material microstructure.	Document	NEAMS	FY2014
Experimental Validation of UO2 Microstructural Evolutions for NEAMS tool MARMOT	University of Florida	$798,000	Researchers will experimentally validate MARMOT for predicting the microstructural evolutions of UO2 oxide fuel under the driving forces of high temperatures and large temperature gradient in reactors. By performing the experiments and simulations simultaneously using precisely defined initial conditions, the experiment data will provide direct benchmarking of the MARMOT code.	Document	NEAMS	FY2014
High-resolution time-resolved experiments on mixing and entrainment of buoyant jets in stratified environments	University of Michigan	$799,983	Researchers will study high spatial and time-resolution experimental data of the fluid dynamics phenomena of flow jets interacting with a stratified layer. The issue plays an important role in the safety of several reactor designs, including sodium-cooled reactors. The data addresses the NEAMS needs for the validation of high fidelity computational fluid dynamics methodologies.	Document	NEAMS	FY2014
Fundamental study of key issues related to advanced S-CO2 Brayton Cycle: prototypic HX development and Cavitation	Georgia Institute of Technology	$799,000	Researchers will study scientific and operational issues pertinent to compact heat exchanger systems and turbo-machinery. The project will work to resolve issues with the fabrication of diffusion bonded compact heat exchangers, alternate heat exchange technology for recuperators, and resolution of issues with cavitation and fluid instabilities.	Document	RCRD&D	FY2014
Advanced Models for Nondestructive Evaluation of Aging Nuclear Power Plant Cables	Iowa State University	$787,291	Researchers will develop advanced models that relate environmentally induced microstructural and chemical changes in cable insulation polymers to their macroscopic electrical parameters. These parameters will be measured and modeled over a wide range of the electromagnetic spectrum, covering several potential nondestructive evaluation techniques, enabling identification of the most sensitive techniques for future development.	Document	RCRD&D	FY2014
Development of Novel Functionally Graded Transition Joints for Improving the Creep Strength of Dissimilar Metal Welds in Nuclear Applications	Lehigh University	$800,000	Researchers will develop graded transition joints and improved creep life models for increasing the life of dissimilar metal welds (DMWs) in nuclear reactors. The research represents the first application of functionally graded material concepts for solving the problem of DMW failures through an integrated approach of additive manufacturing, modeling, microstructural characterization, and advanced strain-sensing techniques.	Document	RCRD&D	FY2014
Feasibility Assessment of a Micro Modular Reactor (MMR)	North Carolina State University	$400,000	Researchers will develop an innovative compact reactor concept that integrates power production, power conversion and electricity generation in a single unit: the Micro Modular Reactor (MMR). It is designed to be absolutely melt-down proof (MDP) under all circumstances including complete loss of coolant scenarios with no possible release of radioactive material, to have a cycle length of greater than 10 years, and to be highly proliferation resistant.	Document	RCRD&D	FY2014
Scaling Studies for Advanced Gas Reactor Concepts	Oregon State University	$681,834	Researchers will expand the utilization of the Oregon State University High Temperature Test Facility (HTTF) to validate a broader range of advanced high temperature reactors and events. The facility will be revised to add a detailed scaling analysis of additional gas reactor concepts including advanced gas-cooled, molten salt, and sodium cooled reactors.	Document	RCRD&D	FY2014
Fluid Stratification Separate Effects Analysis, Testing and Benchmarking	Oregon State University	$800,000	Researchers will study fluid stratification in high temperature gas reactors. Coolant stratification is the result of incomplete mixing of one or more fluids, leading to a density gradient, which may or may not dissipate under diffusive or convective effects. This combined analytical and experimental project seeks to investigate stratification driven by diffusive and convective mechanisms and is expected to yield insight into this phenomenon.	Document	RCRD&D	FY2014
Probabilistic Economic Valuation of Safety Margin Management Analysis	Oregon State University	$795,364	Researchers will use RAVEN and develop a companion software package to facilitate economic analysis of safety margins. The project is a proof of concept that will use techniques to examine the cost of improving safety margins vs. the risk of accidents from not improving safety margins. This analysis can be used to evaluate the economic viability of various plant upgrades.	Document	RCRD&D	FY2014
Novel Dissimilar Joints Between Alloy 800H and 2.25%Cr and 1%Mo Steel	Pennsylvania State University	$800,000	Researchers will fabricate and test dissimilar metal joints between a nickel base alloy and a steel with gradual variations of chemical composition, microstructure and properties in a manner that reduces abrupt thermal expansion mismatch and the resulting residual stresses. Data on structure and properties will serve as valuable inputs for the initiation of an ASME code case.	Document	RCRD&D	FY2014
Multi-Phase Model Development to Assess RCIC System Capabilities under Severe Accident Conditions	Texas A&M University	$564,246	Researchers will develop physics-based models of the Reactor Core Isolation Cooling (RCIC) System and incorporating them into a multi-phase code for validation. The project will tackle the current major challenges in RCIC System analysis and enable evaluation of two-phase thermodynamic aspects.	Document	RCRD&D	FY2014
Experimental Investigation and CFD Analysis of Steam Ingress Accidents in HTGRs	The Ohio State University	$800,000	Researchers will study the steam ingress scenario for HTGRs. The study will investigate thermal-hydraulic behavior and graphite oxidation of stream ingress phenomena to validate predictive CFD models. This work will resolve concerns about possible steam generator tube ruptures in a HTGR He-Steam Rankine cycle.	Document	RCRD&D	FY2014
Coiled Tube Gas Heaters For Nuclear Gas-Brayton Power Conversion	University of California, Berkeley	$800,000	Researchers will develop heat exchangers for Brayton-cycle power conversion in reactors using sodium, NaK, or salt as intermediate coolants. The proposed coiled tube gas heaters (CTGHs) are expected to have excellent power density, thermal shock/creep, in-service inspection, and reparability characteristics.	Document	RCRD&D	FY2014
Fundamental Studies of Irradiation-Induced Modifications in Microstructural Evolution and Mechanical Properties of Advanced Alloys	University of Illinois, Urbana-Champaign	$800,000	Researchers will develop and test a mechanism for predicting neutron irradiation performance for optimized Grade 92 and Alloy 709 for applications in advanced reactor systems. The work will employ ion irradiations and available information from neutron irradiations of related alloys to develop a basis for predicting the neutron irradiation performance of the optimized alloys.	Document	RCRD&D	FY2014
Integrated Computational and Experimental Study of Radiation Damage Effects in Grade 92 Steel and Alloy 709	University of Tennessee	$800,000	Researchers will develop a mechanistic understanding and predictive models of irradiation-induced microstructural evolution and resulting mechanical properties in optimized ferritic-martensitic Grade 92 steel and austenitic alloy 709 using multiscale simulations coupled with rigorous experimental validation. The project will provide insights into the correlation between ion irradiation and fast neutron damage.	Document	RCRD&D	FY2014
Meta-Level Design Guidance and Operator Performance Measures for Hybrid Control Rooms	Vanderbilt University	$799,869	Researchers will apply human factors engineering methods and relevant expertise from non-nuclear high-risk high-consequence domains toward the measurement of operator performance in analog, digital, and hybrid main control rooms. Performance measures will be developed for evaluating the situation awareness and decision-making proficiencies to support the transition to digital or hybrid control room displays.	Document	RCRD&D	FY2014

FY 2014 Research and Development Awards

The Department of Energy is awarding $30 million in support of the Nuclear Energy University Programs for 44 nuclear energy research and development projects focused on developing innovative solutions in the following fields: Fuel Cycle Technologies; Reactor Concepts Research; Development & Demonstration; and Nuclear Energy Advanced Modeling & Simulation.

These projects, selected for negotiation of award, are led by 30 American universities and colleges in 29 states and the District of Columbia. Other universities, industry leaders and National Laboratories will serve as collaborators and research partners.

A complete list of R&D projects with their associated abstracts is available below.

Title	Institution	Estimated Funding*	Project Description	Abstract	Project Type	Fiscal Year
Neutron Damage and MAX Phase Ternary Compounds	Drexel University			Document	IIR	FY2009
Atomistic Calculations of the Effect of Minor Actinides on Thermodynamic and Kinetic Properties of UO2+x	Georgia Institute of Technology			Document	IIR	FY2009
Maximum Fuel Utilization in Fast Reactors without Chemical Reprocessing	University of California, Berkeley			Document	IIR	FY2009
Developing a High Thermal Conductivity Fuel with Silicon Carbide Additives	University of Florida			Document	IIR	FY2009
Fabrication of Tungsten-Rhenium Cladding Materials via Spark Plasma Sintering for Ultra High Temperature Reactor Applications	University of Idaho			Document	IIR	FY2009
Ionic Liquid and Supercritical Fluid Hyphenated Techniques for Dissolution and Separation of Lanthanides, Actinides, and Fission Products	University of Idaho			Document	IIR	FY2009
Improved Fission Neutron Data Base for Active Interrogation of Actinides	University of Michigan			Document	IIR	FY2009
Utilization of Methacrylates and Polymer Matrices for the Synthesis of Ion Specific Resins	University of Nevada, Las Vegas			Document	IIR	FY2009
Improved LWR Cladding Performance by EPD Surface Modification Technique	University of Wisconsin, Madison			Document	IIR	FY2009
Advanced Models of LWR Pressure Vessel Embrittlement for Low Flux-High Fluence Conditions	University of California, Santa Barbara			Document	LWRS	FY2009
Irradiation Creep in Graphite	Boise State University			Document	NGNP	FY2009
Modeling the Stress Strain Relationships and Predicting Failure Probabilities For Graphite Core Components	Cleveland State University			Document	NGNP	FY2009
TRISO-Coated Fuel Durability Under Extreme Conditions	Colorado School of Mines			Document	NGNP	FY2009
An Innovative and Advanced Coupled Neutron Transport and Thermal Hydraulic Method (Tool) for the Design, Analysis and Optimization of VHTR/NGNP Prismatic Reactors	Georgia Institute of Technology			Document	NGNP	FY2009
Removal of 14C from Irradiated Graphite for Graphite Recycle and Waste Volume Reduction	Idaho State University			Document	NGNP	FY2009
Millimeter-Wave Thermal Analysis Development and Application to Gen IV Reactor Materials	Massachusetts Institute of Technology			Document	NGNP	FY2009
Accurate Development of Thermal Neutron Scattering Cross Section Libraries	North Carolina State University			Document	NGNP	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
Understanding Creep Mechanisms in Graphite with Experiments, Multiscale Simulations, and Modeling	North Carolina State University			Document	NGNP	FY2009
Simulations of the Thermodynamic and Diffusion Properties of Actinide Oxide Fuel Materials	University of Michigan			Document	AFCI	FY2009
Verification & Validation of High-Order Short-Characteristics-Based Deterministic Transport Methodology on Unstructured Grids	North Carolina State University			Document	NGNP	FY2009
Adsorptive Separation and Sequestration of Krypton, I and C14 on Diamond Nanoparticles	University of Missouri, Columbia			Document	AFCI	FY2009
Microscale Heat Conduction Models and Doppler Feedback	North Carolina State University			Document	NGNP	FY2009
Fundamental Understanding of Ambient and High-Temperature Plasticity Phenomena in Structural Materials in Advanced Reactors	Georgia Institute of Technology			Document	AFCI	FY2009
Development of Alternative Technetium Waste Forms	University of Nevada, Las Vegas			Document	AFCI	FY2009
Optimizing Neutron Thermal Scattering Effects in Very High Temperature Reactors	North Carolina State University			Document	NGNP	FY2009
Advanced Elastic/Inelastic Nuclear Data Development Project	Idaho State University			Document	AFCI	FY2009
Heterogeneous Recycling in Fast Reactors	Massachusetts Institute of Technology			Document	AFCI	FY2009
Quantification of UV-Visible and Laser Spectroscopic Techniques for Materials Accountability and Process Control	University of Nevada, Las Vegas			Document	AFCI	FY2009
Multiaxial Creep-Fatigue and CreepRatcheting Failures of Grade 91 and Haynes 230 Alloys Toward Addressing Design Issues of Gen IV Nuclear Power Plants	North Carolina State University			Document	NGNP	FY2009
Thermodynamic Development of Corrosion Rate Modeling in Iron Phosphate Glasses	Missouri University of Science and Technology			Document	AFCI	FY2009
Development of Subspace-Based Hybrid Monte Carlo-Deterministic Algorithms for Reactor Physics Calculations	North Carolina State University			Document	AFCI	FY2009
High-Fidelity Space-Time Adaptive Multiphysics Simulations in Nuclear Engineering	University of Nevada, Reno			Document	AFCI	FY2009
Improvements to Nuclear Data and Its Uncertainties by Theoretical Modeling	Rensselaer Polytechnic Institute			Document	AFCI	FY2009
Investigation of Countercurrent Helium-air Flows in Air-ingress Accidents for VHTRs	Ohio State University			Document	NGNP	FY2009
Sharp Interface Tracking in Rotating Microflows of Solvent Extraction	State University of New York at Stony Brook			Document	AFCI	FY2009
Bulk Nanostructured FCC Steels with Enhanced Radiation Tolerance	Texas A&M University			Document	AFCI	FY2009
Simulations of Failure via Three-Dimensional Cracking in Fuel Cladding for Advanced Nuclear Fuels	University of Texas, Dallas			Document	AFCI	FY2009
Testing of Performance of Optical Fibers Under Irradiation in Intense Radiation Fields, When Subjected to Very High Temperatures	Ohio State University			Document	NGNP	FY2009
Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels	Texas A&M University			Document	AFCI	FY2009
SiC Schottky Diode Detectors for Measurement of Actinide Concentrations from Alpha Activities in Molten Salt Electrolyte	The Ohio State University			Document	AFCI	FY2009
Computational Design of Advanced Nuclear Fuels	University of California, Davis			Document	AFCI	FY2009
Advanced Mesh-Enabled Monte Carlo Capability for Multi-Physics Reactor Analysis	University of Wisconsin, Madison			Document	AFCI	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
A Distributed Fiber Optic Sensor Network for Online 3-D Temperature and Neutron Fluence Mapping in a VHTR Environment	Texas A&M University			Document	NGNP	FY2009
Ab Initio Enhanced Calphad Modeling of Actinide Rich Nuclear Fuels	University of Wisconsin, Madison			Document	AFCI	FY2009
Investigation on the Core Bypass Flow in a Very High Temperature Reactor	Texas A&M University			Document	NGNP	FY2009
Development of Diffusion Barrier Coatings and Deposition Technologies for Mitigating Fuel Cladding Chemical Interactions (FCCI)	University of Wisconsin, Madison			Document	AFCI	FY2009
CFD Model Development and Validation for High Temperature Gas Cooled Reactor Cavity Cooling System (RCCS) Applications	Texas A&M University			Document	NGNP	FY2009
Thermal Properties of LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin, Madison			Document	AFCI	FY2009
Study of Air ingress across the duct during the accident conditions	Texas A&M University			Document	NGNP	FY2009
Verification of the CENTRM Module for Adaptation of the SCALE Code to NGNP Prismatic and PBR Core Designs	University of Arizona			Document	NGNP	FY2009
Integral and Separate Effects Tests for Thermal Hydraulics Code Validation for Liquid-Salt Cooled Nuclear Reactors	University of California, Berkeley			Document	NGNP	FY2009
Mechanisms Governing the Creep Behavior of High Temperature Alloys for Generation IV Nuclear Energy Systems	University of Cincinnati			Document	NGNP	FY2009
ALD Produced B2O3, Al2O3 and TiO2 Coatings on Gd2O3 Burnable Poison Nanoparticles	University of Colorado, Boulder			Document	NGNP	FY2009
Experimental Study and Computational Simulations of Key Pebble Bed Thermomechanics Issues for Design and Safety	University of Idaho			Document	NGNP	FY2009
Prediction and Monitoring Systems of Creep-Fracture Behavior of 9Cr-1Mo Steels for Reactor Pressure Vessels	University of Idaho			Document	NGNP	FY2009
Understanding Fundamental Material Degradation Processes in High Temperature Aggressive Chemomechanical Environments	University of Illinois, Urbana-Champaign			Document	NGNP	FY2009
Multi-Scale Multi-physics Methods Development for the Calculation of Hot-Spots in the NGNP	University of Michigan			Document	NGNP	FY2009
Corrosion and Creep of Candidate Alloys in High Temperature Helium and Steam Environments for the NGNP	University of Michigan			Document	NGNP	FY2009
Creation of a Full-Core HTR Benchmark with the Fort St. Vrain Initial Core and Validation of the DHF Method with Helios for NGNP Configurations	University of Michigan			Document	NGNP	FY2009
Fission Product Sorptivity in Graphite	University of Missouri, Columbia			Document	NGNP	FY2009
Identifying and Understanding Environment-Induced Crack Propagation Behavior in Ni-Based Superalloy INCONEL 617	University of Nevada, Las Vegas			Document	NGNP	FY2009
Graphite Oxidation Simulation in HTR Accident Conditions	University of New Mexico			Document	NGNP	FY2009
Non Destructive Thermal Analysis and In Situ Investigation of Creep Mechanism of Graphite and Ceramic Composites using Phase-sensitive THz Imaging & Nonlinear Resonant Ultrasonic Spectroscopy	University of Rochester			Document	NGNP	FY2009
Tritium Sequestration in Gen IV NGNP Gas Stream via Proton Conducting Ceramic Pumps	University of South Carolina			Document	NGNP	FY2009
Materials, Turbomachinery and Heat Exchangers for Supercritical CO2 Systems	University of Wisconsin, Madison			Document	NGNP	FY2009
Experimental Studies of NGNP Reactor Cavity Cooling System with Water	University of Wisconsin, Madison			Document	NGNP	FY2009
Assessment of Embrittlement of VHTR Structural Alloys in Impure Helium Environments	University of Wisconsin, Madison			Document	NGNP	FY2009
Modeling Fission Product Sorption in Graphite Structures	University of Wisconsin, Madison			Document	NGNP	FY2009
Liquid Salt Heat Exchanger Technology for VHTR Based Applications	University of Wisconsin, Madison			Document	NGNP	FY2009
Effect of Post-Weld Heat Treatment on Creep Rupture Properties of Grade 91 Steel Heavy Section Welds	Utah State University			Document	NGNP	FY2009
Alpha Radiolysis of Nuclear Solvent Extraction Ligands used for An(III) and Ln(III) Separations	California State University, Long Beach	$1,390,252		Document	FCR&D	FY2010
Predictive Maturity of Multi-Scale Simulation Models for Fuel Performance	Clemson University	$614,690		Document	FCR&D	FY2010
Freeze-casting as a Novel Manufacturing Process for Fast Reactor Fuels	Drexel University	$1,149,327		Document	FCR&D	FY2010
Fuel Performance Experiments on the Atomistic Level, Studying Fuel Through Engineered Single Crystal UO2	Idaho State University	$650,000		Document	FCR&D	FY2010
Development of A Self Biased High Efficiency Solid-State Neutron Detector for MPACT Applications	Rensselaer Polytechnic Institute	$810,141		Document	FCR&D	FY2010
Development of a Innovative High Thermal Conductivity UO 2 Ceramic Composites Fuel Pellets with Carbon Nano-Tubes Using Spark Plasma Sintering	University of Florida	$894,042		Document	FCR&D	FY2010
Exploration and Modeling of Structural Changes in Waste Glass under Corrosion	Pennsylvania State University	$1,377,444		Document	FCR&D	FY2010
Evaluation of materials for interim storage of spent fuel for more than 100 years	University of Michigan	$931,603		Document	FCR&D	FY2010
Implementation of On-the-Fly Doppler Broadening in MCNP5 for Multiphysics Simulation of Nuclear Reactors	University of Michigan	$406,712		Document	FCR&D	FY2010
Methods and tools to allow molecular flow simulations to be coupled to higher level continuum descriptions of flows in porous/fractured media and aerosol/dust dynamics	University of Missouri-Columbi	$541,286		Document	FCR&D	FY2010
Characterization and Modeling of Materials for Kr-Xe Separations	University of Nevada-Las Vegas	$989,800		Document	FCR&D	FY2010
Modeling Solute Thermokinetics in LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin-Madison	$616,073		Document	FCR&D	FY2010
Advanced Aqueous Separation Systems for Actinide Partitioning: Develop Fundamental Understanding of An(III)/Ln(III) Separation	Washington State University	$1,451,784		Document	FCR&D	FY2010
Consistent Multigroup Theory Enabling Accurate Coarse-Group Simulation of GenIV Reactors	Georgia Institute of Technology	$1,046,277		Document	GEN IV	FY2010
Studies of Deteriorated Heat Transfer in Prismatic Cores Stemming from Irradiation-Induced Geometry Distortion	Idaho State University	$1,287,921		Document	GEN IV	FY2010
Carbide Coatings for Nickel Alloys, Graphite, and Carbon/Carbon Composites to be Used in Fluoride Salt Valves	Johns Hopkins University	$1,183,239		Document	GEN IV	FY2010
Design, Testing, and Modeling of the Direct Reactor Auxiliary Cooling System for AHTRs	Ohio State University	$1,366,627		Document	GEN IV	FY2010
Monitoring microstructural evolution of Alloy 617 with nonlinear acoustics for remaining useful life prediction; multiaxial creep-fatigue and creep-ratcheting	Pennsylvania State University	$1,000,000		Document	GEN IV	FY2010
Development and Validation of Multidimensional Models of Supercritical CO 2 Energy Conversion Systems for Nuclear Power Reactors	Rensselaer Polytechnic Institute	$475,005		Document	GEN IV	FY2010
Multiscale Concrete Modeling for Aging Degradation	Mississippi State University	$345,941		Document	LWRS	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term and Elevated Temperature Irradiation: Modeling and Experimental Investigation	University of California-Berkeley	$1,320,667		Document	GEN IV	FY2010
Development of an advanced computational fluid dynamics technology for the next-generation nuclear reactor system analysis and safety margin characterization code	North Carolina State University	$418,199		Document	LWRS	FY2010
Development of Barrier Layers for the Protection of Candidate Alloys in the VHTR	University of California-Santa Barbara	$995,232		Document	GEN IV	FY2010
Precursor Derived Nanostructured Si-C-X Materials for Nuclear Applications	University of Washington	$899,518		Document	MRIIR	FY2010
Investigation of a Novel NDE Method for Monitoring Thermo-Mechanical Damage and Microstructure Evolution in Ferritic-Martensitic Steels for Generation IV Nuclear Energy Systems	University of Cincinnati	$833,109		Document	GEN IV	FY2010
Development and Testing of an Open-Loop Oscillator for Small Reactivity Worth Samples	Idaho State University	$597,252		Document	MRIIR	FY2010
Fission Product Transport in TRISO Particle Layers under Operating and Off-Normal Conditions	University of Michigan	$966,581		Document	GEN IV	FY2010
Understanding the Irradiation Behavior of Zirconium Carbide	Pennsylvania State University	$870,613		Document	MRIIR	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term Irradiation at Elevated Temperature: Critical Experiments	University of Michigan	$1,181,379		Document	GEN IV	FY2010
Modeling investigation of the stability and irradiation-induced evolution of nanoscale precipitates in advanced structural materials	University of Tennessee-Knoxville	$380,653		Document	MRIIR	FY2010
Three-dimensional NDE of VHTR Core Components via Simulation-based Testing	University of Minnesota	$1,366,163		Document	GEN IV	FY2010
Investigation of Laser Shock Peening for Enhancing Fatigue and Stress Corrosion Cracking Resistance of Nuclear Energy Materials	University of Cincinnati	$1,242,019		Document	MRIIR	FY2010
Failure Predictions for VHTR Core Components using a Probabilistic Continuum Damage Mechanics Model	University of Minnesota	$854,542		Document	GEN IV	FY2010
Irradiation Accelerated Corrosion of Reactor Core Materials	University of Michigan	$798,943		Document	MRIIR	FY2010
Development of a Scanning Microscale Fast Neutron Irradiation Platform for Examining the Correlation Between Local Neutron Damage and Graphite Microstructure	University of Missouri-Columbia	$703,064		Document	GEN IV	FY2010
Study of Interfacial Interactions using Thin Film Surface Modification: Radiation and Oxidation Effects in Materials	University of Wisconsin-Madison	$538,032		Document	MRIIR	FY2010
Development of Thermal Transient Flow Rate Sensors for High Temperature, Irradiation, Corrosive Environment	University of Nevada-Las Vegas	$451,269		Document	GEN IV	FY2010
Novel Engineered Refractory Materials for Advanced Reactor Applications	North Carolina State University	$1,129,304		Document	MRIIR	FY2010
Novel Methods of Tritium Sequestration: High Temperature Gettering and Separation Membrane Materials Discovery for Nuclear Energy Systems	University of South Carolina	$1,366,626		Document	GEN IV	FY2010
Heat Transfer Salts for Nuclear Reactor Systems - Chemistry Control, Corrosion Mitigation, and Modeling	University of Wisconsin-Madison	$1,352,040		Document	GEN IV	FY2010
Pulsed Magnetic Welding for Advanced Core and Cladding Steels	University of Wisconsin-Madison	$525,206		Document	GEN IV	FY2010
Corrosion in Supercritical Carbon Dioxide: Materials, Environmental Purity, Surface Treatments, and Flow Issues	University of Wisconsin-Madison	$651,447		Document	GEN IV	FY2010
Quantification of Cation Sorption to Engineered Barrier Materials Under Extreme Conditions	Clemson University	$1,171,380		Document	FCR&D	FY2011
In-Pile Instrumentation Multi-Parameter System Utilizing Photonic Fibers and Nanovision	Idaho State University	$1,199,990		Document	FCR&D	FY2011
Development of Plasmonically Cloaked Nanoparticles	Idaho State University	$800,000		Document	FCR&D	FY2011
Fission Product Transmutation in Mixed Radiation Fields	Idaho State University	$800,000		Document	FCR&D	FY2011
Life Prediction of Spent Fuel Storage Canister Material	Massachusetts Institute of Technology	$899,826		Document	FCR&D	FY2011
Active Interrogation using Photofission Technique for Nuclear Materials Control and Accountability	Oregon State University	$900,000		Document	FCR&D	FY2011
Anisotropic Azimuthal Power and Temperature Distribution on Fuel Rod: Impact of Hydride Distribution	Pennsylvania State University	$631,956		Document	FCR&D	FY2011
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$1,000,000		Document	FCR&D	FY2011
Recovery of Uranium from Seawater: Preparation and Development of Polymer-Supported Extractants	City College of New York, Hunter	$363,716		Document	MSTR	FY2011
Microemulsions and Aggregation Formation in Extraction Processes for Used Nuclear Fuel: Thermodynamics and Structural Studies	University of California, Irvine	$1,000,000		Document	FCR&D	FY2011
One-Dimensional Nanostructures for Neutron Detection	North Carolina State University	$455,629		Document	MSTR	FY2011
Optimized Processing Fabrication Paths for Larger Heats of Nanostructured Ferritic Alloys	University of California, Santa Barbara	$1,000,000		Document	FCR&D	FY2011
Feasibility and Safety Assessment for Advanced Reactor Concepts Using Vented Fuel	Oregon State University	$600,000		Document	MSTR	FY2011
Basic Physics Data: Measurement of Neutron Multiplicity from Induced Fission	University of Michigan	$973,364		Document	FCR&D	FY2011
Development of an Efficient Meso-Scale Multi-Phase Flow Solver in Nuclear Applications	City College of New York	$505,858		Document	NEAMS	FY2011
High Temperature Transducers for Online Monitoring of Microstructure Evolution	Pennsylvania State University	$455,628		Document	MSTR	FY2011
Radionuclide Incorporation and Long Term Performance of Apatite Waste Forms	University of Michigan	$862,500		Document	FCR&D	FY2011
Multiscale Modeling and Uncertainty Quantification for Nuclear Fuel Performance	Colorado State University	$1,098,250		Document	NEAMS	FY2011
Laser-Arc Hybrid Welding of Thick Section Ni-base Alloys- Advanced Modeling and Experiments	Pennsylvania State University	$536,117		Document	MSTR	FY2011
Actinide Foil Production for MPACT Research	University of Nevada-Las Vegas	$156,897		Document	FCR&D	FY2011
Fundamental Studies of the Role of Grain Boundaries on Uniform Corrosion of Advanced Nuclear Reactor Materials	Drexel University	$1,098,250		Document	NEAMS	FY2011
Correlates of Sensitive Technologies	Texas A&M University	$509,467		Document	MSTR	FY2011
Enriched Boron-Doped Amorphous Selenium Based Position-Sensitive Solid-State Thermal Neutron Detector for MPACT Applications	University of South Carolina	$1,000,000		Document	FCR&D	FY2011
Phenomena-based Uncertainty Quantification in Predictive Coupled-Physics Reactor Simulations	Texas A&M University	$1,098,250		Document	NEAMS	FY2011
Improved Safety Margin Characterization of Risk from Loss of Offsite Power	Texas A&M University	$600,000		Document	MSTR	FY2011
Development of Advanced High Uranium Density Fuels for Light Water Reactors	University of Wisconsin-Madison	$1,000,000		Document	FCR&D	FY2011
Characterization of Modeling of Grain Boundary Chemistry Evolution in Ferritic Steels Under Irradiation	University of Michigan	$1,098,250		Document	NEAMS	FY2011
Diffusion, Thermal Properties and chemical Compatibilities of Select MAX Phases with Materials for Advanced Nuclear Systems	Drexel University	$535,927		Document	NEET	FY2011
A High Temperature-Tolerant and Radiation-Resistant In-Core Neutron Sensor for Advanced Reactors	The Ohio State University	$455,629		Document	MSTR	FY2011
Developing the User Experience for a Next Generation Nuclear Fuel Cycle Simulator	University of Wisconsin-Madison	$1,200,000		Document	FCR&D	FY2011
Development of Multiscale Materials Modeling Techniques and Coarse-Graining Strategies for Predicting Materials Degradation in Extreme Irradiation Environments	University of Tennessee, Knoxville	$750,000		Document	NEAMS	FY2011
A New Light Weight Structural Material for Nuclear Structures	North Carolina State University	$399,490		Document	NEET	FY2011
Pathway Aggregation in the Risk Assessment of Proliferation Resistance and Physical Protection (PR&PP) of Nuclear Energy Systems	The Ohio State University	$534,471		Document	MSTR	FY2011
Experimental Investigation of Convection and Heat Transfer in the Reactor Core for a VHTR	City College of New York	$1,118,856		Document	RCRD&D	FY2011
Preparation of High Purity, High Molecular-Weight Chitin from Ionic Liquids for Use as an Adsorbate for the Extraction of Uranium from Seawater	University of Alabama	$338,260		Document	MSTR	FY2011
Graphite Microstructural Characterization Using Time-Domain and Correlation-Based Ultrasonics	Johns Hopkins University	$1,199,997		Document	RCRD&D	FY2011
Selectivity in Ligand Binding to Uranyl Compounds: A Synthetic, Structural, Thermodynamic and Computational Study	University of California-Berkeley	$500,000		Document	MSTR	FY2011
Methodology Development for Passive Component Reliability Modeling in a Multi-Physics Simulation Environment	The Ohio State University	$533,457		Document	RCRD&D	FY2011
Development of Seismic Isolation Systems Using Periodic Materials	University of Houston	$538,154		Document	MSTR	FY2011
Pebble Fuel Handling and Reactivity Control for Salt-Cooled High Temperature Reactors	University of California, Berkeley	$612,721		Document	RCRD&D	FY2011
Innovative Elution Processes for Recovering Uranium from Seawater	University of Idaho	$400,000		Document	MSTR	FY2011
Self-Sustaining Thorium Boiling Water Reactors	University of California, Berkeley	$1,145,932		Document	RCRD&D	FY2011
Development of Austenitic ODS Strengthened Alloys for Very High Temperature Applications	University of Illinois-Urbana Champaign	$538,154		Document	MSTR	FY2011
High Fluency Low Flux Embrittlement Models of LWR Reactor Pressure Vessel Embrittlement and a Supporting Database from the UCSB ATR-2 Irradiation Experiment	University of California, Santa Barbara	$1,199,607		Document	RCRD&D	FY2011
Enhancement of the Extraction of the Uranium from Seawater	University of Maryland	$400,000		Document	MSTR	FY2011
A Research Program for Fission Product/Dust Transport in HTGR's	University of Missouri-Columbia	$1,157,367		Document	RCRD&D	FY2011
Transient Safety Analysis of Fast Spectrum TRU Burning LWR with Internal Blankets	University of Michigan	$599,475		Document	MSTR	FY2011
Development and Validation of a Lifecycle-based Prognostics Architecture with Test Bed Validation	University of Tennessee, Knoxville	$846,315		Document	RCRD&D	FY2011
Development of Novel Sorbents for Uranium Extraction from Seawater	University of North Carolina, Chapel Hill	$400,000		Document	MSTR	FY2011
In-situ Condition Monitoring of Components in Small Modular Reactors Using Process and Electrical Signature Analysis	University of Tennessee, Knoxville	$650,000		Document	RCRD&D	FY2011
Radiation Behavior of High-Entropy Alloys for Advanced Reactors	University of Tennessee, Knoxville	$538,159		Document	MSTR	FY2011
Technical Development for S-CO2 Advanced Energy Conversion	University of Wisconsin	$815,000		Document	RCRD&D	FY2011
Rapid Computer Aided Ligand Design and Screening of Precious Metal Extractants from TRUEX Raffinate with Experimental Validation	Washington State University	$500,000		Document	MSTR	FY2011
Ag Transport Through Non-Irradiated and Irradiated SiC	University of Wisconsin-Madison	$1,055,456		Document	RCRD&D	FY2011
Critical Heat Flux Phenomena at High Pressure and Low Mass Fluxes: Tests and Models	University of Wisconsin-Madison	$1,199,781		Document	RCRD&D	FY2011
Modeling and Test Validation of a Reactor Cavity Cooling System with Air	University of Wisconsin-Madison	$1,199,988		Document	RCRD&D	FY2011
Transient Mixed Convection Validation for NGNP	Utah State University	$635,860		Document	RCRD&D	FY2011
Alternative High-Performance Ceramic Waste Forms	Alfred University	$840,000	This project aims to advance fundamental understanding of the kinetics of structural evolution of crystalline ceramic waste forms. The structure/property relationships will be identified and will reveal new formulations, improved processing routes, and strategies for improved performance or ceramic waste forms.	Document	FCR&D	FY2012
Surface Layer Bulk Glass Interface Evolution with Aqueous Corrosion	Alfred University	$880,000	This project will investigate the links between the morphology, structure and chemistry of surface layer-bulk glass interface and the long-term corrosion-reaction kinetics using in-situ and ex-situ experiments. The understanding will result in improved models for long-term predictive behavior of high-level-waste (HLW) glasses under repository conditions.	Document	FCR&D	FY2012
Improved Accident Tolerance of Austenitic Stainless Steel Cladding through Colossal Supersaturation with Interstitial Solutes	Case Western Reserve University	$850,000	This project aims to develop new case-hardened austenitic stainless steels by saturating them with materials that improve their mechanical properties, corrosion resistance and radiation resistance. This project, if successful, will result in safer, longer-lasting, and more accident tolerant fuel claddings.	Document	FCR&D	FY2012
Optimization of Deep Borehole Systems for HLW Disposal	Massachusetts Institute of Technology	$850,000	Researchers aim to carry out a comprehensive evaluation of the deep borehole option for disposal of used nuclear fuel and high livel waste. The models developed will predict potential movement of water through natural and engineered barriers and release of radionuclides to the biosphere which will aide in site selection.	Document	FCR&D	FY2012
Scholarship for Nuclear Communications and Methods for Evaluation of Nuclear Project Acceptability	Massachusetts Institute of Technology	$800,000	Researchers will work to develop a model to characterize the factors affecting social acceptance of nuclear projects with potential stakeholders. The resultant model will strengthen the ability to design and implement large projects more efficiently, leading to higher rates of success of future nuclear projects.	Document	FCR&D	FY2012
Accurate Holdup Calculations with Predictive Modeling and Data Integration	North Carolina State University	$875,000	Researchers will develop and use state-of-the-art radiation transport codes to account accurately for the fissile material in a nuclear materials processing facility. An accurate estimation of the materials will allow for ensured radiological safety, security, waste management and efficient plant operation.	Document	FCR&D	FY2012
Novel Metal Sulfides to Achieve Effective Capture and Durable Consolidation of Radionuclides	Northwestern University	$760,000	Researchers will evaluate the effectiveness of chalcogenide based materials design novel metal sulfides to effectively capture and store of radioisotopes released during reprocessing of used nuclear fuel. This project will focus on understanding structure-property relationships to enable refined and direct synthesis approaches for improved and cost-efficient nuclear waste forms.	Document	FCR&D	FY2012
Nonlinear Ultrasonic Diagnosis and Prognosis of ASR Damage in Dry Cask Storage	Northwestern University	$885,000	Researchers aim to use nondestructive damage characterization methods to detect, manage and mitigate the degradation/damage mechanisms of dry cask storage systems for nuclear fuels. This project, if successful, will provide tools that will allow the prediction of the reliability and the safety of concrete structures in dry cask storage systems.	Document	FCR&D	FY2012
Prototype Demonstration of Gamma-Blind Tensioned Metastable Fluid Neutron/Multiplicity/Alpha Detector- Real Time Methods for Advanced Fuel Cycle Applications	Texas A&M University	$875,000	This project aims to create a prototype demonstration of a novel neutron/alpha detector based on a technology that is blind to gamma field used fuel. The prototype, if successful, will enhance instrumentation for monitoring real-time material balance during various stages of the nuclear cycle.	Document	FCR&D	FY2012
Testing of Sapphire Optical Fiber and Sensors in Intense Radiation Fields, when Subjected to Very High Temperatures	The Ohio State University	$885,000	The researchers on this project will investigate the performance of sapphire optical fibers and sensors in reactor environments. The project, if successful, will result in improved instrumentation to understand the behavior and predict performance of nuclear fuel systems at the microstructural level.	Document	FCR&D	FY2012
Concrete Materials with Ultra-High Damage Resistance and Self-Sensing Capacity for Extended Nuclear Fuel Storage Systems	University of California, Irvine	$800,000	Researchers aim to design a new class of multifunctional concrete materials. This project, if successful, will result in a novel multifunctional concrete material that possesses inherent degradation monitoring capability and is suitable for an extended storage system for the used nuclear fuel.	Document	FCR&D	FY2012
Development of Innovative Accident Tolerant High Thermal Conductivity UO2 Fuel Pellets with a Diamond Dopant	University of Florida	$800,000	Researchers will evaluate the use of diamond nanoparticles composite material in innovative accident tolerant fuel pellets. This could significantly improve both the thermal conductivity of fuel pellets and light water reactors' efficiency safety.	Document	FCR&D	FY2012
Probabilistic Multi-Hazard Assessment of Dry Cask Structures	University of Houston	$865,000	This project aims to investigate the performance of dry cask storage systems under multiple hazard systems (earthquake, tornados, combined with aging effects) using a probabilistic multi-hazard framework. This framework will be validated based on experimental research and will provide improved models for safety and reliability of spent nuclear fuels during storage and transportation.	Document	FCR&D	FY2012
Measurement of Irradiated Pyroprocessing Samples via Laser Induced Breakdown Spectroscopy	University of Idaho	$820,000	This project aims to use advanced characterization techniques to investigate microstructural changes and the micromechanisms related to irradiation induced damage in used nuclear fuels and waste forms. This project, if successful, will result in enhanced models to predict the structural and chemical response of used fuel and waster forms during interim storage and permanent disposal.	Document	FCR&D	FY2012
Elastic/Inelastic Measurement Project	University of Kentucky	$880,523	Researchers will measure nuclear data for elastic/inelastic scattered neutrons on coolants and structural materials. The data generated, will be useful for future R&D programs that will study innovative next generation LWR and future fast systems.	Document	FCR&D	FY2012
Electrochemical Corrosion Studies for Modeling Metallic Waste Form Release Rates	University of Nevada- Las Vegas	$790,000	This project aims to use advanced electrochemical methods to investigate the corrosion related degradation of metal alloys used for housing fission products. The data obtained from this study will allow for the prediction of the long-term behavior of the metallic host phase materials over geological time-scales.	Document	FCR&D	FY2012
Thermodynamic and Microstructural Mechanisms in the Corrosion of Advanced Ceramic Tc-bearing Waste Forms and Thermophysical Properties	University of Nevada- Las Vegas	$795,000	This project team will harvest thermodynamic and microstructural data on the evolution of ceramic based waste forms. The data will be used to advance the current state-of-the-art methodology used for isolation and stabilization of fission products and improve on nuclear fuel recycling processes.	Document	FCR&D	FY2012
Development and Experimental Benchmark of Simulations to Predict Used Nuclear Fuel Cladding Temperatures during Drying and Transfer Operations	University of Nevada- Reno	$745,000	Researchers will conduct experiments to investigate and develop advanced computational models of heat transfer in post-pool-storage drying operations. This project, if successful, will result in tools that can be used to design efficient drying processes to as to ensure suitability for dry-cask systems for long-term storage and transport.	Document	FCR&D	FY2012
Better Radiation Response and Accident Tolerance of Nanostructured Ceramic Fuel Materials?	University of Tennessee	$815,000	Researchers will use novel experimental methods to investigate the links between microstructure, phase stability and damage evolution in nanostructured ceramic fuel materials. The project will study fuel materials at temperatures and irradiation conditions relevant to operation and accidental scenarios.	Document	FCR&D	FY2012
Radiation and Thermal Effects on Used Nuclear Fuel and Nuclear Waste Forms	University of Tennesssee	$770,000	This project aims to investigate the structural and chemical response of used nuclear fuel and waste forms during interim storage and permanent disposal. If successful, this project will generate models that will allow the prediction of structural evolution and hence the radiological safety and security of nuclear fuel and waste forms.	Document	FCR&D	FY2012
Seismic Performance of Dry Casks Storage for Long-Term Exposure	University of Utah	$873,319	Researchers will evaluate the mechanical performance of dry-cask storage under seismic loading for mid-term operational periods. Simulations will include scenarios for freestanding, anchored, and vaulted casks. The experimental tests will also evaluate the dynamic seismic response of freestanding and anchored dry-cask storage prototypes, providing recommendations for optimal Interim Spent Fuel Storage Installations (ISFSIs) design.	Document	FCR&D	FY2012
Validation Experiments for Spent-Fuel Dry-Cask In-Basket Convection	Utah State University	$690,000	Researchers in this project aim to conduct experiments that generate data on natural convection through a fuel assembly. The data will be used to validate the computational models being developed for nuclear safety and design.	Document	FCR&D	FY2012
Re-Branding the Nuclear Fuel Cycle	Virginia Commonwealth University	$850,000	This project will create a comprehensive framework for the evaluation of alternative fuel cycle systems that will be used to identify and analyze key elements related to long-term management of nuclear fuels , with the ultimate goal to develop a communications strategy to reach stakeholders.	Document	FCR&D	FY2012
Advanced Characterization of Molecular Interactions in TALSPEAK-like Separations Systems	Washington State University	$875,000	Researchers will use advanced characterization techniques (experimental and computational) to improve understanding of the molecular level processes/interactions during separation processes for advanced fuel cycles. The understanding of these interactions will be used to develop more robust and streamlined separation processes for advanced fuel cycles.	Document	FCR&D	FY2012
Coupling of Nuclear Waste Form Corrosion and Radionuclide Transport in Presence of Relevant Repository Sediments	Washington State University	$885,000	Researchers will conduct experiments to understand the mechanisms responsible for the corrosion of nuclear waste forms in realistic chemical environments. The data generated from these experiments will enable increased reliability of the models used to predict the waste form performance in repository environments.	Document	FCR&D	FY2012
Stationary Liquid Fuel Fast Reactor (SLFFR) Concept for TRU Burning	Purdue University	$450,000	Reasearchers will investigate a new type of molten metallic fuel reactor concept that will consume hazardous transuranic waste. The liquid fuel alloy has several advantages over solid fuel fast reactors that are used for the same purpose.	Document	MSTR	FY2012
ABR for TRU Transmutation with Breed & Burn Thorium Blanket for Improved Economics and Resource Utilization	University of California- Berkeley	$450,000	The research team will use detailed neutronic analysis for a new Advanced Burner Reactor concept with low conversion ratio. The concept will use a new core shape to improve the utilization of neutrons to perform breed and burn.	Document	MSTR	FY2012
New Materials for High Temperature Thermoelecric Power Generation	University of California, Davis	$450,000	Reasearchers will work to develop nanostructured and other new materials to support the development of higher efficiency thermoelectric devices. These devices convert thermal energy to electricity with no moving parts. The new materials will operate at higher efficiencies and over a wider temperature range than those currently available--an important quality for future nuclear-powered deep space exploration.	Document	MSTR	FY2012
Microscopic Fuel Particles Produced by Self-Assembly of Actinide Nanoclusters on Carbon Nanomaterials	University of Notre Dame	$440,000	Reasearchers will develop the mechanisms, conditions and protocols to prepare uranium-carbon nanocomposite materials to make them more flexible. This could result in the generation of wholesale electricity, providing process heat, and providing power for households.	Document	MSTR	FY2012
High Hydrogen Content Graphene Hydride Compounds & High Cross-Section Cladding Coatings for Fast Neutron Detection	University of South Carolina	$430,000	This project will exploit recent breakthroughs to grow epitaxial graphene on commercial SiC wafers. This will allow researchers to develop a new detection method for fast neutrons. In addition, it will lead to better and more compact neutron detection system.	Document	MSTR	FY2012
Reducing Actinide Production Using Inert Matrix Fuels	University of Texas- Austin	$435,000	Reasearchers will perform a neutronic analysis, a thermal-hydraulic analysis and a simulation of fuel decay heat as a functionof fuel burnup, to determine if inert matrix fuel in coventional reactors will continue to be licensable. If successful, the inert matrix fuel mixtures will reduce harmful transuranic components in the fuel discharge streams at a level comparable to a fast reactcor burner.	Document	MSTR	FY2012
An Integrated Fuel Depletion Calculator for Fuel Cycle Options Analysis	University of Texas- Austin	$395,000	Reasearchers use new analysis techniques to better predict nuclear fuel behavior. The new model will allow improved fuel cycle for a larger number of users.	Document	MSTR	FY2012
Atomic-Scale to Meso-Scale Simulation Studies of Thermal Ageing and Irradiation Effects in Fe-Cr Alloys	Boston University	$874,997	Reasearchers will develop predictive, multi-scale simulation tools for iron-chromium alloys, which are expected to be key components of advanced steels envisioned as fuel cladding and structural components for Generation IV reactors. Such modeling is necessary to avoid resource intensive and costly thermal and neutron irradiation experiments to obtain required performance data.	Document	NEAMS	FY2012
Validation Data and Model Development for Fuel Assembly Response to Seismic Loads	George Washington University	$862,435	Reasearchers will conduct experiments that will provide comprehensive data characterizing the dynamics of the fluid and the structure in Pressurized Water Reactors (PWR) fuel assemblies under seismic loads (earthquakes and loss of coolant accidents). Completion of their project will greatly benefit the safety of existing and future nuclear reactors.	Document	NEAMS	FY2012
Uncertainty Quantification and Management for Multiscale Nuclear Materials Modeling	Georgia Institute of Technology	$743,444	Reasearchers will address the question of uncertainty propogation and error estimates associated with model prediction of material behavior under irradiation. Their work will facilitate a better understanding of the connection of various unit processes to collective responses in a multiscale model chain enabling the development of high strength and high ductility materials.	Document	NEAMS	FY2012
Fuel and Core Design Options to Overcome the Heavy Metal Loading Limit and Improve Performance and Safety of Liquid Salt Cooled Reactors	Georgia Insitute of Technology	$784,689	Reasearchers will examine new options for fuel and core designs in liquid salt cooled reactors where the current standard of TRISO type fuel has limitations due to loading characteristics. The research could enable new, more feasible fuel-core-reload options that will improve safety and performance parameters.	Document	RCRD&D	FY2012
Nonlinear Ultrasonic Techniques to Monitor Radiation Damage in RPV and Internal Components	Georgia Institute of Technology	$877,000	Reasearchers will explore new nondestructive materials evaluation and monitoring techniques utilizing nonlinear ultrasonic measurements . This technique will allow researchers to assess remaining useful life of select reactor components. Breakthroughs in this area will lead to the ability to characterize radiation damage in reactor pressure vessels and other components-leading to a clearer definition of reactor safety margins.	Document	RCRD&D	FY2012
Intergral Reactor Containment Condensation Model and Experimental Validation	Oregon State University	$871,119	Reasearchers will conduct experiments to enhance the safety and efficiency of small modular reactors (SMRs). This project will assess the impact of high-pressure steam condensation on steel containment vessels to be used for SMR deigns.	Document	RCRD&D	FY2012
Investigation of Natural Circulation Instability and Transients in Passively Safe Small Modular Reactors	Purdue University	$871,100	Reasearchers will perform scaled experiments to study the thermal-hydraulic instabilities that can occur in Small Modular Reactors (SMR) which rely on natural circulation cooling during normal operation and accident conditions. Their work will not only improve our understanding of general natural circulation instability but also lead to the development of stability criteria and predictability in the operation of SMRÃs.	Document	RCRD&D	FY2012
Thermoelectric-Driven Sustainable Sensing and Actuation Systems for Fault-Tolerant Nuclear Incidents	State University of New York, Stony Brook	$599,802	Reasearchers will examine the use of solid-state thermoelectric generators to produce electricity to sense and opeate during both normal and abnormal situations. This will provide indefinite monitoring of key components during power outages or station blackouts.	Document	RCRD&D	FY2012
Experimental and CFD Studies of Coolant Flow Mixing within Scaled Models of the Upper and Lower Plenums of NGNP Gas-Cooled Reactors	Texas A&M University	$713,051	Reasearchers will model the internal coolant flow of a prismatic core very high temperature reactor (VHTR) by using large eddy simulation tools. This method will enable more accurate prediction of flow field characteristics and better evaluation of VHTR behavior under operational and accidental conditions.	Document	RCRD&D	FY2012
Demonstrating Hybrid Heat Transport and Energy Conversion System Performance Characterization Using Intelligent Control Systems	University of Idaho	$877,000	Reasearchers will demonstrate an intelligent control systems in a hybrid energy conversion loop for a next generation nuclear power plant. Hybrid energy systems are a method of optimizing the use of natural resources for energy production. Hybrid systems present an opportunity to develop domestic energy sources to improve energy security.	Document	RCRD&D	FY2012
Advanced Reactor-Intermediate Heat Exchanger (IHX) Coupling: Theoretical Modeling and Experimental Validation	University of Idaho	$869,997	Reasearchers will model the behavior of the Advanced Reactor Intermediate Heat Exchanger Chemical Process system and develop advanced control techniques that take into account abnormal scenarios. The data and information obtained will assist in the development of intelligent control systems for next generation nuclear reactor systems.	Document	RCRD&D	FY2012
Irradiation Performance of Fe-Cr Base Alloys	University of Illinois- Urbana Champaign	$876,332	Reasearchers will perform post-radiation analysis and develop tools for future development and application of the Fe-Cr class of alloys. The results of this research will lead to better modeling of performance and development of an alloy designated as the primary choice for reactor fuel cladding and structural applications in advanced systems.	Document	RCRD&D	FY2012
Accelerated Irradiations for High Dose Microstructures in Fast Reactor Alloys	University of Michigan	$831,876	Reasearchers will determine the extent to which high dose rate irradiation can be used as an irradiation damage tool to understand microstructure evolution at high doses and temperatures relevant to advanced fast reactors. The project will provide fundamental understanding of the effectiveness of this process and thus of microstructure development in irradiated materials.	Document	RCRD&D	FY2012
Mitigating IASCC of Reactor Core Internals by Post-Irradiation Annealing Advanced Mitigation Strategies	University of Michigan	$876,985	Reasearchers will determine the optimum Post-irradiation annealing (PIA)-driven mitigation strategy to extend the potential lifetime of light water reactors. Samples that have already been irradiated in a light water reactor will be used to test PIA treatments to understand IASCC initiation and propoagation, annealing kinetics, the role of microstructure features in irradation hardening and localized deformation, and the optimum mitigation strategy based on PIA.	Document	RCRD&D	FY2012
Experimentally Validated Numerical Models for Effects of Non-Isothermal Turbulent Mixing on Wall Stresses in High Temperature Reactors	University of Pittsburgh	$876,422	Reasearchers will develop a comprehensive experimentally validated computational framework for the turbulent mixing in the lower plenum of a very high temperature reactor (VHTR). Through CFD modeling and experimental validation, the results from this project will lay the groundwork for future stress analysis, failure and fatigue studies, and uncertainty quantification for the VHTR system.	Document	RCRD&D	FY2012
Role of Defects in Swelling and Creep of Irradiated SiC	University of Wisconsin- Madison	$875,350	Reasearchers will study mechanisms controlling both radiation swelling and radiation creep in silicon carbide. These two effects are crucial to understanding the issues associated with the brittle silicon carbide composite. Success in this project will ground progress in the adoption of silicon carbide for reactor solutions, particularly as fuel cladding.	Document	RCRD&D	FY2012
Advanced Supercritical Carbon Dioxide Brayton Cycle Development	University of Wisconsin, Madison	$877,000	Reasearchers will investigate the benefits of utilizing advanced Brayton cycles with supercritical carbon dioxide in new reactor systems and components. Benefits of this research include improvement of analysis and performance of components currently utilizing these cycles as well as the potential for a large scale advanced CO2 power system.	Document	RCRD&D	FY2012
Mechanical Behavior of UO2 at Sub-grain Length Scales: Quantification of Elastic, Plastic and Creep Properties via Microscale Testing	Arizona State University	$800,000	Reasearchers will develop techniques to measure properties at sub-grain scales using depleted Uranium Oxide samples. The project will provide a framework to measure sub-grain scale mechanical properties, as well as provide experimental data to improve the understanding of advanced oxide fuels.	Document	FCR&D	FY2013
The Impacts of Pore-Scale Physical and Chemical Heterogeneities on the Transport of Radionuclide-Carrying Colloids	Colorado School of Mines	$800,000	Reasearchers will identify the dominant transport mechanisms to develop models that predict radionuclide distribution in porous materials. Experimental and computational models will be created that couple pore-scale geometric and interfacial structures. Simulators such as these are a necessary step towards fully predictive models for field-scale applications in the future.	Document	FCR&D	FY2013
Recovery of Uranium from Seawater: Polymer-Supported Aminophosphinates as Selective Extractants	Hunter College, CUNY	$399,999	Reasearchers will prepare a polymer-supported extractant for the recovery of uranium from seawater. The project will focus on primary amines that could provide a 3-fold increase in uranium capture capacity than current methods.	Document	FCR&D	FY2013
In-pile Thermal Conductivity Characterization with Single-laser Heating/Time Resolved Raman	Iowa State University	$800,000	Reasearchers will develop a time-resolved Raman-based thermal conductivity measurement system to improve remote in-pile thermal conductivity measurement. These measurements will provide new insights into the behavior of materials exposed to extreme radiation and temperature environments. Understanding the behavior of materials at the microstructural level will support optimized fuel designs.	Document	FCR&D	FY2013
Organic Speciation and Interactions in ALSEP - One Step Partitioning Process of Minor Actinides, Lanthanides, and Fission Products	Oregon State University	$600,000	Reasearchers will investigate the Actinide-Lanthanide Separation (ALSEP) process organic phase prior to aqueous phase separation and after aqueous separation phases of bare and metal-loaded acids. Quantifying these effects can be used to determine how an engineering scale process will perform and generate an accurate chemical model for the system.	Document	FCR&D	FY2013
Glass Composition and Solution Speciation Effects on Stage III Dissolution	Pennsylvania State University	$700,000	Reasearchers will study the chemical and structural triggers of long-term vitrified nuclear waste form behavior. They will study a range of waste glass compositions in corrosive environments. The study will improve understanding of the long-term residual rate and may provide new options for environmental control of glass dissolution rates.	Document	FCR&D	FY2013
Correlating Thermal, Mechanical, and Electrical Coupling Based Multiphysics Behavior of Nuclear Materials Through In-Situ Measurements	Purdue University	$800,000	Reasearchers will use in-situ experimental techniques to monitor the influence of extreme conditions on fuel cladding. The project will establish an in-situ experimental setup that can predict change in thermal properties and their correlation with mechanical properties and correlate such changes to changes in microstructural and chemical features.	Document	FCR&D	FY2013
Creation of a Geant4 Muon Tomography Package for Imaging of Nuclear Fuel in Dry Cask Storage	Purdue University	$440,000	Reasearchers will develop a simulation and analysis package to aid in the non-destructive assessment of sealed used nuclear fuel dry casks using cosmic ray muons. Cosmic ray muon tomography allows for non-destructive assessment that can independently verify and identify weapons grade material sealed within dense dry casks.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Two-stage Fast Reactor Fuel Cycle Options for Optimum Resource Utilization and Waste Management	Purdue University	$400,000	Reasearchers will evaluate the two different two-stage fast reactor fuel cycle options that will offer efficient use of uranium resources and the ability to burn actinides and long-live fission products. Evaluation of these fast fuel cycle options will serve as a useful complement to the options currently being considered in the Fuel Cycle Options Campaign.	Document	FCR&D	FY2013
Mixed Metal Phosphonate-Phosphate Resins for Separation of Lanthanides from Actinides	Texas A&M University	$650,000	Reasearchers will use ion exchangers to cleanly separate lanthanides and curium from reusable actinides. The study will assist in the development of an inexpensive, simple way in which to separate lanthanides from actinides found in used nuclear fuel rods and to recover a large portion of the usable fuel.	Document	FCR&D	FY2013
Safeguards in Pyroprocessing: an Integrated Model Development and Measurement Data Analysis	The Ohio State University	$626,151	Reasearchers will develop a comprehensive and effective safeguards approach for a pyroprocessing facility to support safeguards for future fuel cycles in the United States. The new approach and design will focus directly on the special nuclear materials in the electrorefiner where actinides are separated from fission products through electrochemical process.	Document	FCR&D	FY2013
Using Ionic Liquids for the Development of Renewable Biopolymer-Based Adsorbents for the Extraction of Uranium from Seawater and Testing Under Marine Conditions	University of Alabama	$400,000	Reasearchers will explore the fundamental engineering parameters for a renewable high-performance adsorbent for the extraction of uranium from sweater based on a recently proven ionic liquid (IL)-chitin platform. The project will use the platform to develop a versatile, modifiable adsorbent and characterize its performance and degradation in marine conditions.	Document	FCR&D	FY2013
Developing Ultra-Small Scale Mechanical Testing Methods and Microstructural Investigation Procedures for Irradiated Materials.	University of California, Berkeley	$800,000	Reasearchers will develop new small-scale mechanical testing techniques to allow for the estimation or direct measurement of bulk properties. The combined experiments and modeling will significantly enhance the statistics and information that can be obtained on small radioactive archived samples, as well as new ion beam irradiated specimens.	Document	FCR&D	FY2013
Improved Delayed-Neutron Spectroscopy Using Trapped Ions	University of California, Berkeley	$400,000	Reasearchers will develop innovative spectroscopy techniques to measure the decay of fission fragments. The resulting data from these new techniques will be used to better understand reactor kinetics under accident conditions and failure scenarios.	Document	FCR&D	FY2013
Thermally and Chemically Responsive Nanoporous Materials for Efficient Capture of Fission Product Gases	University of California, Davis	$750,000	Reasearchers will create new nanoporous materials that will be highly effective at capturing fission product gases. These materials would be relevant to both reactor fuels applications and reprocessing operations. Tests will be performed in carbon based and nitride based nanostructures, with the most promising materials from the modeling perspective undergoing further testing.	Document	FCR&D	FY2013
Multiphase Nanocrystalline Ceramic Concept for Nuclear Fuel	University of California, Irvine	$800,000	Researchers will study the use of nanoparticles and nanostructured ceramics to create new materials that can extend the service life and increase efficiency for nuclear fuel. Multiphase nanocrystalline ceramics will be used to design simulated nuclear fuel that can provide added plasticity, better radiation tolerance and improved thermal conductivity.	Document	FCR&D	FY2013
Development of Novel Porous Sorbents for Extraction of Uranium from Seawater	University of Chicago	$400,000	Reasearchers will develop a highly porous sorbent for the extraction of uranium from seawater. Previous research has established sorbent performance. This project will use past foundational studies to design and investigate a new nanocomposites that will be processed into tacks or braids for field tests in seawater tests. The technology may also be used for other metals.	Document	FCR&D	FY2013
Microwave Readout Techniques for Very Large Arrays of Nuclear Sensors	University of Colorado, Boulder	$799,937	Reasearchers will develop a powerful readout technique based on microwave transmission and reflection. The technique will enable very large arrays of diverse sensor types for nuclear materials quantification and tracking. It will provide more accurate data on material composition and quantity.	Document	FCR&D	FY2013
BiI3 Gamma-Ray Spectrometers for Reliable Room-Temperature Nuclear Materials Safeguarding	University of Florida	$799,999	Reasearchers will develop gamma-ray spectrometers based on BiI3 single crystals for MPACT applications such as burnup validation quantification, improved assay of plutonium, determination of uranium enrichment and overall monitoring spent fuel within the fuel cycle. The project will improve energy resolution, efficiency and environmental performance with this new gamma-ray detector.	Document	FCR&D	FY2013
Innovative Coating of Nanostructured Vanadium Carbide on the F/M Cladding Tube Inner Surface for Mitigating the Fuel Cladding Chemical Interactions	University of Florida	$760,276	Researchers will develop barrier coatings on the inner surface of fuel cladding tubes to improve performance of materials at elevated temperatures and high neutron exposures in fast reactors. The project will develop and test a low temperature coating process of nanostructured vanadium carbide that will provide a benchmark for use in future studies.	Document	FCR&D	FY2013
Doubling the Life of Concrete Structures	University of Idaho	$800,000	Reasearchers will use nanoscale techniques to develop methods for doubling the service life of concrete structures. They will study the effect of temperature load and temperature cycling (freezing and thawing) on the durability of concrete with nanoscale viscosity modifiers. The project will benefit from non-destructive evaluation of concrete performance through electrochemical techniques.	Document	FCR&D	FY2013
Off-Gas Treatment: Evaluation of Nano-structured Sorbents for Selective Removal of Contaminants	University of Idaho	$785,910	Reasearchers will evaluate nanostructured sorbent materials for their effectiveness in removing and immobilizing radionuclides for the off-gas treatment from used nuclear fuel recycling operations. The project aims at achieving near-zero emissions of radionuclides by capturing them from the off-gas of recycling operations, allowing for the development of advanced fuel cycles.	Document	FCR&D	FY2013
Innovative Elution Processes for Recovering Uranium and Transition Metals from Amidoxime-Based Sorbents	University of Idaho	$399,864	Reasearchers will develop a new two-step elution process to achieve total recovery of uranium and effective recycling of the sorbent. The extraction process would selectively remove uranium from the sorbent with little or no damage. The process would then remove transition metals and regenerate the sorbent for repeated use, making uranium extraction from seawater economically viable.	Document	FCR&D	FY2013
Performance of a Steel/Oxide Composite Waste Form for Combined Waste Streams from Advanced Electrochemical Processes over Geologic Time Scales	University of Illinois at Chicago	$700,000	Reasearchers will develop and validate a mechanistically-based corrosion model for cermet-type waste forms, creating a testing protocol and modeling approach for predicting long-term performance. The study will apply novel electrochemical testing and modeling methods to the behavior of metal/oxide phase boundaries to evaluate waste form performance.	Document	FCR&D	FY2013
Enhancement of the Extraction of Uranium from Seawater	University of Maryland, College Park	$400,000	Reasearchers will develop and optimize novel adsorbents for uranium recovery from seawater. The team will use radiation-induced grafting of organic phosphates onto polymers. The experiments will use ocean water, with mechanistic analysis, to provide a solid basis for large-scale demonstration of the performance of the new adsorbents in ocean environments.	Document	FCR&D	FY2013
Improving the Understanding of the Coupled Thermal-Mechanical-Hydrologic Behavior of Consolidating Granular Salt	University of New Mexico	$800,000	Reasearchers will increase the understanding of granular salt seal materials for shafts, drifts and boreholes. By coupling thermal, mechanical and hydrological responses, the study will result in greater confidence in granular salt consolidation as a principal strategy for closure and isolation of long-term waste repositories.	Document	FCR&D	FY2013
Fission Fragment Yield Data in Support of Advanced Reactor Technology	University of New Mexico	$399,816	Reasearchers will produce a highly accurate data set for thermal fission. These precision data are necessary for high-accuracy simulations of nuclear criticality, transmutation rates, radiation effects and heating as well as for nuclear fuel, material accounting and identification needs.	Document	FCR&D	FY2013
Molecular dynamics-based simulations of bulk/interfacial structures and diffusion behaviors in nuclear waste glasses	University of North Texas	$700,000	Reasearchers will generate accurate atomic structural models for use in Monte Carlo simulations of the dissolution of nuclear waste glasses. Large-scale molecular dynamics-based computer simulations will be used to investigate self-diffusion behaviors, interfacial structure, and other structures formed during dissolution of these glasses.	Document	FCR&D	FY2013
U3Si2 Fabrication and Testing for Implementation into the BISON Fuel Performance Code	University of South Carolina	$800,000	Reasearchers will fabricate, test and model a high uranium density, advanced nuclear fuel that operates at a much lower temperature and stores less energy. The work will deliver key research data on creep and grain growth, improving economics, through possible power uprates, and advancing accident tolerant fuels research.	Document	FCR&D	FY2013
Structural Health Monitoring of Nuclear Spent Fuel Storage Facilities	University of South Carolina	$738,618	Reasearchers will develop a nuclear structural health monitoring system based on a sensing technology that monitors material degradation and aging for dry cask storage systems. The low-cost, low-profile sensors will perform on-demand monitoring of the structural integrity of individual components as well as the entire system.	Document	FCR&D	FY2013
ORIGEN-based Nuclear Fuel Depletion Module for Fuel Cycle Assessment	University of Tennessee at Knoxville	$755,181	Reasearchers will develop a flexible reactor analysis module for the CYCLUS fuel cycle simulator based on established tools for reactor fuel depletion and decay. They will use ORIGEN, a mature and experimentally validated code, affording greater flexibility and allowing for accurate evaluations of impacts of both present and future fuel cycle options.	Document	FCR&D	FY2013
Cost and System Analysis of Innovative Fuel Resources Concepts	University of Texas at Austin	$295,960	_This project will develop and test braided polymer fiber adsorbents that surpass the sorption capacity, selectivity and durability of the best existing technology to recover uranium from seawater.	Document	FCR&D	FY2013
Risk Assessment of Structural Integrity of Transportation Casks	University of Utah	$789,296	Reasearchers will assess the loss of structural integrity of transportation casks and fuel cladding after extended storage. This risk assessment will conduct experimental tests and simulations to evaluate the structural performance of fuel, fuel assemblies and cask components when subjected to vibration and impact loads during transport.	Document	FCR&D	FY2013
Market-Based and System-Wide Fuel Cycle Optimization	University of Wisconsin, Madison	$612,731	Reasearchers will create market and economic optimizers to improve calculations for the CYCLUS fuel cycle simulator. The team will leverage existing optimization software frameworks within the simulator to resolve top level policy questions. The optimizations will allow CYCLUS to move beyond static material compositions, providing a holistic view of the fuel cycle system.		FCR&D	FY2013
Optical Fiber Based System for Multiple Thermophysical Properties for Glove Box, Hot Cell and In-Pile Applications	Utah State University	$799,975	Reasearchers will use a small pressure vessel to develop a robust technique for the measurement of multiple thermophysical properties at very high temperatures. The technique will lead to a system design moving toward the eventual measurement of irradiated fuels in a glovebox and/or hot cell with all sensors and electronics outside of the glovebox and/or hot cell.	Document	FCR&D	FY2013
Development of a Nano-Modified Concrete for Next Generation of Storage Systems	Vanderbilt University	$796,268	Reasearchers will use nano-sized and nano-structured particles based on enhanced reactivity to develop a superior concrete for the long-term storage of used nuclear fuel. The project will use state-of-the-art experimental chemical and mechanical characterizations and computation analysis to assess the performance of nano-modified concretes.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Thorium Fuel Cycle Options	Vanderbilt University	$797,995	Reasearchers will develop six fuel cycle data packages for multi-stage, thermal fuel cycles which incorporate thorium. These new fuel cycle data packages will provide the opportunity to examine fuel cycle options beyond those which have traditionally been considered. A thorium fuel cycle database will also be assembled as a basis for thorium literature for future evaluations of the thorium fuel cycle.	Document	FCR&D	FY2013
Enhanced Shielding Performance of HLW Storage Packages via Multi-Component Coatings	Virginia Polytechnic Institute and State University	$796,947	Reasearchers will develop a multi-layer composite that will enhance long-term storage and facilitate safe transport of storage packages. This novel multi-layer, multi-component coating would create an outer shield material that is resistant to the corrosion, radiation, diffusion and thermal cycling processes that affect fuel packages during long term storage.	Document	FCR&D	FY2013
Managing Zirconium Chemistry and Phase Compatibility in Combined Process Separations for Minor Actinide Partitioning	Washington State University	$700,000	Reasearchers will address unique challenges for combining TRUEX and TALSPEAK processes for partitioning of lanthanides and minor actinides. The project will develop improved information on the thermodynamics of fission product zirconium and develop a framework for an organic phase solvation model. Combined process development could streamline separations processes.	Document	FCR&D	FY2013
Advances in the Recovery of Uranium from Seawater: Studies Under Real Ocean Conditions	Woods Hole Oceanographic Institution	$398,882	Reasearchers will provide infrastructure and expertise for marine testing of currently available adsorbents in real ocean conditions. The team will move adsorbent research from the lab to field testing in order to quantify sorptive properties and uranium uptake. The project will provide valuable field data that will show the potential of large scale applications of these technologies.	Document	FCR&D	FY2013
NEUP Project 20-19172: Irradiation of Sensors and Adhesive Couplants for Application in LWR Primary Loop Piping and Components		$497,881	Reasearchers paln to attach ultrasonic transducers to substrates using various adhesive couplants that will be irradiated at elevated temperature to simulate LWR primary loop conditions at the PULSTAR reactor at North Carolina State University. Ultrasonic data will be taken in-situ. Subsequently, the sensors and couplant interfaces will be characterized using the LAMDA facility at ORNL. The results will be used to benefit a parallel EPRI project on online monitoring of cracks in LWR primary loop piping._	Document	R&D NSUF	FY2013
NEUP Project 20-19404: Extension of MSTDB to Provide a High-Quality, Validated Thermochemical Database for Predicting/Simulating Corrosion in Molten Salt Reactor SystemsUniversity of South Carolina		$600,000	Reasearchers will generate a validated, consistent database of initial fuel compositions and potential corrossion products of fluoride and chloride salts, allowing for important phenomena predictions in molten salt reactors to guide confident decisions. The database will be integral to the currently being developed Molten Salt Thermochemical Database (MSTDB), structured to allow use by commercial and open source codes._	Document	NEAMS	FY2013
Lower Length Scale Characterization and Validation of Formation and Stability of Helium Bubbles in Nano-structured Ferritic Alloys under Irradiation	Clemson University	$399,870	Reasearchers will provide a fundamental knowledge about the formation and stability of ultra-fine helium bubbles within 14YWT after neutron/ion irradiation for further design of new advanced structural materials with a characteristic high density nanoparticles feature which can increase the mechanical strength, hardness, irradiation resistance and the operational temperature range of materials.	Document	NEAMS	FY2013
Three-Dimensional Fuel Pin Model Validation by Prediction of Hydrogen Distribution in Cladding and Comparison with Experiment	Pennsylvania State University	$800,000	Reasearchers will validate important three-dimensional aspects of the fuel pin modeling by using specialized numerical modeling techniques coupled with laboratory experiments to validate existing models for predicting fuel performance in light water reactors.	Document	NEAMS	FY2013
Collocation-Based Surrogate Models for Uncertainty Quantification and Validation of Coupled, Multiphysics Fuel Performance Simulation Tools	University of Michigan	$596,835	Reasearchers will provide the necessary high fidelity, coupled, multiphysics fuel performance simulator for computational modeling and develop surrogates which will accelerate and focus the validation of the coupled codes. This will be achieved by utilizing the high fidelity coupled fuel performance, thermal-hydraulics and neutronics codes BISON/STAR-CCM+/MPACT and an innovative collocation-based surrogate methodology.	Document	NEAMS	FY2013
Multi-Resolution In-Situ Testing and Mutliscale Simulation for Creep Damage Fatigue Damage Analysis of Alloy 617	Arizona State University	$800,000	This project will develop novel testing and experimentally validated prediction methodologies for micro-structural damage mechanisms of structural materials for advanced reactor systems. The investigations will focus on the characterization and testing of specific metal alloys, but the proposed testing and life-prediction methodologies are applicable to other structural materials as well.	Document	RCRD&D	FY2013
Novel High Temperature and Radiation Resistant Infrared Glasses and Optical Fibers for Sensing in Advanced Small Modular Reactors	Clemson University	$800,000	Clemson University, in partnership with the Iowa State University and the Pacific Northwest National Laboratory, will develop novel optical materials with improved heat and radiation exposure resistance in order to enable in-vessel fiber optic sensing for advanced Small Modular Reactors.	Document	RCRD&D	FY2013
Validation Data Acquisition in HTTF during PCC Events	George Washington University	$800,000	Reasearchers at the George Washington University and Oregon State University will collaborate with NASA Langley Research Center to measure flow velocities in a high temperature test facility. This work supports the development of very-high temperature reactors with passive safety systems.	Document	RCRD&D	FY2013
Advanced High Temperature Inspection Capabilities for Small Modular Reactors	Iowa State University	$790,822	The objective of this project is to develop non-destructive evaluation techniques for advanced small modular reactors. The research will provide key enabling inspection technologies needed to support the design and the reactor component performance validation process for advanced small modular reactors.	Document	RCRD&D	FY2013
Experimental and Computational Investigations of Plenum-to-Plenum Heat Transfer under Natural Circulation in a Prismatic Very High Temperature Reactor	Missouri University of Science and Technology	$799,999	Reasearchers will perform experimental and computational investigations to study heat transfer and natural circulation phenomena in very-high temperature reactors. The study will assist in the ability to predict and analyze passive safety systems.	Document	RCRD&D	FY2013
New Mechanistic Models of Creep-Fatigue Crack Growth Interactions for Advanced High Temperature Reactor Components	Oregon State University	$790,790	Reasearchers will create and validate a robust, multi-scale, numerical model to predict material degradation in nickel-based reactor alloys. If successful, this project will provide better numerical tools for reactor designers and greatly improve their capability to design against material failures for reactor alloys in the long term.	Document	RCRD&D	FY2013
Self-Powered Wireless Dual-mode Langasite Sensor for Pressure/Temperature Monitoring of Nuclear Reactors	State University of New York, Stony Brook	$800,000	This research will develop a novel self-powered wireless hybrid sensor that can accurately monitor both pressure and temperature using a single device without requiring external electricity, even in extreme harsh environments.	Document	RCRD&D	FY2013
Compact Heat Exchanger Design and Testing for Advanced Nuclear Reactors and Advanced Power Cycles	The Ohio State University	$800,000	The goal of this project is to investigate optimal heat exchanger designs for advanced reactors. The research will study the optimization of printed circuit heat exchangers for specific fluids under a variety of conditions as well as perform numerical modeling. Experiments will focus on thermal performance and heat stress during extreme conditions.	Document	RCRD&D	FY2013
Fundamental Understanding of Creep-Fatigue Interactions in 9Cr-1MoV Steel Welds	The Ohio State University	$798,000	This project will advance the state of knowledge and fundamental understanding of deforming materials and welds under loading conditions. Specifically, new integrated testing procedures will be evaluated and applied for conditions that are most detrimental to material stability leading to improved predictions of life expectancy for reactor steels and welds.	Document	RCRD&D	FY2013
Advanced Mechanistic 3D Spatial Modeling and Analysis Methods to Accurately Represent Nuclear Facility External Event Scenarios	The Ohio State University	$800,000	Reasearchers will develop three-dimensional characterization uncertainty analysis for commercial power plants. The project will involve combining experts from the fields of seismic structural modeling and advanced methods of risk assessment. This effort is expected to result in next generation tools that can be used for assessment of seismic risks.	Document	RCRD&D	FY2013
Tritium Mitigation/Control for Advanced Reactor Systems	The Ohio State University	$400,000	Reasearchers will develop a fluoride salt cooled high-temperature reactor featuring a specialized system to control tritium production. If successful, this will result in a significant reduction in size and cost in comparison to other reactor designs.	Document	RCRD&D	FY2013
A Pebble-Bed Breed and Burn Reactor	University of California, Berkeley	$400,000	Reasearchers will assess the feasibility of designing a type of metal cooled reactor able to establish and maintain operation when fueled with depleted uranium. If successful, this reactor will offer at least a 30-fold increase in the uranium ore utilization versus that achieved in contemporary light water reactors without the need for fuel reprocessing and recycling.	Document	RCRD&D	FY2013
Investigation of Thermal Aging Effects on the Evolution of Microstructure and Mechanical Properties of Cast Duplex Stainless Steels	University of Maryland, College Park	$799,966	This research will provide a better understanding of the microstructural evolution and simultaneous change in mechanical response during aging. The results of the research will provide data that can be used to estimate degraded mechanical properties for an 80-year service life of light water reactors.	Document	RCRD&D	FY2013
Model validation using CFD-grade experimental database for NGNP Reactor Cavity Cooling Systems with water and air	University of Michigan	$799,348	Reasearchers will use advanced innovative instrumentation to build a high-resolution experimental database and to use the novel experimental data to assess and further develop the predictive capabilities of computer codes for thermal hydraulics and computational fluid dynamics. The improved models developed by this project will also have the direct benefit of improving the predictive capability of the passive systems of third generation light water reactors and small modular reactor systems.	Document	RCRD&D	FY2013
Long-Term Prediction of Emissivity of Structural Material for High Temperature Reactor Systems	University of Missouri	$799,117	Reasearchers will study specific types of emissivity driven cooling from a variety of materials that are relevant to nuclear reactors. The research will provide a basis for numerical modeling to support reactor development.	Document	RCRD&D	FY2013
Advanced I&C for Fault-Tolerant Supervisory Control of Small Modular Reactors	University of Pittsburgh	$800,000	The purpose of this research is to develop advanced instrumentation and control techniques for supervisory control of advanced small modular reactors. This research supports the operational goals of small modular reactor concepts through the development of improved oversight and surveillance techniques.	Document	RCRD&D	FY2013
Corrosion of Structural Materials for Advanced Supercritical Carbon-Dioxide Brayton Cycle	University of Wisconsin-Madison	$798,672	Reasearchers will study a variety of materials for corrosion resistance under conditions that improve power conversion. In addition to studying the corrosion resistance of the materials, researchers will study the effect of additives to mitigate corrosion. Development of corrosion theories and modeling aimed at prediction of long-term corrosion will be the underlying theme throughout the project.	Document	RCRD&D	FY2013
Component and Technology Development for Advanced Liquid Metal Reactors	University of Wisconsin-Madison	$798,920	In support of liquid metal cooled reactors, the University of Wisconsin, Madison will evaluate advanced alloys and ceramics that come in contact with liquid metals. Additionally, a robust oxygen sensor and for use in liquid metals will be developed in order to better evaluate corrosion profiles in support of diagnostic testing.	Document	RCRD&D	FY2013
A New Paradigm for Understanding Multi-phase Ceramic Waste Form Performance	Clemson University	$800,000	Researchers will use advanced characterization tools to develop 3-D microstructural data that can be incorporated into computer-based simulations in order to predict the performance of waste forms. Materials system modeling will incorporate elemental release and the interconnected microstructural network of phases to better understand performance and degradation, which will accelerate waste form acceptance in repository settings.	Document	FCR&D	FY2014
Controlling Hexavalent Americium: A Centerpiece to a Compact Nuclear Fuel Cycle	Colorado School of Mines	$800,000	Researchers will develop and exploit the fundamental chemistry of Americium to enable an industrially viable means to co-recover the major and minor actinide elements from used nuclear fuel. The results would be a significant step forward in the development of aqueous separations approaches designed to recover the U-Am actinides based on the availability of the hexavalent oxidation state.	Document	FCR&D	FY2014
Zeolite Membranes for Krypton/Xenon Separation from Spent Nuclear Fuel Reprocessing Off-Gas	Georgia Institute of Technology	$400,000	Researchers will develop a high-performance, lower-cost zeolitic membrane process for Kr/Xe separations during spent nuclear fuel processing. Current separation methods are not considered economical and a membrane process would have relatively lower cost, equipment size, and ambient operating temperature. The process would form a sound basis for further development of this transformative separation technology for the nuclear fuel cycle.	Document	FCR&D	FY2014
Optimizing Polymer-Grafted Amidoxime-based Adsorbents for Uranium Uptake from Seawater	Georgia Institute of Technology	$399,999	Researchers will work to increase the adsorbent capacity and selectivity toward uranium by optimizing the adsorbent morphology, synthesis variables, and conditioning parameters and by investigating the rate-limiting variables through transport and reaction modeling. A novel adsorption/partition concept that has the potential to substantially increase the adsorbent capacity will be tested, making uranium from seawater extraction more economically viable.	Document	FCR&D	FY2014
Extraction of Uranium from Seawater: Design and Testing of a Symbiotic System	Massachusetts Institute of Technology	$400,000	Researchers will develop a seawater uranium extraction system that will work symbiotically with an offshore windmill by utilizing the structure, mooring and power of the windmill, while increasing the energy harvested by the installation. Uranium will be extracted by an adsorbent polymer belt, which will be cycled through the seawater and an elution plant located at the base of the windmill tower. Increasing the frequency of harvesting could overcome current economic barriers to seawater uranium extraction.	Document	FCR&D	FY2014
Imaging a Dry Storage Cask with Cosmic Ray Muons	Oregon State University	$799,871	Researchers will develop an imaging system to monitor the content of a dry storage cask with cosmic ray muons. A very large amount of plutonium under nuclear safeguards is contained in used fuel assemblies stored in dry storage casks. Muon imaging will allow a cost effective and reliable way to evaluate dry storage cask content and integrity before transport.	Document	FCR&D	FY2014
Apatite and sodalite based glass-bonded waste forms for immobilization of 129I and mixed halide radioactive wastes	Rutgers University	$800,000	Researchers will develop advanced and chemically durable waste forms for immobilizing 129I (aqueous based reprocessing of fuel) and mixed-halide wastes (molten-salt processing of fuel) by low temperature synthesis. Halide-containing sodalite and calcium phosphate-based apatite minerals will be synthesized, consolidated and tested for chemical durability. The project will provide needed baseline data for the development of advanced waste forms for immobilization of iodine and mixed-halide wastes.	Document	FCR&D	FY2014
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$350,000	Researchers will develop modeling tools supported by experiments for off-gas capture from future nuclear-fuel recycling facilities. Target species include tritium, iodine, krypton, and xenon. The models are intended to provide path forward recommendations to develop off-gas treatment adsorption processes. The project will contribute to the evaluation of options for environmentally acceptable recycle systems.	Document	FCR&D	FY2014
Development of high performance ODS alloys	Texas A&M University	$800,000	Researchers will study swelling, radiation hardening and changes in mechanical properties of ODS alloys to develop two sets of advanced ODS alloys. Two sets of first-round candidate alloys that have already undergone extensive development and testing will evaluate irradiation performance. The study will meet the need for high strength, radiation-tolerant cladding and core components that have enhanced resistance to void swelling.	Document	FCR&D	FY2014
Rare Earth Electrochemical Property Measurements and Phase Diagram Development in a Complex Molten Salt Mixture for Molten Salt Recycle	The Ohio State University	$800,000	Researchers will investigate rare earth (RE) properties in complex molten salt mixtures. In a molten salt recycle approach, the RE drawdown by electrolysis is a key step in which REs are separated from salt containing other fission products. Investigation of RE electrolysis must consider the electrochemical properties of the REs. We propose to conduct studies of detailed experiments and corresponding models to provide the physical properties and phase diagrams required to predict the performance of RE drawdown for processing complex molten salts.	Document	FCR&D	FY2014
Studies of Lanthanide Transport in Metallic Nuclear Fuels	The Ohio State University	$800,000	Researchers will study the redistribution of lanthanides and migration of lanthanides to the fuel surface. The mechanisms of lanthanide transport in metallic fuel based on the novel discovery of a Ôliquid-likeÕ transport mechanism will be studied analytically and experimentally. The project will develop a fundamental understanding of lanthanide fission product migration and redistribution in advanced metallic nuclear fuels, and theory and data to mitigate fuel-cladding chemical interactions.	Document	FCR&D	FY2014
Computational and Experimental Studies of Microstructure-Scale Porosity in Metallic Fuels for Improved Gas Swelling Behavior	University of Arkansas	$796,823	Researchers will study the microstructure of metallic uranium alloy fuels, and their resistance to densification, to minimize in-pile irradiation swelling through bimodal pore size distribution. The project will develop a predictive approach to design metallic fuel microstructures for optimal swelling resistance and fission gas retention.	Document	FCR&D	FY2014
Improved Hybrid Modeling of Spent Fuel Storage Facilities	University of California, Berkeley	$645,393	Researchers will develop a variance reduction method for computational transport that will improve the ability to design and operate monitoring systems for interim used fuel installations through enhanced modeling and simulation. This new tool will demonstrate that modeling calculations can be done more accurately in less time than with current tools and will perform studies characterizing how changes in material, cask configurations, and number of casks could impact monitoring systems.	Document	FCR&D	FY2014
Selective ligands for uranyl via combinatorial peptoid libraries: A synthetic, structural, thermodynamic and computational study	University of California, Berkeley	$400,000	Researchers will study how donor ligands bind to the uranyl ion, UO22+, with the longer-term goal of using this information to tackle selective recognition of uranyl in aqueous solution. The study will impact underlying approaches to controlling the behavior of uranium in these systems. The actinide separation technology could be used in several areas including uranium extraction from seawater, nuclear waste remediation and nuclear materials.	Document	FCR&D	FY2014
Combining Experiments and Simulations of Extraction Kinetics and Thermodynamics in Advanced Separation Processes for Used Nuclear Fuel	University of California, Irvine	$799,938	Researchers will study how the kinetics and thermodynamics of metal ion extraction in advanced separation processes for used nuclear fuel can be described by molecular dynamic (MD) simulations and how the simulations can be validated by experimental data. The project would have broad impacts on several separations processes including advanced TALSPEAK, ALSEP and GANEX by increasing the confidence and accuracy of computer modeling of metal ion extraction._	Document	FCR&D	FY2014
Effect of Metallic Li on the Behavior of Metals in Molten Salts	University of Nevada, Reno	$458,250	Researchers will identify the effect of metallic lithium on materials that are used in molten salt recycling. The study will try to understand how the presence of Li(0) in molten salts affects the degradation of alloys. Studying these changes will help accurately predict container material behavior and longevity.	Document	FCR&D	FY2014
Assessment of Corrosion Resistance of Promising Accident Tolerant Fuel Cladding under Reactor Conditions	University of Notre Dame	$800,000	Researchers will assess the corrosion behavior of accident tolerant fuel candidate iron-based alloys under normal LWR operating conditions consisting of high temperature, relevant water chemistry and irradiation. The assessment will produce data about possible irradiation-accelerated corrosion rates of iron-based alloys, and the mechanisms by which such corrosion rates are accelerated. The project will advance the selection of appropriate replacements for Zircaloy cladding.	Document	FCR&D	FY2014
Functionalized Porous Organic Polymers as Uranium Nano-Traps for Efficient Recovery of Uranium from Seawaterr	University of South Florida	$399,000	Researchers will develop functionalized porous organic polymers, or Ônano-trapsÕ for extraction of uranium from seawater. This technique allows for increased surface area and custom-designed pore size and chemistry to fit specific parameters. The adsorbent materials have high efficiency and effectiveness for uranium recovery from seawater, providing a potential supply for nuclear fuel.	Document	FCR&D	FY2014
Enhanced Accident-Tolerant Fuel Performance and Reliability for Aggressive iPWR/SMR Operation	University of Tennessee	$799,967	To develop a process that evaluates operational and safety performance of reactor-and-fuel combinations by integrating whole-core 3D neutronics with MOOSE/BISON fuel performance assessments via explicit time and space dependent fuel rod operational power histories. The project will be valuable in analyzing and evaluating accident tolerant fuel concepts and furthering the understanding of reactor physics and fuel performance aspects of key accident tolerant fuel concepts.	Document	FCR&D	FY2014
Nuclear Technology R&D Strategies in an Era of Energy Price Uncertainty	University of Texas, Austin	$799,112	Researchers will identify nuclear technology options that are competitive over a wide range of plausible future business environments. No single nuclear technology or business practice will be the best choice across all or even most future conditions. The study will focus on hybrid nuclear-fossil technologies, energy storage and conversion, which will result in an identification of nuclear strategies that can succeed under future market conditions.	Document	FCR&D	FY2014
Development and Optimization of Voltammetric Methods for Real Time Analysis of Electrorefiner Salt with High Concentrations of Actinides and Fission Products	University of Utah	$621,612	Researchers will develop an advanced voltammetry method to pursue the objective of real time monitoring of actinide concentrations in electrorefiner salt. This will include experimental measurement of key parameters such as activity coefficients and exchange current density. It will also involve simulation of voltammetry processes based on first principles. The project will allow for real time measurements that could support the commercialization of pyroprocessing.	Document	FCR&D	FY2014
Development of Self-Healing Zirconium-Silicide Coatings for Improved Performance of Zirconium-Alloy Fuel Cladding	University of Wisconsin, Madison	$798,621	Researchers will study the deposition of self-healing zirconium-silicide coatings on zirconium-alloy fuel cladding material to improve corrosion resistance under normal and accident conditions. Under these conditions, Zr-Si coating evolves into a highly protective functionally-graded multilayered system. The study will lead to improved performance of zirconium-alloy fuels._	Document	FCR&D	FY2014
Thermal Conductivity in Metallic Fuels	Virginia Polytechnic Institute and State University	$799,837	Researchers will calculate the thermal conductivity of metallic uranium and neptunium alloys, including the effects of noble gasses, using density functional theory. The experiments will validate the calculated effective thermal conductivity using the MARMOT code and by helping determine DFT simulation parameters. The study works to improve fuel lifetime by understanding its thermal behavior.	Document	FCR&D	FY2014
SiC-ODS Alloy Gradient Nanocomposites as Novel Cladding Materials	Virginia Polytechnic Institute and State University	$799,998	Researchers will combine nuclear nanomaterial design, processing, testing, and characterization efforts to develop revolutionary materials that can withstand neutron irradiation for long period of time using nanostructured SiC and oxide dispersion strengthened steel. The ultimate objective is to offer new cladding materials with increased corrosion resistance, strength, and creep resistance in both steady state and accident conditions.	Document	FCR&D	FY2014
Experimental Breeder Reactor II Benchmark Evaluation	Idaho State University	$400,000	Researchers will develop a benchmark evaluation of the Experimental Breeder Reactor II (EBR-II). During nearly 30 years of operation numerous experiments were conducted at EBR-II. The most significant of these experiments were conducted in 1986 demonstrating inherent safety features in loss of flow without reactor scram and loss of heat sink without reactor scram. Benchmark evaluation will be valuable for the reactor design efforts in the United States and South Korea.	Document	MSNE	FY2014
Integral full core multi-physics PWR benchmark with measured data	Massachusetts Institute of Technology	$400,000	Researchers will introduce BEAVRS, a new multi-cycle full-core Pressurized Water Reactor (PWR) depletion benchmark based on two operational cycles of a commercial nuclear power plant. This project aims at addressing the uncertainty quantification of the measured data and on making this benchmark a true non-proprietary international benchmark for the validation of high-fidelity multi-physics computational tools.	Document	MSNE	FY2014
Benchmark Evaluation of PROTEUS Gas-Cooled Reactor Experiments	University of Florida	$400,000	Researchers will create International Reactor Physics Experiment Evaluation Project (IRPhEP) benchmarks using data from 1970s experiments of the neutronics of gas-cooled fast reactor (GCFR) designs investigated in the PROTEUS reactor. The GCFR-PROTEUS experiments fill a gap in current integral benchmark data. These experiments can provide validation of computational models and nuclear data for next generation reactors.	Document	MSNE	FY2014
An Investigation To Establish Multiphysical Property Dataset Of Nuclear Materials Based On In-Situ Observations And Measurements	Purdue University	$800,000	Researchers will create an in-situ measurement based experimental approach to develop experimental validation dataset for NEAMS based code validation. Particular emphasis is on supplying data set for multiphysics simulations in extreme conditions as a function of material microstructure.	Document	NEAMS	FY2014
Experimental Validation of UO2 Microstructural Evolutions for NEAMS tool MARMOT	University of Florida	$798,000	Researchers will experimentally validate MARMOT for predicting the microstructural evolutions of UO2 oxide fuel under the driving forces of high temperatures and large temperature gradient in reactors. By performing the experiments and simulations simultaneously using precisely defined initial conditions, the experiment data will provide direct benchmarking of the MARMOT code.	Document	NEAMS	FY2014
High-resolution time-resolved experiments on mixing and entrainment of buoyant jets in stratified environments	University of Michigan	$799,983	Researchers will study high spatial and time-resolution experimental data of the fluid dynamics phenomena of flow jets interacting with a stratified layer. The issue plays an important role in the safety of several reactor designs, including sodium-cooled reactors. The data addresses the NEAMS needs for the validation of high fidelity computational fluid dynamics methodologies.	Document	NEAMS	FY2014
Fundamental study of key issues related to advanced S-CO2 Brayton Cycle: prototypic HX development and Cavitation	Georgia Institute of Technology	$799,000	Researchers will study scientific and operational issues pertinent to compact heat exchanger systems and turbo-machinery. The project will work to resolve issues with the fabrication of diffusion bonded compact heat exchangers, alternate heat exchange technology for recuperators, and resolution of issues with cavitation and fluid instabilities.	Document	RCRD&D	FY2014
Advanced Models for Nondestructive Evaluation of Aging Nuclear Power Plant Cables	Iowa State University	$787,291	Researchers will develop advanced models that relate environmentally induced microstructural and chemical changes in cable insulation polymers to their macroscopic electrical parameters. These parameters will be measured and modeled over a wide range of the electromagnetic spectrum, covering several potential nondestructive evaluation techniques, enabling identification of the most sensitive techniques for future development.	Document	RCRD&D	FY2014
Development of Novel Functionally Graded Transition Joints for Improving the Creep Strength of Dissimilar Metal Welds in Nuclear Applications	Lehigh University	$800,000	Researchers will develop graded transition joints and improved creep life models for increasing the life of dissimilar metal welds (DMWs) in nuclear reactors. The research represents the first application of functionally graded material concepts for solving the problem of DMW failures through an integrated approach of additive manufacturing, modeling, microstructural characterization, and advanced strain-sensing techniques.	Document	RCRD&D	FY2014
Feasibility Assessment of a Micro Modular Reactor (MMR)	North Carolina State University	$400,000	Researchers will develop an innovative compact reactor concept that integrates power production, power conversion and electricity generation in a single unit: the Micro Modular Reactor (MMR). It is designed to be absolutely melt-down proof (MDP) under all circumstances including complete loss of coolant scenarios with no possible release of radioactive material, to have a cycle length of greater than 10 years, and to be highly proliferation resistant.	Document	RCRD&D	FY2014
Scaling Studies for Advanced Gas Reactor Concepts	Oregon State University	$681,834	Researchers will expand the utilization of the Oregon State University High Temperature Test Facility (HTTF) to validate a broader range of advanced high temperature reactors and events. The facility will be revised to add a detailed scaling analysis of additional gas reactor concepts including advanced gas-cooled, molten salt, and sodium cooled reactors.	Document	RCRD&D	FY2014
Fluid Stratification Separate Effects Analysis, Testing and Benchmarking	Oregon State University	$800,000	Researchers will study fluid stratification in high temperature gas reactors. Coolant stratification is the result of incomplete mixing of one or more fluids, leading to a density gradient, which may or may not dissipate under diffusive or convective effects. This combined analytical and experimental project seeks to investigate stratification driven by diffusive and convective mechanisms and is expected to yield insight into this phenomenon.	Document	RCRD&D	FY2014
Probabilistic Economic Valuation of Safety Margin Management Analysis	Oregon State University	$795,364	Researchers will use RAVEN and develop a companion software package to facilitate economic analysis of safety margins. The project is a proof of concept that will use techniques to examine the cost of improving safety margins vs. the risk of accidents from not improving safety margins. This analysis can be used to evaluate the economic viability of various plant upgrades.	Document	RCRD&D	FY2014
Novel Dissimilar Joints Between Alloy 800H and 2.25%Cr and 1%Mo Steel	Pennsylvania State University	$800,000	Researchers will fabricate and test dissimilar metal joints between a nickel base alloy and a steel with gradual variations of chemical composition, microstructure and properties in a manner that reduces abrupt thermal expansion mismatch and the resulting residual stresses. Data on structure and properties will serve as valuable inputs for the initiation of an ASME code case.	Document	RCRD&D	FY2014
Multi-Phase Model Development to Assess RCIC System Capabilities under Severe Accident Conditions	Texas A&M University	$564,246	Researchers will develop physics-based models of the Reactor Core Isolation Cooling (RCIC) System and incorporating them into a multi-phase code for validation. The project will tackle the current major challenges in RCIC System analysis and enable evaluation of two-phase thermodynamic aspects.	Document	RCRD&D	FY2014
Experimental Investigation and CFD Analysis of Steam Ingress Accidents in HTGRs	The Ohio State University	$800,000	Researchers will study the steam ingress scenario for HTGRs. The study will investigate thermal-hydraulic behavior and graphite oxidation of stream ingress phenomena to validate predictive CFD models. This work will resolve concerns about possible steam generator tube ruptures in a HTGR He-Steam Rankine cycle.	Document	RCRD&D	FY2014
Coiled Tube Gas Heaters For Nuclear Gas-Brayton Power Conversion	University of California, Berkeley	$800,000	Researchers will develop heat exchangers for Brayton-cycle power conversion in reactors using sodium, NaK, or salt as intermediate coolants. The proposed coiled tube gas heaters (CTGHs) are expected to have excellent power density, thermal shock/creep, in-service inspection, and reparability characteristics.	Document	RCRD&D	FY2014
Fundamental Studies of Irradiation-Induced Modifications in Microstructural Evolution and Mechanical Properties of Advanced Alloys	University of Illinois, Urbana-Champaign	$800,000	Researchers will develop and test a mechanism for predicting neutron irradiation performance for optimized Grade 92 and Alloy 709 for applications in advanced reactor systems. The work will employ ion irradiations and available information from neutron irradiations of related alloys to develop a basis for predicting the neutron irradiation performance of the optimized alloys.	Document	RCRD&D	FY2014
Integrated Computational and Experimental Study of Radiation Damage Effects in Grade 92 Steel and Alloy 709	University of Tennessee	$800,000	Researchers will develop a mechanistic understanding and predictive models of irradiation-induced microstructural evolution and resulting mechanical properties in optimized ferritic-martensitic Grade 92 steel and austenitic alloy 709 using multiscale simulations coupled with rigorous experimental validation. The project will provide insights into the correlation between ion irradiation and fast neutron damage.	Document	RCRD&D	FY2014
Meta-Level Design Guidance and Operator Performance Measures for Hybrid Control Rooms	Vanderbilt University	$799,869	Researchers will apply human factors engineering methods and relevant expertise from non-nuclear high-risk high-consequence domains toward the measurement of operator performance in analog, digital, and hybrid main control rooms. Performance measures will be developed for evaluating the situation awareness and decision-making proficiencies to support the transition to digital or hybrid control room displays.	Document	RCRD&D	FY2014

FY 2013 Research and Development Awards

The Department of Energy is awarding $42 million in support of the Nuclear Energy University Programs for 61 nuclear energy research and development projects focused on developing innovative solutions in the following fields: Fuel Cycle Technologies; Reactor Concepts Research; Development & Demonstration; and Nuclear Energy Advanced Modeling & Simulation.

These projects, selected for negotiation of award, are led by 38 American universities and colleges in 28 states and the District of Columbia. Other universities, industry leaders and National Laboratories will serve as collaborators and research partners.

A complete list of R&D projects with their associated abstracts is available below.

Title	Institution	Estimated Funding*	Project Description	Abstract	Project Type	Fiscal Year
Neutron Damage and MAX Phase Ternary Compounds	Drexel University			Document	IIR	FY2009
Atomistic Calculations of the Effect of Minor Actinides on Thermodynamic and Kinetic Properties of UO2+x	Georgia Institute of Technology			Document	IIR	FY2009
Maximum Fuel Utilization in Fast Reactors without Chemical Reprocessing	University of California, Berkeley			Document	IIR	FY2009
Developing a High Thermal Conductivity Fuel with Silicon Carbide Additives	University of Florida			Document	IIR	FY2009
Fabrication of Tungsten-Rhenium Cladding Materials via Spark Plasma Sintering for Ultra High Temperature Reactor Applications	University of Idaho			Document	IIR	FY2009
Ionic Liquid and Supercritical Fluid Hyphenated Techniques for Dissolution and Separation of Lanthanides, Actinides, and Fission Products	University of Idaho			Document	IIR	FY2009
Improved Fission Neutron Data Base for Active Interrogation of Actinides	University of Michigan			Document	IIR	FY2009
Utilization of Methacrylates and Polymer Matrices for the Synthesis of Ion Specific Resins	University of Nevada, Las Vegas			Document	IIR	FY2009
Improved LWR Cladding Performance by EPD Surface Modification Technique	University of Wisconsin, Madison			Document	IIR	FY2009
Advanced Models of LWR Pressure Vessel Embrittlement for Low Flux-High Fluence Conditions	University of California, Santa Barbara			Document	LWRS	FY2009
Irradiation Creep in Graphite	Boise State University			Document	NGNP	FY2009
Modeling the Stress Strain Relationships and Predicting Failure Probabilities For Graphite Core Components	Cleveland State University			Document	NGNP	FY2009
TRISO-Coated Fuel Durability Under Extreme Conditions	Colorado School of Mines			Document	NGNP	FY2009
An Innovative and Advanced Coupled Neutron Transport and Thermal Hydraulic Method (Tool) for the Design, Analysis and Optimization of VHTR/NGNP Prismatic Reactors	Georgia Institute of Technology			Document	NGNP	FY2009
Removal of 14C from Irradiated Graphite for Graphite Recycle and Waste Volume Reduction	Idaho State University			Document	NGNP	FY2009
Millimeter-Wave Thermal Analysis Development and Application to Gen IV Reactor Materials	Massachusetts Institute of Technology			Document	NGNP	FY2009
Accurate Development of Thermal Neutron Scattering Cross Section Libraries	North Carolina State University			Document	NGNP	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
Understanding Creep Mechanisms in Graphite with Experiments, Multiscale Simulations, and Modeling	North Carolina State University			Document	NGNP	FY2009
Simulations of the Thermodynamic and Diffusion Properties of Actinide Oxide Fuel Materials	University of Michigan			Document	AFCI	FY2009
Verification & Validation of High-Order Short-Characteristics-Based Deterministic Transport Methodology on Unstructured Grids	North Carolina State University			Document	NGNP	FY2009
Adsorptive Separation and Sequestration of Krypton, I and C14 on Diamond Nanoparticles	University of Missouri, Columbia			Document	AFCI	FY2009
Microscale Heat Conduction Models and Doppler Feedback	North Carolina State University			Document	NGNP	FY2009
Fundamental Understanding of Ambient and High-Temperature Plasticity Phenomena in Structural Materials in Advanced Reactors	Georgia Institute of Technology			Document	AFCI	FY2009
Development of Alternative Technetium Waste Forms	University of Nevada, Las Vegas			Document	AFCI	FY2009
Optimizing Neutron Thermal Scattering Effects in Very High Temperature Reactors	North Carolina State University			Document	NGNP	FY2009
Advanced Elastic/Inelastic Nuclear Data Development Project	Idaho State University			Document	AFCI	FY2009
Heterogeneous Recycling in Fast Reactors	Massachusetts Institute of Technology			Document	AFCI	FY2009
Quantification of UV-Visible and Laser Spectroscopic Techniques for Materials Accountability and Process Control	University of Nevada, Las Vegas			Document	AFCI	FY2009
Multiaxial Creep-Fatigue and CreepRatcheting Failures of Grade 91 and Haynes 230 Alloys Toward Addressing Design Issues of Gen IV Nuclear Power Plants	North Carolina State University			Document	NGNP	FY2009
Thermodynamic Development of Corrosion Rate Modeling in Iron Phosphate Glasses	Missouri University of Science and Technology			Document	AFCI	FY2009
Development of Subspace-Based Hybrid Monte Carlo-Deterministic Algorithms for Reactor Physics Calculations	North Carolina State University			Document	AFCI	FY2009
High-Fidelity Space-Time Adaptive Multiphysics Simulations in Nuclear Engineering	University of Nevada, Reno			Document	AFCI	FY2009
Improvements to Nuclear Data and Its Uncertainties by Theoretical Modeling	Rensselaer Polytechnic Institute			Document	AFCI	FY2009
Investigation of Countercurrent Helium-air Flows in Air-ingress Accidents for VHTRs	Ohio State University			Document	NGNP	FY2009
Sharp Interface Tracking in Rotating Microflows of Solvent Extraction	State University of New York at Stony Brook			Document	AFCI	FY2009
Bulk Nanostructured FCC Steels with Enhanced Radiation Tolerance	Texas A&M University			Document	AFCI	FY2009
Simulations of Failure via Three-Dimensional Cracking in Fuel Cladding for Advanced Nuclear Fuels	University of Texas, Dallas			Document	AFCI	FY2009
Testing of Performance of Optical Fibers Under Irradiation in Intense Radiation Fields, When Subjected to Very High Temperatures	Ohio State University			Document	NGNP	FY2009
Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels	Texas A&M University			Document	AFCI	FY2009
SiC Schottky Diode Detectors for Measurement of Actinide Concentrations from Alpha Activities in Molten Salt Electrolyte	The Ohio State University			Document	AFCI	FY2009
Computational Design of Advanced Nuclear Fuels	University of California, Davis			Document	AFCI	FY2009
Advanced Mesh-Enabled Monte Carlo Capability for Multi-Physics Reactor Analysis	University of Wisconsin, Madison			Document	AFCI	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
A Distributed Fiber Optic Sensor Network for Online 3-D Temperature and Neutron Fluence Mapping in a VHTR Environment	Texas A&M University			Document	NGNP	FY2009
Ab Initio Enhanced Calphad Modeling of Actinide Rich Nuclear Fuels	University of Wisconsin, Madison			Document	AFCI	FY2009
Investigation on the Core Bypass Flow in a Very High Temperature Reactor	Texas A&M University			Document	NGNP	FY2009
Development of Diffusion Barrier Coatings and Deposition Technologies for Mitigating Fuel Cladding Chemical Interactions (FCCI)	University of Wisconsin, Madison			Document	AFCI	FY2009
CFD Model Development and Validation for High Temperature Gas Cooled Reactor Cavity Cooling System (RCCS) Applications	Texas A&M University			Document	NGNP	FY2009
Thermal Properties of LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin, Madison			Document	AFCI	FY2009
Study of Air ingress across the duct during the accident conditions	Texas A&M University			Document	NGNP	FY2009
Verification of the CENTRM Module for Adaptation of the SCALE Code to NGNP Prismatic and PBR Core Designs	University of Arizona			Document	NGNP	FY2009
Integral and Separate Effects Tests for Thermal Hydraulics Code Validation for Liquid-Salt Cooled Nuclear Reactors	University of California, Berkeley			Document	NGNP	FY2009
Mechanisms Governing the Creep Behavior of High Temperature Alloys for Generation IV Nuclear Energy Systems	University of Cincinnati			Document	NGNP	FY2009
ALD Produced B2O3, Al2O3 and TiO2 Coatings on Gd2O3 Burnable Poison Nanoparticles	University of Colorado, Boulder			Document	NGNP	FY2009
Experimental Study and Computational Simulations of Key Pebble Bed Thermomechanics Issues for Design and Safety	University of Idaho			Document	NGNP	FY2009
Prediction and Monitoring Systems of Creep-Fracture Behavior of 9Cr-1Mo Steels for Reactor Pressure Vessels	University of Idaho			Document	NGNP	FY2009
Understanding Fundamental Material Degradation Processes in High Temperature Aggressive Chemomechanical Environments	University of Illinois, Urbana-Champaign			Document	NGNP	FY2009
Multi-Scale Multi-physics Methods Development for the Calculation of Hot-Spots in the NGNP	University of Michigan			Document	NGNP	FY2009
Corrosion and Creep of Candidate Alloys in High Temperature Helium and Steam Environments for the NGNP	University of Michigan			Document	NGNP	FY2009
Creation of a Full-Core HTR Benchmark with the Fort St. Vrain Initial Core and Validation of the DHF Method with Helios for NGNP Configurations	University of Michigan			Document	NGNP	FY2009
Fission Product Sorptivity in Graphite	University of Missouri, Columbia			Document	NGNP	FY2009
Identifying and Understanding Environment-Induced Crack Propagation Behavior in Ni-Based Superalloy INCONEL 617	University of Nevada, Las Vegas			Document	NGNP	FY2009
Graphite Oxidation Simulation in HTR Accident Conditions	University of New Mexico			Document	NGNP	FY2009
Non Destructive Thermal Analysis and In Situ Investigation of Creep Mechanism of Graphite and Ceramic Composites using Phase-sensitive THz Imaging & Nonlinear Resonant Ultrasonic Spectroscopy	University of Rochester			Document	NGNP	FY2009
Tritium Sequestration in Gen IV NGNP Gas Stream via Proton Conducting Ceramic Pumps	University of South Carolina			Document	NGNP	FY2009
Materials, Turbomachinery and Heat Exchangers for Supercritical CO2 Systems	University of Wisconsin, Madison			Document	NGNP	FY2009
Experimental Studies of NGNP Reactor Cavity Cooling System with Water	University of Wisconsin, Madison			Document	NGNP	FY2009
Assessment of Embrittlement of VHTR Structural Alloys in Impure Helium Environments	University of Wisconsin, Madison			Document	NGNP	FY2009
Modeling Fission Product Sorption in Graphite Structures	University of Wisconsin, Madison			Document	NGNP	FY2009
Liquid Salt Heat Exchanger Technology for VHTR Based Applications	University of Wisconsin, Madison			Document	NGNP	FY2009
Effect of Post-Weld Heat Treatment on Creep Rupture Properties of Grade 91 Steel Heavy Section Welds	Utah State University			Document	NGNP	FY2009
Alpha Radiolysis of Nuclear Solvent Extraction Ligands used for An(III) and Ln(III) Separations	California State University, Long Beach	$1,390,252		Document	FCR&D	FY2010
Predictive Maturity of Multi-Scale Simulation Models for Fuel Performance	Clemson University	$614,690		Document	FCR&D	FY2010
Freeze-casting as a Novel Manufacturing Process for Fast Reactor Fuels	Drexel University	$1,149,327		Document	FCR&D	FY2010
Fuel Performance Experiments on the Atomistic Level, Studying Fuel Through Engineered Single Crystal UO2	Idaho State University	$650,000		Document	FCR&D	FY2010
Development of A Self Biased High Efficiency Solid-State Neutron Detector for MPACT Applications	Rensselaer Polytechnic Institute	$810,141		Document	FCR&D	FY2010
Development of a Innovative High Thermal Conductivity UO 2 Ceramic Composites Fuel Pellets with Carbon Nano-Tubes Using Spark Plasma Sintering	University of Florida	$894,042		Document	FCR&D	FY2010
Exploration and Modeling of Structural Changes in Waste Glass under Corrosion	Pennsylvania State University	$1,377,444		Document	FCR&D	FY2010
Evaluation of materials for interim storage of spent fuel for more than 100 years	University of Michigan	$931,603		Document	FCR&D	FY2010
Implementation of On-the-Fly Doppler Broadening in MCNP5 for Multiphysics Simulation of Nuclear Reactors	University of Michigan	$406,712		Document	FCR&D	FY2010
Methods and tools to allow molecular flow simulations to be coupled to higher level continuum descriptions of flows in porous/fractured media and aerosol/dust dynamics	University of Missouri-Columbi	$541,286		Document	FCR&D	FY2010
Characterization and Modeling of Materials for Kr-Xe Separations	University of Nevada-Las Vegas	$989,800		Document	FCR&D	FY2010
Modeling Solute Thermokinetics in LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin-Madison	$616,073		Document	FCR&D	FY2010
Advanced Aqueous Separation Systems for Actinide Partitioning: Develop Fundamental Understanding of An(III)/Ln(III) Separation	Washington State University	$1,451,784		Document	FCR&D	FY2010
Consistent Multigroup Theory Enabling Accurate Coarse-Group Simulation of GenIV Reactors	Georgia Institute of Technology	$1,046,277		Document	GEN IV	FY2010
Studies of Deteriorated Heat Transfer in Prismatic Cores Stemming from Irradiation-Induced Geometry Distortion	Idaho State University	$1,287,921		Document	GEN IV	FY2010
Carbide Coatings for Nickel Alloys, Graphite, and Carbon/Carbon Composites to be Used in Fluoride Salt Valves	Johns Hopkins University	$1,183,239		Document	GEN IV	FY2010
Design, Testing, and Modeling of the Direct Reactor Auxiliary Cooling System for AHTRs	Ohio State University	$1,366,627		Document	GEN IV	FY2010
Monitoring microstructural evolution of Alloy 617 with nonlinear acoustics for remaining useful life prediction; multiaxial creep-fatigue and creep-ratcheting	Pennsylvania State University	$1,000,000		Document	GEN IV	FY2010
Development and Validation of Multidimensional Models of Supercritical CO 2 Energy Conversion Systems for Nuclear Power Reactors	Rensselaer Polytechnic Institute	$475,005		Document	GEN IV	FY2010
Multiscale Concrete Modeling for Aging Degradation	Mississippi State University	$345,941		Document	LWRS	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term and Elevated Temperature Irradiation: Modeling and Experimental Investigation	University of California-Berkeley	$1,320,667		Document	GEN IV	FY2010
Development of an advanced computational fluid dynamics technology for the next-generation nuclear reactor system analysis and safety margin characterization code	North Carolina State University	$418,199		Document	LWRS	FY2010
Development of Barrier Layers for the Protection of Candidate Alloys in the VHTR	University of California-Santa Barbara	$995,232		Document	GEN IV	FY2010
Precursor Derived Nanostructured Si-C-X Materials for Nuclear Applications	University of Washington	$899,518		Document	MRIIR	FY2010
Investigation of a Novel NDE Method for Monitoring Thermo-Mechanical Damage and Microstructure Evolution in Ferritic-Martensitic Steels for Generation IV Nuclear Energy Systems	University of Cincinnati	$833,109		Document	GEN IV	FY2010
Development and Testing of an Open-Loop Oscillator for Small Reactivity Worth Samples	Idaho State University	$597,252		Document	MRIIR	FY2010
Fission Product Transport in TRISO Particle Layers under Operating and Off-Normal Conditions	University of Michigan	$966,581		Document	GEN IV	FY2010
Understanding the Irradiation Behavior of Zirconium Carbide	Pennsylvania State University	$870,613		Document	MRIIR	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term Irradiation at Elevated Temperature: Critical Experiments	University of Michigan	$1,181,379		Document	GEN IV	FY2010
Modeling investigation of the stability and irradiation-induced evolution of nanoscale precipitates in advanced structural materials	University of Tennessee-Knoxville	$380,653		Document	MRIIR	FY2010
Three-dimensional NDE of VHTR Core Components via Simulation-based Testing	University of Minnesota	$1,366,163		Document	GEN IV	FY2010
Investigation of Laser Shock Peening for Enhancing Fatigue and Stress Corrosion Cracking Resistance of Nuclear Energy Materials	University of Cincinnati	$1,242,019		Document	MRIIR	FY2010
Failure Predictions for VHTR Core Components using a Probabilistic Continuum Damage Mechanics Model	University of Minnesota	$854,542		Document	GEN IV	FY2010
Irradiation Accelerated Corrosion of Reactor Core Materials	University of Michigan	$798,943		Document	MRIIR	FY2010
Development of a Scanning Microscale Fast Neutron Irradiation Platform for Examining the Correlation Between Local Neutron Damage and Graphite Microstructure	University of Missouri-Columbia	$703,064		Document	GEN IV	FY2010
Study of Interfacial Interactions using Thin Film Surface Modification: Radiation and Oxidation Effects in Materials	University of Wisconsin-Madison	$538,032		Document	MRIIR	FY2010
Development of Thermal Transient Flow Rate Sensors for High Temperature, Irradiation, Corrosive Environment	University of Nevada-Las Vegas	$451,269		Document	GEN IV	FY2010
Novel Engineered Refractory Materials for Advanced Reactor Applications	North Carolina State University	$1,129,304		Document	MRIIR	FY2010
Novel Methods of Tritium Sequestration: High Temperature Gettering and Separation Membrane Materials Discovery for Nuclear Energy Systems	University of South Carolina	$1,366,626		Document	GEN IV	FY2010
Heat Transfer Salts for Nuclear Reactor Systems - Chemistry Control, Corrosion Mitigation, and Modeling	University of Wisconsin-Madison	$1,352,040		Document	GEN IV	FY2010
Pulsed Magnetic Welding for Advanced Core and Cladding Steels	University of Wisconsin-Madison	$525,206		Document	GEN IV	FY2010
Corrosion in Supercritical Carbon Dioxide: Materials, Environmental Purity, Surface Treatments, and Flow Issues	University of Wisconsin-Madison	$651,447		Document	GEN IV	FY2010
Quantification of Cation Sorption to Engineered Barrier Materials Under Extreme Conditions	Clemson University	$1,171,380		Document	FCR&D	FY2011
In-Pile Instrumentation Multi-Parameter System Utilizing Photonic Fibers and Nanovision	Idaho State University	$1,199,990		Document	FCR&D	FY2011
Development of Plasmonically Cloaked Nanoparticles	Idaho State University	$800,000		Document	FCR&D	FY2011
Fission Product Transmutation in Mixed Radiation Fields	Idaho State University	$800,000		Document	FCR&D	FY2011
Life Prediction of Spent Fuel Storage Canister Material	Massachusetts Institute of Technology	$899,826		Document	FCR&D	FY2011
Active Interrogation using Photofission Technique for Nuclear Materials Control and Accountability	Oregon State University	$900,000		Document	FCR&D	FY2011
Anisotropic Azimuthal Power and Temperature Distribution on Fuel Rod: Impact of Hydride Distribution	Pennsylvania State University	$631,956		Document	FCR&D	FY2011
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$1,000,000		Document	FCR&D	FY2011
Recovery of Uranium from Seawater: Preparation and Development of Polymer-Supported Extractants	City College of New York, Hunter	$363,716		Document	MSTR	FY2011
Microemulsions and Aggregation Formation in Extraction Processes for Used Nuclear Fuel: Thermodynamics and Structural Studies	University of California, Irvine	$1,000,000		Document	FCR&D	FY2011
One-Dimensional Nanostructures for Neutron Detection	North Carolina State University	$455,629		Document	MSTR	FY2011
Optimized Processing Fabrication Paths for Larger Heats of Nanostructured Ferritic Alloys	University of California, Santa Barbara	$1,000,000		Document	FCR&D	FY2011
Feasibility and Safety Assessment for Advanced Reactor Concepts Using Vented Fuel	Oregon State University	$600,000		Document	MSTR	FY2011
Basic Physics Data: Measurement of Neutron Multiplicity from Induced Fission	University of Michigan	$973,364		Document	FCR&D	FY2011
Development of an Efficient Meso-Scale Multi-Phase Flow Solver in Nuclear Applications	City College of New York	$505,858		Document	NEAMS	FY2011
High Temperature Transducers for Online Monitoring of Microstructure Evolution	Pennsylvania State University	$455,628		Document	MSTR	FY2011
Radionuclide Incorporation and Long Term Performance of Apatite Waste Forms	University of Michigan	$862,500		Document	FCR&D	FY2011
Multiscale Modeling and Uncertainty Quantification for Nuclear Fuel Performance	Colorado State University	$1,098,250		Document	NEAMS	FY2011
Laser-Arc Hybrid Welding of Thick Section Ni-base Alloys- Advanced Modeling and Experiments	Pennsylvania State University	$536,117		Document	MSTR	FY2011
Actinide Foil Production for MPACT Research	University of Nevada-Las Vegas	$156,897		Document	FCR&D	FY2011
Fundamental Studies of the Role of Grain Boundaries on Uniform Corrosion of Advanced Nuclear Reactor Materials	Drexel University	$1,098,250		Document	NEAMS	FY2011
Correlates of Sensitive Technologies	Texas A&M University	$509,467		Document	MSTR	FY2011
Enriched Boron-Doped Amorphous Selenium Based Position-Sensitive Solid-State Thermal Neutron Detector for MPACT Applications	University of South Carolina	$1,000,000		Document	FCR&D	FY2011
Phenomena-based Uncertainty Quantification in Predictive Coupled-Physics Reactor Simulations	Texas A&M University	$1,098,250		Document	NEAMS	FY2011
Improved Safety Margin Characterization of Risk from Loss of Offsite Power	Texas A&M University	$600,000		Document	MSTR	FY2011
Development of Advanced High Uranium Density Fuels for Light Water Reactors	University of Wisconsin-Madison	$1,000,000		Document	FCR&D	FY2011
Characterization of Modeling of Grain Boundary Chemistry Evolution in Ferritic Steels Under Irradiation	University of Michigan	$1,098,250		Document	NEAMS	FY2011
Diffusion, Thermal Properties and chemical Compatibilities of Select MAX Phases with Materials for Advanced Nuclear Systems	Drexel University	$535,927		Document	NEET	FY2011
A High Temperature-Tolerant and Radiation-Resistant In-Core Neutron Sensor for Advanced Reactors	The Ohio State University	$455,629		Document	MSTR	FY2011
Developing the User Experience for a Next Generation Nuclear Fuel Cycle Simulator	University of Wisconsin-Madison	$1,200,000		Document	FCR&D	FY2011
Development of Multiscale Materials Modeling Techniques and Coarse-Graining Strategies for Predicting Materials Degradation in Extreme Irradiation Environments	University of Tennessee, Knoxville	$750,000		Document	NEAMS	FY2011
A New Light Weight Structural Material for Nuclear Structures	North Carolina State University	$399,490		Document	NEET	FY2011
Pathway Aggregation in the Risk Assessment of Proliferation Resistance and Physical Protection (PR&PP) of Nuclear Energy Systems	The Ohio State University	$534,471		Document	MSTR	FY2011
Experimental Investigation of Convection and Heat Transfer in the Reactor Core for a VHTR	City College of New York	$1,118,856		Document	RCRD&D	FY2011
Preparation of High Purity, High Molecular-Weight Chitin from Ionic Liquids for Use as an Adsorbate for the Extraction of Uranium from Seawater	University of Alabama	$338,260		Document	MSTR	FY2011
Graphite Microstructural Characterization Using Time-Domain and Correlation-Based Ultrasonics	Johns Hopkins University	$1,199,997		Document	RCRD&D	FY2011
Selectivity in Ligand Binding to Uranyl Compounds: A Synthetic, Structural, Thermodynamic and Computational Study	University of California-Berkeley	$500,000		Document	MSTR	FY2011
Methodology Development for Passive Component Reliability Modeling in a Multi-Physics Simulation Environment	The Ohio State University	$533,457		Document	RCRD&D	FY2011
Development of Seismic Isolation Systems Using Periodic Materials	University of Houston	$538,154		Document	MSTR	FY2011
Pebble Fuel Handling and Reactivity Control for Salt-Cooled High Temperature Reactors	University of California, Berkeley	$612,721		Document	RCRD&D	FY2011
Innovative Elution Processes for Recovering Uranium from Seawater	University of Idaho	$400,000		Document	MSTR	FY2011
Self-Sustaining Thorium Boiling Water Reactors	University of California, Berkeley	$1,145,932		Document	RCRD&D	FY2011
Development of Austenitic ODS Strengthened Alloys for Very High Temperature Applications	University of Illinois-Urbana Champaign	$538,154		Document	MSTR	FY2011
High Fluency Low Flux Embrittlement Models of LWR Reactor Pressure Vessel Embrittlement and a Supporting Database from the UCSB ATR-2 Irradiation Experiment	University of California, Santa Barbara	$1,199,607		Document	RCRD&D	FY2011
Enhancement of the Extraction of the Uranium from Seawater	University of Maryland	$400,000		Document	MSTR	FY2011
A Research Program for Fission Product/Dust Transport in HTGR's	University of Missouri-Columbia	$1,157,367		Document	RCRD&D	FY2011
Transient Safety Analysis of Fast Spectrum TRU Burning LWR with Internal Blankets	University of Michigan	$599,475		Document	MSTR	FY2011
Development and Validation of a Lifecycle-based Prognostics Architecture with Test Bed Validation	University of Tennessee, Knoxville	$846,315		Document	RCRD&D	FY2011
Development of Novel Sorbents for Uranium Extraction from Seawater	University of North Carolina, Chapel Hill	$400,000		Document	MSTR	FY2011
In-situ Condition Monitoring of Components in Small Modular Reactors Using Process and Electrical Signature Analysis	University of Tennessee, Knoxville	$650,000		Document	RCRD&D	FY2011
Radiation Behavior of High-Entropy Alloys for Advanced Reactors	University of Tennessee, Knoxville	$538,159		Document	MSTR	FY2011
Technical Development for S-CO2 Advanced Energy Conversion	University of Wisconsin	$815,000		Document	RCRD&D	FY2011
Rapid Computer Aided Ligand Design and Screening of Precious Metal Extractants from TRUEX Raffinate with Experimental Validation	Washington State University	$500,000		Document	MSTR	FY2011
Ag Transport Through Non-Irradiated and Irradiated SiC	University of Wisconsin-Madison	$1,055,456		Document	RCRD&D	FY2011
Critical Heat Flux Phenomena at High Pressure and Low Mass Fluxes: Tests and Models	University of Wisconsin-Madison	$1,199,781		Document	RCRD&D	FY2011
Modeling and Test Validation of a Reactor Cavity Cooling System with Air	University of Wisconsin-Madison	$1,199,988		Document	RCRD&D	FY2011
Transient Mixed Convection Validation for NGNP	Utah State University	$635,860		Document	RCRD&D	FY2011
Alternative High-Performance Ceramic Waste Forms	Alfred University	$840,000	This project aims to advance fundamental understanding of the kinetics of structural evolution of crystalline ceramic waste forms. The structure/property relationships will be identified and will reveal new formulations, improved processing routes, and strategies for improved performance or ceramic waste forms.	Document	FCR&D	FY2012
Surface Layer Bulk Glass Interface Evolution with Aqueous Corrosion	Alfred University	$880,000	This project will investigate the links between the morphology, structure and chemistry of surface layer-bulk glass interface and the long-term corrosion-reaction kinetics using in-situ and ex-situ experiments. The understanding will result in improved models for long-term predictive behavior of high-level-waste (HLW) glasses under repository conditions.	Document	FCR&D	FY2012
Improved Accident Tolerance of Austenitic Stainless Steel Cladding through Colossal Supersaturation with Interstitial Solutes	Case Western Reserve University	$850,000	This project aims to develop new case-hardened austenitic stainless steels by saturating them with materials that improve their mechanical properties, corrosion resistance and radiation resistance. This project, if successful, will result in safer, longer-lasting, and more accident tolerant fuel claddings.	Document	FCR&D	FY2012
Optimization of Deep Borehole Systems for HLW Disposal	Massachusetts Institute of Technology	$850,000	Researchers aim to carry out a comprehensive evaluation of the deep borehole option for disposal of used nuclear fuel and high livel waste. The models developed will predict potential movement of water through natural and engineered barriers and release of radionuclides to the biosphere which will aide in site selection.	Document	FCR&D	FY2012
Scholarship for Nuclear Communications and Methods for Evaluation of Nuclear Project Acceptability	Massachusetts Institute of Technology	$800,000	Researchers will work to develop a model to characterize the factors affecting social acceptance of nuclear projects with potential stakeholders. The resultant model will strengthen the ability to design and implement large projects more efficiently, leading to higher rates of success of future nuclear projects.	Document	FCR&D	FY2012
Accurate Holdup Calculations with Predictive Modeling and Data Integration	North Carolina State University	$875,000	Researchers will develop and use state-of-the-art radiation transport codes to account accurately for the fissile material in a nuclear materials processing facility. An accurate estimation of the materials will allow for ensured radiological safety, security, waste management and efficient plant operation.	Document	FCR&D	FY2012
Novel Metal Sulfides to Achieve Effective Capture and Durable Consolidation of Radionuclides	Northwestern University	$760,000	Researchers will evaluate the effectiveness of chalcogenide based materials design novel metal sulfides to effectively capture and store of radioisotopes released during reprocessing of used nuclear fuel. This project will focus on understanding structure-property relationships to enable refined and direct synthesis approaches for improved and cost-efficient nuclear waste forms.	Document	FCR&D	FY2012
Nonlinear Ultrasonic Diagnosis and Prognosis of ASR Damage in Dry Cask Storage	Northwestern University	$885,000	Researchers aim to use nondestructive damage characterization methods to detect, manage and mitigate the degradation/damage mechanisms of dry cask storage systems for nuclear fuels. This project, if successful, will provide tools that will allow the prediction of the reliability and the safety of concrete structures in dry cask storage systems.	Document	FCR&D	FY2012
Prototype Demonstration of Gamma-Blind Tensioned Metastable Fluid Neutron/Multiplicity/Alpha Detector- Real Time Methods for Advanced Fuel Cycle Applications	Texas A&M University	$875,000	This project aims to create a prototype demonstration of a novel neutron/alpha detector based on a technology that is blind to gamma field used fuel. The prototype, if successful, will enhance instrumentation for monitoring real-time material balance during various stages of the nuclear cycle.	Document	FCR&D	FY2012
Testing of Sapphire Optical Fiber and Sensors in Intense Radiation Fields, when Subjected to Very High Temperatures	The Ohio State University	$885,000	The researchers on this project will investigate the performance of sapphire optical fibers and sensors in reactor environments. The project, if successful, will result in improved instrumentation to understand the behavior and predict performance of nuclear fuel systems at the microstructural level.	Document	FCR&D	FY2012
Concrete Materials with Ultra-High Damage Resistance and Self-Sensing Capacity for Extended Nuclear Fuel Storage Systems	University of California, Irvine	$800,000	Researchers aim to design a new class of multifunctional concrete materials. This project, if successful, will result in a novel multifunctional concrete material that possesses inherent degradation monitoring capability and is suitable for an extended storage system for the used nuclear fuel.	Document	FCR&D	FY2012
Development of Innovative Accident Tolerant High Thermal Conductivity UO2 Fuel Pellets with a Diamond Dopant	University of Florida	$800,000	Researchers will evaluate the use of diamond nanoparticles composite material in innovative accident tolerant fuel pellets. This could significantly improve both the thermal conductivity of fuel pellets and light water reactors' efficiency safety.	Document	FCR&D	FY2012
Probabilistic Multi-Hazard Assessment of Dry Cask Structures	University of Houston	$865,000	This project aims to investigate the performance of dry cask storage systems under multiple hazard systems (earthquake, tornados, combined with aging effects) using a probabilistic multi-hazard framework. This framework will be validated based on experimental research and will provide improved models for safety and reliability of spent nuclear fuels during storage and transportation.	Document	FCR&D	FY2012
Measurement of Irradiated Pyroprocessing Samples via Laser Induced Breakdown Spectroscopy	University of Idaho	$820,000	This project aims to use advanced characterization techniques to investigate microstructural changes and the micromechanisms related to irradiation induced damage in used nuclear fuels and waste forms. This project, if successful, will result in enhanced models to predict the structural and chemical response of used fuel and waster forms during interim storage and permanent disposal.	Document	FCR&D	FY2012
Elastic/Inelastic Measurement Project	University of Kentucky	$880,523	Researchers will measure nuclear data for elastic/inelastic scattered neutrons on coolants and structural materials. The data generated, will be useful for future R&D programs that will study innovative next generation LWR and future fast systems.	Document	FCR&D	FY2012
Electrochemical Corrosion Studies for Modeling Metallic Waste Form Release Rates	University of Nevada- Las Vegas	$790,000	This project aims to use advanced electrochemical methods to investigate the corrosion related degradation of metal alloys used for housing fission products. The data obtained from this study will allow for the prediction of the long-term behavior of the metallic host phase materials over geological time-scales.	Document	FCR&D	FY2012
Thermodynamic and Microstructural Mechanisms in the Corrosion of Advanced Ceramic Tc-bearing Waste Forms and Thermophysical Properties	University of Nevada- Las Vegas	$795,000	This project team will harvest thermodynamic and microstructural data on the evolution of ceramic based waste forms. The data will be used to advance the current state-of-the-art methodology used for isolation and stabilization of fission products and improve on nuclear fuel recycling processes.	Document	FCR&D	FY2012
Development and Experimental Benchmark of Simulations to Predict Used Nuclear Fuel Cladding Temperatures during Drying and Transfer Operations	University of Nevada- Reno	$745,000	Researchers will conduct experiments to investigate and develop advanced computational models of heat transfer in post-pool-storage drying operations. This project, if successful, will result in tools that can be used to design efficient drying processes to as to ensure suitability for dry-cask systems for long-term storage and transport.	Document	FCR&D	FY2012
Better Radiation Response and Accident Tolerance of Nanostructured Ceramic Fuel Materials?	University of Tennessee	$815,000	Researchers will use novel experimental methods to investigate the links between microstructure, phase stability and damage evolution in nanostructured ceramic fuel materials. The project will study fuel materials at temperatures and irradiation conditions relevant to operation and accidental scenarios.	Document	FCR&D	FY2012
Radiation and Thermal Effects on Used Nuclear Fuel and Nuclear Waste Forms	University of Tennesssee	$770,000	This project aims to investigate the structural and chemical response of used nuclear fuel and waste forms during interim storage and permanent disposal. If successful, this project will generate models that will allow the prediction of structural evolution and hence the radiological safety and security of nuclear fuel and waste forms.	Document	FCR&D	FY2012
Seismic Performance of Dry Casks Storage for Long-Term Exposure	University of Utah	$873,319	Researchers will evaluate the mechanical performance of dry-cask storage under seismic loading for mid-term operational periods. Simulations will include scenarios for freestanding, anchored, and vaulted casks. The experimental tests will also evaluate the dynamic seismic response of freestanding and anchored dry-cask storage prototypes, providing recommendations for optimal Interim Spent Fuel Storage Installations (ISFSIs) design.	Document	FCR&D	FY2012
Validation Experiments for Spent-Fuel Dry-Cask In-Basket Convection	Utah State University	$690,000	Researchers in this project aim to conduct experiments that generate data on natural convection through a fuel assembly. The data will be used to validate the computational models being developed for nuclear safety and design.	Document	FCR&D	FY2012
Re-Branding the Nuclear Fuel Cycle	Virginia Commonwealth University	$850,000	This project will create a comprehensive framework for the evaluation of alternative fuel cycle systems that will be used to identify and analyze key elements related to long-term management of nuclear fuels , with the ultimate goal to develop a communications strategy to reach stakeholders.	Document	FCR&D	FY2012
Advanced Characterization of Molecular Interactions in TALSPEAK-like Separations Systems	Washington State University	$875,000	Researchers will use advanced characterization techniques (experimental and computational) to improve understanding of the molecular level processes/interactions during separation processes for advanced fuel cycles. The understanding of these interactions will be used to develop more robust and streamlined separation processes for advanced fuel cycles.	Document	FCR&D	FY2012
Coupling of Nuclear Waste Form Corrosion and Radionuclide Transport in Presence of Relevant Repository Sediments	Washington State University	$885,000	Researchers will conduct experiments to understand the mechanisms responsible for the corrosion of nuclear waste forms in realistic chemical environments. The data generated from these experiments will enable increased reliability of the models used to predict the waste form performance in repository environments.	Document	FCR&D	FY2012
Stationary Liquid Fuel Fast Reactor (SLFFR) Concept for TRU Burning	Purdue University	$450,000	Reasearchers will investigate a new type of molten metallic fuel reactor concept that will consume hazardous transuranic waste. The liquid fuel alloy has several advantages over solid fuel fast reactors that are used for the same purpose.	Document	MSTR	FY2012
ABR for TRU Transmutation with Breed & Burn Thorium Blanket for Improved Economics and Resource Utilization	University of California- Berkeley	$450,000	The research team will use detailed neutronic analysis for a new Advanced Burner Reactor concept with low conversion ratio. The concept will use a new core shape to improve the utilization of neutrons to perform breed and burn.	Document	MSTR	FY2012
New Materials for High Temperature Thermoelecric Power Generation	University of California, Davis	$450,000	Reasearchers will work to develop nanostructured and other new materials to support the development of higher efficiency thermoelectric devices. These devices convert thermal energy to electricity with no moving parts. The new materials will operate at higher efficiencies and over a wider temperature range than those currently available--an important quality for future nuclear-powered deep space exploration.	Document	MSTR	FY2012
Microscopic Fuel Particles Produced by Self-Assembly of Actinide Nanoclusters on Carbon Nanomaterials	University of Notre Dame	$440,000	Reasearchers will develop the mechanisms, conditions and protocols to prepare uranium-carbon nanocomposite materials to make them more flexible. This could result in the generation of wholesale electricity, providing process heat, and providing power for households.	Document	MSTR	FY2012
High Hydrogen Content Graphene Hydride Compounds & High Cross-Section Cladding Coatings for Fast Neutron Detection	University of South Carolina	$430,000	This project will exploit recent breakthroughs to grow epitaxial graphene on commercial SiC wafers. This will allow researchers to develop a new detection method for fast neutrons. In addition, it will lead to better and more compact neutron detection system.	Document	MSTR	FY2012
Reducing Actinide Production Using Inert Matrix Fuels	University of Texas- Austin	$435,000	Reasearchers will perform a neutronic analysis, a thermal-hydraulic analysis and a simulation of fuel decay heat as a functionof fuel burnup, to determine if inert matrix fuel in coventional reactors will continue to be licensable. If successful, the inert matrix fuel mixtures will reduce harmful transuranic components in the fuel discharge streams at a level comparable to a fast reactcor burner.	Document	MSTR	FY2012
An Integrated Fuel Depletion Calculator for Fuel Cycle Options Analysis	University of Texas- Austin	$395,000	Reasearchers use new analysis techniques to better predict nuclear fuel behavior. The new model will allow improved fuel cycle for a larger number of users.	Document	MSTR	FY2012
Atomic-Scale to Meso-Scale Simulation Studies of Thermal Ageing and Irradiation Effects in Fe-Cr Alloys	Boston University	$874,997	Reasearchers will develop predictive, multi-scale simulation tools for iron-chromium alloys, which are expected to be key components of advanced steels envisioned as fuel cladding and structural components for Generation IV reactors. Such modeling is necessary to avoid resource intensive and costly thermal and neutron irradiation experiments to obtain required performance data.	Document	NEAMS	FY2012
Validation Data and Model Development for Fuel Assembly Response to Seismic Loads	George Washington University	$862,435	Reasearchers will conduct experiments that will provide comprehensive data characterizing the dynamics of the fluid and the structure in Pressurized Water Reactors (PWR) fuel assemblies under seismic loads (earthquakes and loss of coolant accidents). Completion of their project will greatly benefit the safety of existing and future nuclear reactors.	Document	NEAMS	FY2012
Uncertainty Quantification and Management for Multiscale Nuclear Materials Modeling	Georgia Institute of Technology	$743,444	Reasearchers will address the question of uncertainty propogation and error estimates associated with model prediction of material behavior under irradiation. Their work will facilitate a better understanding of the connection of various unit processes to collective responses in a multiscale model chain enabling the development of high strength and high ductility materials.	Document	NEAMS	FY2012
Fuel and Core Design Options to Overcome the Heavy Metal Loading Limit and Improve Performance and Safety of Liquid Salt Cooled Reactors	Georgia Insitute of Technology	$784,689	Reasearchers will examine new options for fuel and core designs in liquid salt cooled reactors where the current standard of TRISO type fuel has limitations due to loading characteristics. The research could enable new, more feasible fuel-core-reload options that will improve safety and performance parameters.	Document	RCRD&D	FY2012
Nonlinear Ultrasonic Techniques to Monitor Radiation Damage in RPV and Internal Components	Georgia Institute of Technology	$877,000	Reasearchers will explore new nondestructive materials evaluation and monitoring techniques utilizing nonlinear ultrasonic measurements . This technique will allow researchers to assess remaining useful life of select reactor components. Breakthroughs in this area will lead to the ability to characterize radiation damage in reactor pressure vessels and other components-leading to a clearer definition of reactor safety margins.	Document	RCRD&D	FY2012
Intergral Reactor Containment Condensation Model and Experimental Validation	Oregon State University	$871,119	Reasearchers will conduct experiments to enhance the safety and efficiency of small modular reactors (SMRs). This project will assess the impact of high-pressure steam condensation on steel containment vessels to be used for SMR deigns.	Document	RCRD&D	FY2012
Investigation of Natural Circulation Instability and Transients in Passively Safe Small Modular Reactors	Purdue University	$871,100	Reasearchers will perform scaled experiments to study the thermal-hydraulic instabilities that can occur in Small Modular Reactors (SMR) which rely on natural circulation cooling during normal operation and accident conditions. Their work will not only improve our understanding of general natural circulation instability but also lead to the development of stability criteria and predictability in the operation of SMRÃs.	Document	RCRD&D	FY2012
Thermoelectric-Driven Sustainable Sensing and Actuation Systems for Fault-Tolerant Nuclear Incidents	State University of New York, Stony Brook	$599,802	Reasearchers will examine the use of solid-state thermoelectric generators to produce electricity to sense and opeate during both normal and abnormal situations. This will provide indefinite monitoring of key components during power outages or station blackouts.	Document	RCRD&D	FY2012
Experimental and CFD Studies of Coolant Flow Mixing within Scaled Models of the Upper and Lower Plenums of NGNP Gas-Cooled Reactors	Texas A&M University	$713,051	Reasearchers will model the internal coolant flow of a prismatic core very high temperature reactor (VHTR) by using large eddy simulation tools. This method will enable more accurate prediction of flow field characteristics and better evaluation of VHTR behavior under operational and accidental conditions.	Document	RCRD&D	FY2012
Demonstrating Hybrid Heat Transport and Energy Conversion System Performance Characterization Using Intelligent Control Systems	University of Idaho	$877,000	Reasearchers will demonstrate an intelligent control systems in a hybrid energy conversion loop for a next generation nuclear power plant. Hybrid energy systems are a method of optimizing the use of natural resources for energy production. Hybrid systems present an opportunity to develop domestic energy sources to improve energy security.	Document	RCRD&D	FY2012
Advanced Reactor-Intermediate Heat Exchanger (IHX) Coupling: Theoretical Modeling and Experimental Validation	University of Idaho	$869,997	Reasearchers will model the behavior of the Advanced Reactor Intermediate Heat Exchanger Chemical Process system and develop advanced control techniques that take into account abnormal scenarios. The data and information obtained will assist in the development of intelligent control systems for next generation nuclear reactor systems.	Document	RCRD&D	FY2012
Irradiation Performance of Fe-Cr Base Alloys	University of Illinois- Urbana Champaign	$876,332	Reasearchers will perform post-radiation analysis and develop tools for future development and application of the Fe-Cr class of alloys. The results of this research will lead to better modeling of performance and development of an alloy designated as the primary choice for reactor fuel cladding and structural applications in advanced systems.	Document	RCRD&D	FY2012
Accelerated Irradiations for High Dose Microstructures in Fast Reactor Alloys	University of Michigan	$831,876	Reasearchers will determine the extent to which high dose rate irradiation can be used as an irradiation damage tool to understand microstructure evolution at high doses and temperatures relevant to advanced fast reactors. The project will provide fundamental understanding of the effectiveness of this process and thus of microstructure development in irradiated materials.	Document	RCRD&D	FY2012
Mitigating IASCC of Reactor Core Internals by Post-Irradiation Annealing Advanced Mitigation Strategies	University of Michigan	$876,985	Reasearchers will determine the optimum Post-irradiation annealing (PIA)-driven mitigation strategy to extend the potential lifetime of light water reactors. Samples that have already been irradiated in a light water reactor will be used to test PIA treatments to understand IASCC initiation and propoagation, annealing kinetics, the role of microstructure features in irradation hardening and localized deformation, and the optimum mitigation strategy based on PIA.	Document	RCRD&D	FY2012
Experimentally Validated Numerical Models for Effects of Non-Isothermal Turbulent Mixing on Wall Stresses in High Temperature Reactors	University of Pittsburgh	$876,422	Reasearchers will develop a comprehensive experimentally validated computational framework for the turbulent mixing in the lower plenum of a very high temperature reactor (VHTR). Through CFD modeling and experimental validation, the results from this project will lay the groundwork for future stress analysis, failure and fatigue studies, and uncertainty quantification for the VHTR system.	Document	RCRD&D	FY2012
Role of Defects in Swelling and Creep of Irradiated SiC	University of Wisconsin- Madison	$875,350	Reasearchers will study mechanisms controlling both radiation swelling and radiation creep in silicon carbide. These two effects are crucial to understanding the issues associated with the brittle silicon carbide composite. Success in this project will ground progress in the adoption of silicon carbide for reactor solutions, particularly as fuel cladding.	Document	RCRD&D	FY2012
Advanced Supercritical Carbon Dioxide Brayton Cycle Development	University of Wisconsin, Madison	$877,000	Reasearchers will investigate the benefits of utilizing advanced Brayton cycles with supercritical carbon dioxide in new reactor systems and components. Benefits of this research include improvement of analysis and performance of components currently utilizing these cycles as well as the potential for a large scale advanced CO2 power system.	Document	RCRD&D	FY2012
Mechanical Behavior of UO2 at Sub-grain Length Scales: Quantification of Elastic, Plastic and Creep Properties via Microscale Testing	Arizona State University	$800,000	Reasearchers will develop techniques to measure properties at sub-grain scales using depleted Uranium Oxide samples. The project will provide a framework to measure sub-grain scale mechanical properties, as well as provide experimental data to improve the understanding of advanced oxide fuels.	Document	FCR&D	FY2013
The Impacts of Pore-Scale Physical and Chemical Heterogeneities on the Transport of Radionuclide-Carrying Colloids	Colorado School of Mines	$800,000	Reasearchers will identify the dominant transport mechanisms to develop models that predict radionuclide distribution in porous materials. Experimental and computational models will be created that couple pore-scale geometric and interfacial structures. Simulators such as these are a necessary step towards fully predictive models for field-scale applications in the future.	Document	FCR&D	FY2013
Recovery of Uranium from Seawater: Polymer-Supported Aminophosphinates as Selective Extractants	Hunter College, CUNY	$399,999	Reasearchers will prepare a polymer-supported extractant for the recovery of uranium from seawater. The project will focus on primary amines that could provide a 3-fold increase in uranium capture capacity than current methods.	Document	FCR&D	FY2013
In-pile Thermal Conductivity Characterization with Single-laser Heating/Time Resolved Raman	Iowa State University	$800,000	Reasearchers will develop a time-resolved Raman-based thermal conductivity measurement system to improve remote in-pile thermal conductivity measurement. These measurements will provide new insights into the behavior of materials exposed to extreme radiation and temperature environments. Understanding the behavior of materials at the microstructural level will support optimized fuel designs.	Document	FCR&D	FY2013
Organic Speciation and Interactions in ALSEP - One Step Partitioning Process of Minor Actinides, Lanthanides, and Fission Products	Oregon State University	$600,000	Reasearchers will investigate the Actinide-Lanthanide Separation (ALSEP) process organic phase prior to aqueous phase separation and after aqueous separation phases of bare and metal-loaded acids. Quantifying these effects can be used to determine how an engineering scale process will perform and generate an accurate chemical model for the system.	Document	FCR&D	FY2013
Glass Composition and Solution Speciation Effects on Stage III Dissolution	Pennsylvania State University	$700,000	Reasearchers will study the chemical and structural triggers of long-term vitrified nuclear waste form behavior. They will study a range of waste glass compositions in corrosive environments. The study will improve understanding of the long-term residual rate and may provide new options for environmental control of glass dissolution rates.	Document	FCR&D	FY2013
Correlating Thermal, Mechanical, and Electrical Coupling Based Multiphysics Behavior of Nuclear Materials Through In-Situ Measurements	Purdue University	$800,000	Reasearchers will use in-situ experimental techniques to monitor the influence of extreme conditions on fuel cladding. The project will establish an in-situ experimental setup that can predict change in thermal properties and their correlation with mechanical properties and correlate such changes to changes in microstructural and chemical features.	Document	FCR&D	FY2013
Creation of a Geant4 Muon Tomography Package for Imaging of Nuclear Fuel in Dry Cask Storage	Purdue University	$440,000	Reasearchers will develop a simulation and analysis package to aid in the non-destructive assessment of sealed used nuclear fuel dry casks using cosmic ray muons. Cosmic ray muon tomography allows for non-destructive assessment that can independently verify and identify weapons grade material sealed within dense dry casks.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Two-stage Fast Reactor Fuel Cycle Options for Optimum Resource Utilization and Waste Management	Purdue University	$400,000	Reasearchers will evaluate the two different two-stage fast reactor fuel cycle options that will offer efficient use of uranium resources and the ability to burn actinides and long-live fission products. Evaluation of these fast fuel cycle options will serve as a useful complement to the options currently being considered in the Fuel Cycle Options Campaign.	Document	FCR&D	FY2013
Mixed Metal Phosphonate-Phosphate Resins for Separation of Lanthanides from Actinides	Texas A&M University	$650,000	Reasearchers will use ion exchangers to cleanly separate lanthanides and curium from reusable actinides. The study will assist in the development of an inexpensive, simple way in which to separate lanthanides from actinides found in used nuclear fuel rods and to recover a large portion of the usable fuel.	Document	FCR&D	FY2013
Safeguards in Pyroprocessing: an Integrated Model Development and Measurement Data Analysis	The Ohio State University	$626,151	Reasearchers will develop a comprehensive and effective safeguards approach for a pyroprocessing facility to support safeguards for future fuel cycles in the United States. The new approach and design will focus directly on the special nuclear materials in the electrorefiner where actinides are separated from fission products through electrochemical process.	Document	FCR&D	FY2013
Using Ionic Liquids for the Development of Renewable Biopolymer-Based Adsorbents for the Extraction of Uranium from Seawater and Testing Under Marine Conditions	University of Alabama	$400,000	Reasearchers will explore the fundamental engineering parameters for a renewable high-performance adsorbent for the extraction of uranium from sweater based on a recently proven ionic liquid (IL)-chitin platform. The project will use the platform to develop a versatile, modifiable adsorbent and characterize its performance and degradation in marine conditions.	Document	FCR&D	FY2013
Developing Ultra-Small Scale Mechanical Testing Methods and Microstructural Investigation Procedures for Irradiated Materials.	University of California, Berkeley	$800,000	Reasearchers will develop new small-scale mechanical testing techniques to allow for the estimation or direct measurement of bulk properties. The combined experiments and modeling will significantly enhance the statistics and information that can be obtained on small radioactive archived samples, as well as new ion beam irradiated specimens.	Document	FCR&D	FY2013
Improved Delayed-Neutron Spectroscopy Using Trapped Ions	University of California, Berkeley	$400,000	Reasearchers will develop innovative spectroscopy techniques to measure the decay of fission fragments. The resulting data from these new techniques will be used to better understand reactor kinetics under accident conditions and failure scenarios.	Document	FCR&D	FY2013
Thermally and Chemically Responsive Nanoporous Materials for Efficient Capture of Fission Product Gases	University of California, Davis	$750,000	Reasearchers will create new nanoporous materials that will be highly effective at capturing fission product gases. These materials would be relevant to both reactor fuels applications and reprocessing operations. Tests will be performed in carbon based and nitride based nanostructures, with the most promising materials from the modeling perspective undergoing further testing.	Document	FCR&D	FY2013
Multiphase Nanocrystalline Ceramic Concept for Nuclear Fuel	University of California, Irvine	$800,000	Researchers will study the use of nanoparticles and nanostructured ceramics to create new materials that can extend the service life and increase efficiency for nuclear fuel. Multiphase nanocrystalline ceramics will be used to design simulated nuclear fuel that can provide added plasticity, better radiation tolerance and improved thermal conductivity.	Document	FCR&D	FY2013
Development of Novel Porous Sorbents for Extraction of Uranium from Seawater	University of Chicago	$400,000	Reasearchers will develop a highly porous sorbent for the extraction of uranium from seawater. Previous research has established sorbent performance. This project will use past foundational studies to design and investigate a new nanocomposites that will be processed into tacks or braids for field tests in seawater tests. The technology may also be used for other metals.	Document	FCR&D	FY2013
Microwave Readout Techniques for Very Large Arrays of Nuclear Sensors	University of Colorado, Boulder	$799,937	Reasearchers will develop a powerful readout technique based on microwave transmission and reflection. The technique will enable very large arrays of diverse sensor types for nuclear materials quantification and tracking. It will provide more accurate data on material composition and quantity.	Document	FCR&D	FY2013
BiI3 Gamma-Ray Spectrometers for Reliable Room-Temperature Nuclear Materials Safeguarding	University of Florida	$799,999	Reasearchers will develop gamma-ray spectrometers based on BiI3 single crystals for MPACT applications such as burnup validation quantification, improved assay of plutonium, determination of uranium enrichment and overall monitoring spent fuel within the fuel cycle. The project will improve energy resolution, efficiency and environmental performance with this new gamma-ray detector.	Document	FCR&D	FY2013
Innovative Coating of Nanostructured Vanadium Carbide on the F/M Cladding Tube Inner Surface for Mitigating the Fuel Cladding Chemical Interactions	University of Florida	$760,276	Researchers will develop barrier coatings on the inner surface of fuel cladding tubes to improve performance of materials at elevated temperatures and high neutron exposures in fast reactors. The project will develop and test a low temperature coating process of nanostructured vanadium carbide that will provide a benchmark for use in future studies.	Document	FCR&D	FY2013
Doubling the Life of Concrete Structures	University of Idaho	$800,000	Reasearchers will use nanoscale techniques to develop methods for doubling the service life of concrete structures. They will study the effect of temperature load and temperature cycling (freezing and thawing) on the durability of concrete with nanoscale viscosity modifiers. The project will benefit from non-destructive evaluation of concrete performance through electrochemical techniques.	Document	FCR&D	FY2013
Off-Gas Treatment: Evaluation of Nano-structured Sorbents for Selective Removal of Contaminants	University of Idaho	$785,910	Reasearchers will evaluate nanostructured sorbent materials for their effectiveness in removing and immobilizing radionuclides for the off-gas treatment from used nuclear fuel recycling operations. The project aims at achieving near-zero emissions of radionuclides by capturing them from the off-gas of recycling operations, allowing for the development of advanced fuel cycles.	Document	FCR&D	FY2013
Innovative Elution Processes for Recovering Uranium and Transition Metals from Amidoxime-Based Sorbents	University of Idaho	$399,864	Reasearchers will develop a new two-step elution process to achieve total recovery of uranium and effective recycling of the sorbent. The extraction process would selectively remove uranium from the sorbent with little or no damage. The process would then remove transition metals and regenerate the sorbent for repeated use, making uranium extraction from seawater economically viable.	Document	FCR&D	FY2013
Performance of a Steel/Oxide Composite Waste Form for Combined Waste Streams from Advanced Electrochemical Processes over Geologic Time Scales	University of Illinois at Chicago	$700,000	Reasearchers will develop and validate a mechanistically-based corrosion model for cermet-type waste forms, creating a testing protocol and modeling approach for predicting long-term performance. The study will apply novel electrochemical testing and modeling methods to the behavior of metal/oxide phase boundaries to evaluate waste form performance.	Document	FCR&D	FY2013
Enhancement of the Extraction of Uranium from Seawater	University of Maryland, College Park	$400,000	Reasearchers will develop and optimize novel adsorbents for uranium recovery from seawater. The team will use radiation-induced grafting of organic phosphates onto polymers. The experiments will use ocean water, with mechanistic analysis, to provide a solid basis for large-scale demonstration of the performance of the new adsorbents in ocean environments.	Document	FCR&D	FY2013
Improving the Understanding of the Coupled Thermal-Mechanical-Hydrologic Behavior of Consolidating Granular Salt	University of New Mexico	$800,000	Reasearchers will increase the understanding of granular salt seal materials for shafts, drifts and boreholes. By coupling thermal, mechanical and hydrological responses, the study will result in greater confidence in granular salt consolidation as a principal strategy for closure and isolation of long-term waste repositories.	Document	FCR&D	FY2013
Fission Fragment Yield Data in Support of Advanced Reactor Technology	University of New Mexico	$399,816	Reasearchers will produce a highly accurate data set for thermal fission. These precision data are necessary for high-accuracy simulations of nuclear criticality, transmutation rates, radiation effects and heating as well as for nuclear fuel, material accounting and identification needs.	Document	FCR&D	FY2013
Molecular dynamics-based simulations of bulk/interfacial structures and diffusion behaviors in nuclear waste glasses	University of North Texas	$700,000	Reasearchers will generate accurate atomic structural models for use in Monte Carlo simulations of the dissolution of nuclear waste glasses. Large-scale molecular dynamics-based computer simulations will be used to investigate self-diffusion behaviors, interfacial structure, and other structures formed during dissolution of these glasses.	Document	FCR&D	FY2013
U3Si2 Fabrication and Testing for Implementation into the BISON Fuel Performance Code	University of South Carolina	$800,000	Reasearchers will fabricate, test and model a high uranium density, advanced nuclear fuel that operates at a much lower temperature and stores less energy. The work will deliver key research data on creep and grain growth, improving economics, through possible power uprates, and advancing accident tolerant fuels research.	Document	FCR&D	FY2013
Structural Health Monitoring of Nuclear Spent Fuel Storage Facilities	University of South Carolina	$738,618	Reasearchers will develop a nuclear structural health monitoring system based on a sensing technology that monitors material degradation and aging for dry cask storage systems. The low-cost, low-profile sensors will perform on-demand monitoring of the structural integrity of individual components as well as the entire system.	Document	FCR&D	FY2013
ORIGEN-based Nuclear Fuel Depletion Module for Fuel Cycle Assessment	University of Tennessee at Knoxville	$755,181	Reasearchers will develop a flexible reactor analysis module for the CYCLUS fuel cycle simulator based on established tools for reactor fuel depletion and decay. They will use ORIGEN, a mature and experimentally validated code, affording greater flexibility and allowing for accurate evaluations of impacts of both present and future fuel cycle options.	Document	FCR&D	FY2013
Cost and System Analysis of Innovative Fuel Resources Concepts	University of Texas at Austin	$295,960	_This project will develop and test braided polymer fiber adsorbents that surpass the sorption capacity, selectivity and durability of the best existing technology to recover uranium from seawater.	Document	FCR&D	FY2013
Risk Assessment of Structural Integrity of Transportation Casks	University of Utah	$789,296	Reasearchers will assess the loss of structural integrity of transportation casks and fuel cladding after extended storage. This risk assessment will conduct experimental tests and simulations to evaluate the structural performance of fuel, fuel assemblies and cask components when subjected to vibration and impact loads during transport.	Document	FCR&D	FY2013
Market-Based and System-Wide Fuel Cycle Optimization	University of Wisconsin, Madison	$612,731	Reasearchers will create market and economic optimizers to improve calculations for the CYCLUS fuel cycle simulator. The team will leverage existing optimization software frameworks within the simulator to resolve top level policy questions. The optimizations will allow CYCLUS to move beyond static material compositions, providing a holistic view of the fuel cycle system.		FCR&D	FY2013
Optical Fiber Based System for Multiple Thermophysical Properties for Glove Box, Hot Cell and In-Pile Applications	Utah State University	$799,975	Reasearchers will use a small pressure vessel to develop a robust technique for the measurement of multiple thermophysical properties at very high temperatures. The technique will lead to a system design moving toward the eventual measurement of irradiated fuels in a glovebox and/or hot cell with all sensors and electronics outside of the glovebox and/or hot cell.	Document	FCR&D	FY2013
Development of a Nano-Modified Concrete for Next Generation of Storage Systems	Vanderbilt University	$796,268	Reasearchers will use nano-sized and nano-structured particles based on enhanced reactivity to develop a superior concrete for the long-term storage of used nuclear fuel. The project will use state-of-the-art experimental chemical and mechanical characterizations and computation analysis to assess the performance of nano-modified concretes.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Thorium Fuel Cycle Options	Vanderbilt University	$797,995	Reasearchers will develop six fuel cycle data packages for multi-stage, thermal fuel cycles which incorporate thorium. These new fuel cycle data packages will provide the opportunity to examine fuel cycle options beyond those which have traditionally been considered. A thorium fuel cycle database will also be assembled as a basis for thorium literature for future evaluations of the thorium fuel cycle.	Document	FCR&D	FY2013
Enhanced Shielding Performance of HLW Storage Packages via Multi-Component Coatings	Virginia Polytechnic Institute and State University	$796,947	Reasearchers will develop a multi-layer composite that will enhance long-term storage and facilitate safe transport of storage packages. This novel multi-layer, multi-component coating would create an outer shield material that is resistant to the corrosion, radiation, diffusion and thermal cycling processes that affect fuel packages during long term storage.	Document	FCR&D	FY2013
Managing Zirconium Chemistry and Phase Compatibility in Combined Process Separations for Minor Actinide Partitioning	Washington State University	$700,000	Reasearchers will address unique challenges for combining TRUEX and TALSPEAK processes for partitioning of lanthanides and minor actinides. The project will develop improved information on the thermodynamics of fission product zirconium and develop a framework for an organic phase solvation model. Combined process development could streamline separations processes.	Document	FCR&D	FY2013
Advances in the Recovery of Uranium from Seawater: Studies Under Real Ocean Conditions	Woods Hole Oceanographic Institution	$398,882	Reasearchers will provide infrastructure and expertise for marine testing of currently available adsorbents in real ocean conditions. The team will move adsorbent research from the lab to field testing in order to quantify sorptive properties and uranium uptake. The project will provide valuable field data that will show the potential of large scale applications of these technologies.	Document	FCR&D	FY2013
NEUP Project 20-19172: Irradiation of Sensors and Adhesive Couplants for Application in LWR Primary Loop Piping and Components		$497,881	Reasearchers paln to attach ultrasonic transducers to substrates using various adhesive couplants that will be irradiated at elevated temperature to simulate LWR primary loop conditions at the PULSTAR reactor at North Carolina State University. Ultrasonic data will be taken in-situ. Subsequently, the sensors and couplant interfaces will be characterized using the LAMDA facility at ORNL. The results will be used to benefit a parallel EPRI project on online monitoring of cracks in LWR primary loop piping._	Document	R&D NSUF	FY2013
NEUP Project 20-19404: Extension of MSTDB to Provide a High-Quality, Validated Thermochemical Database for Predicting/Simulating Corrosion in Molten Salt Reactor SystemsUniversity of South Carolina		$600,000	Reasearchers will generate a validated, consistent database of initial fuel compositions and potential corrossion products of fluoride and chloride salts, allowing for important phenomena predictions in molten salt reactors to guide confident decisions. The database will be integral to the currently being developed Molten Salt Thermochemical Database (MSTDB), structured to allow use by commercial and open source codes._	Document	NEAMS	FY2013
Lower Length Scale Characterization and Validation of Formation and Stability of Helium Bubbles in Nano-structured Ferritic Alloys under Irradiation	Clemson University	$399,870	Reasearchers will provide a fundamental knowledge about the formation and stability of ultra-fine helium bubbles within 14YWT after neutron/ion irradiation for further design of new advanced structural materials with a characteristic high density nanoparticles feature which can increase the mechanical strength, hardness, irradiation resistance and the operational temperature range of materials.	Document	NEAMS	FY2013
Three-Dimensional Fuel Pin Model Validation by Prediction of Hydrogen Distribution in Cladding and Comparison with Experiment	Pennsylvania State University	$800,000	Reasearchers will validate important three-dimensional aspects of the fuel pin modeling by using specialized numerical modeling techniques coupled with laboratory experiments to validate existing models for predicting fuel performance in light water reactors.	Document	NEAMS	FY2013
Collocation-Based Surrogate Models for Uncertainty Quantification and Validation of Coupled, Multiphysics Fuel Performance Simulation Tools	University of Michigan	$596,835	Reasearchers will provide the necessary high fidelity, coupled, multiphysics fuel performance simulator for computational modeling and develop surrogates which will accelerate and focus the validation of the coupled codes. This will be achieved by utilizing the high fidelity coupled fuel performance, thermal-hydraulics and neutronics codes BISON/STAR-CCM+/MPACT and an innovative collocation-based surrogate methodology.	Document	NEAMS	FY2013
Multi-Resolution In-Situ Testing and Mutliscale Simulation for Creep Damage Fatigue Damage Analysis of Alloy 617	Arizona State University	$800,000	This project will develop novel testing and experimentally validated prediction methodologies for micro-structural damage mechanisms of structural materials for advanced reactor systems. The investigations will focus on the characterization and testing of specific metal alloys, but the proposed testing and life-prediction methodologies are applicable to other structural materials as well.	Document	RCRD&D	FY2013
Novel High Temperature and Radiation Resistant Infrared Glasses and Optical Fibers for Sensing in Advanced Small Modular Reactors	Clemson University	$800,000	Clemson University, in partnership with the Iowa State University and the Pacific Northwest National Laboratory, will develop novel optical materials with improved heat and radiation exposure resistance in order to enable in-vessel fiber optic sensing for advanced Small Modular Reactors.	Document	RCRD&D	FY2013
Validation Data Acquisition in HTTF during PCC Events	George Washington University	$800,000	Reasearchers at the George Washington University and Oregon State University will collaborate with NASA Langley Research Center to measure flow velocities in a high temperature test facility. This work supports the development of very-high temperature reactors with passive safety systems.	Document	RCRD&D	FY2013
Advanced High Temperature Inspection Capabilities for Small Modular Reactors	Iowa State University	$790,822	The objective of this project is to develop non-destructive evaluation techniques for advanced small modular reactors. The research will provide key enabling inspection technologies needed to support the design and the reactor component performance validation process for advanced small modular reactors.	Document	RCRD&D	FY2013
Experimental and Computational Investigations of Plenum-to-Plenum Heat Transfer under Natural Circulation in a Prismatic Very High Temperature Reactor	Missouri University of Science and Technology	$799,999	Reasearchers will perform experimental and computational investigations to study heat transfer and natural circulation phenomena in very-high temperature reactors. The study will assist in the ability to predict and analyze passive safety systems.	Document	RCRD&D	FY2013
New Mechanistic Models of Creep-Fatigue Crack Growth Interactions for Advanced High Temperature Reactor Components	Oregon State University	$790,790	Reasearchers will create and validate a robust, multi-scale, numerical model to predict material degradation in nickel-based reactor alloys. If successful, this project will provide better numerical tools for reactor designers and greatly improve their capability to design against material failures for reactor alloys in the long term.	Document	RCRD&D	FY2013
Self-Powered Wireless Dual-mode Langasite Sensor for Pressure/Temperature Monitoring of Nuclear Reactors	State University of New York, Stony Brook	$800,000	This research will develop a novel self-powered wireless hybrid sensor that can accurately monitor both pressure and temperature using a single device without requiring external electricity, even in extreme harsh environments.	Document	RCRD&D	FY2013
Compact Heat Exchanger Design and Testing for Advanced Nuclear Reactors and Advanced Power Cycles	The Ohio State University	$800,000	The goal of this project is to investigate optimal heat exchanger designs for advanced reactors. The research will study the optimization of printed circuit heat exchangers for specific fluids under a variety of conditions as well as perform numerical modeling. Experiments will focus on thermal performance and heat stress during extreme conditions.	Document	RCRD&D	FY2013
Fundamental Understanding of Creep-Fatigue Interactions in 9Cr-1MoV Steel Welds	The Ohio State University	$798,000	This project will advance the state of knowledge and fundamental understanding of deforming materials and welds under loading conditions. Specifically, new integrated testing procedures will be evaluated and applied for conditions that are most detrimental to material stability leading to improved predictions of life expectancy for reactor steels and welds.	Document	RCRD&D	FY2013
Advanced Mechanistic 3D Spatial Modeling and Analysis Methods to Accurately Represent Nuclear Facility External Event Scenarios	The Ohio State University	$800,000	Reasearchers will develop three-dimensional characterization uncertainty analysis for commercial power plants. The project will involve combining experts from the fields of seismic structural modeling and advanced methods of risk assessment. This effort is expected to result in next generation tools that can be used for assessment of seismic risks.	Document	RCRD&D	FY2013
Tritium Mitigation/Control for Advanced Reactor Systems	The Ohio State University	$400,000	Reasearchers will develop a fluoride salt cooled high-temperature reactor featuring a specialized system to control tritium production. If successful, this will result in a significant reduction in size and cost in comparison to other reactor designs.	Document	RCRD&D	FY2013
A Pebble-Bed Breed and Burn Reactor	University of California, Berkeley	$400,000	Reasearchers will assess the feasibility of designing a type of metal cooled reactor able to establish and maintain operation when fueled with depleted uranium. If successful, this reactor will offer at least a 30-fold increase in the uranium ore utilization versus that achieved in contemporary light water reactors without the need for fuel reprocessing and recycling.	Document	RCRD&D	FY2013
Investigation of Thermal Aging Effects on the Evolution of Microstructure and Mechanical Properties of Cast Duplex Stainless Steels	University of Maryland, College Park	$799,966	This research will provide a better understanding of the microstructural evolution and simultaneous change in mechanical response during aging. The results of the research will provide data that can be used to estimate degraded mechanical properties for an 80-year service life of light water reactors.	Document	RCRD&D	FY2013
Model validation using CFD-grade experimental database for NGNP Reactor Cavity Cooling Systems with water and air	University of Michigan	$799,348	Reasearchers will use advanced innovative instrumentation to build a high-resolution experimental database and to use the novel experimental data to assess and further develop the predictive capabilities of computer codes for thermal hydraulics and computational fluid dynamics. The improved models developed by this project will also have the direct benefit of improving the predictive capability of the passive systems of third generation light water reactors and small modular reactor systems.	Document	RCRD&D	FY2013
Long-Term Prediction of Emissivity of Structural Material for High Temperature Reactor Systems	University of Missouri	$799,117	Reasearchers will study specific types of emissivity driven cooling from a variety of materials that are relevant to nuclear reactors. The research will provide a basis for numerical modeling to support reactor development.	Document	RCRD&D	FY2013
Advanced I&C for Fault-Tolerant Supervisory Control of Small Modular Reactors	University of Pittsburgh	$800,000	The purpose of this research is to develop advanced instrumentation and control techniques for supervisory control of advanced small modular reactors. This research supports the operational goals of small modular reactor concepts through the development of improved oversight and surveillance techniques.	Document	RCRD&D	FY2013
Corrosion of Structural Materials for Advanced Supercritical Carbon-Dioxide Brayton Cycle	University of Wisconsin-Madison	$798,672	Reasearchers will study a variety of materials for corrosion resistance under conditions that improve power conversion. In addition to studying the corrosion resistance of the materials, researchers will study the effect of additives to mitigate corrosion. Development of corrosion theories and modeling aimed at prediction of long-term corrosion will be the underlying theme throughout the project.	Document	RCRD&D	FY2013
Component and Technology Development for Advanced Liquid Metal Reactors	University of Wisconsin-Madison	$798,920	In support of liquid metal cooled reactors, the University of Wisconsin, Madison will evaluate advanced alloys and ceramics that come in contact with liquid metals. Additionally, a robust oxygen sensor and for use in liquid metals will be developed in order to better evaluate corrosion profiles in support of diagnostic testing.	Document	RCRD&D	FY2013
A New Paradigm for Understanding Multi-phase Ceramic Waste Form Performance	Clemson University	$800,000	Researchers will use advanced characterization tools to develop 3-D microstructural data that can be incorporated into computer-based simulations in order to predict the performance of waste forms. Materials system modeling will incorporate elemental release and the interconnected microstructural network of phases to better understand performance and degradation, which will accelerate waste form acceptance in repository settings.	Document	FCR&D	FY2014
Controlling Hexavalent Americium: A Centerpiece to a Compact Nuclear Fuel Cycle	Colorado School of Mines	$800,000	Researchers will develop and exploit the fundamental chemistry of Americium to enable an industrially viable means to co-recover the major and minor actinide elements from used nuclear fuel. The results would be a significant step forward in the development of aqueous separations approaches designed to recover the U-Am actinides based on the availability of the hexavalent oxidation state.	Document	FCR&D	FY2014
Zeolite Membranes for Krypton/Xenon Separation from Spent Nuclear Fuel Reprocessing Off-Gas	Georgia Institute of Technology	$400,000	Researchers will develop a high-performance, lower-cost zeolitic membrane process for Kr/Xe separations during spent nuclear fuel processing. Current separation methods are not considered economical and a membrane process would have relatively lower cost, equipment size, and ambient operating temperature. The process would form a sound basis for further development of this transformative separation technology for the nuclear fuel cycle.	Document	FCR&D	FY2014
Optimizing Polymer-Grafted Amidoxime-based Adsorbents for Uranium Uptake from Seawater	Georgia Institute of Technology	$399,999	Researchers will work to increase the adsorbent capacity and selectivity toward uranium by optimizing the adsorbent morphology, synthesis variables, and conditioning parameters and by investigating the rate-limiting variables through transport and reaction modeling. A novel adsorption/partition concept that has the potential to substantially increase the adsorbent capacity will be tested, making uranium from seawater extraction more economically viable.	Document	FCR&D	FY2014
Extraction of Uranium from Seawater: Design and Testing of a Symbiotic System	Massachusetts Institute of Technology	$400,000	Researchers will develop a seawater uranium extraction system that will work symbiotically with an offshore windmill by utilizing the structure, mooring and power of the windmill, while increasing the energy harvested by the installation. Uranium will be extracted by an adsorbent polymer belt, which will be cycled through the seawater and an elution plant located at the base of the windmill tower. Increasing the frequency of harvesting could overcome current economic barriers to seawater uranium extraction.	Document	FCR&D	FY2014
Imaging a Dry Storage Cask with Cosmic Ray Muons	Oregon State University	$799,871	Researchers will develop an imaging system to monitor the content of a dry storage cask with cosmic ray muons. A very large amount of plutonium under nuclear safeguards is contained in used fuel assemblies stored in dry storage casks. Muon imaging will allow a cost effective and reliable way to evaluate dry storage cask content and integrity before transport.	Document	FCR&D	FY2014
Apatite and sodalite based glass-bonded waste forms for immobilization of 129I and mixed halide radioactive wastes	Rutgers University	$800,000	Researchers will develop advanced and chemically durable waste forms for immobilizing 129I (aqueous based reprocessing of fuel) and mixed-halide wastes (molten-salt processing of fuel) by low temperature synthesis. Halide-containing sodalite and calcium phosphate-based apatite minerals will be synthesized, consolidated and tested for chemical durability. The project will provide needed baseline data for the development of advanced waste forms for immobilization of iodine and mixed-halide wastes.	Document	FCR&D	FY2014
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$350,000	Researchers will develop modeling tools supported by experiments for off-gas capture from future nuclear-fuel recycling facilities. Target species include tritium, iodine, krypton, and xenon. The models are intended to provide path forward recommendations to develop off-gas treatment adsorption processes. The project will contribute to the evaluation of options for environmentally acceptable recycle systems.	Document	FCR&D	FY2014
Development of high performance ODS alloys	Texas A&M University	$800,000	Researchers will study swelling, radiation hardening and changes in mechanical properties of ODS alloys to develop two sets of advanced ODS alloys. Two sets of first-round candidate alloys that have already undergone extensive development and testing will evaluate irradiation performance. The study will meet the need for high strength, radiation-tolerant cladding and core components that have enhanced resistance to void swelling.	Document	FCR&D	FY2014
Rare Earth Electrochemical Property Measurements and Phase Diagram Development in a Complex Molten Salt Mixture for Molten Salt Recycle	The Ohio State University	$800,000	Researchers will investigate rare earth (RE) properties in complex molten salt mixtures. In a molten salt recycle approach, the RE drawdown by electrolysis is a key step in which REs are separated from salt containing other fission products. Investigation of RE electrolysis must consider the electrochemical properties of the REs. We propose to conduct studies of detailed experiments and corresponding models to provide the physical properties and phase diagrams required to predict the performance of RE drawdown for processing complex molten salts.	Document	FCR&D	FY2014
Studies of Lanthanide Transport in Metallic Nuclear Fuels	The Ohio State University	$800,000	Researchers will study the redistribution of lanthanides and migration of lanthanides to the fuel surface. The mechanisms of lanthanide transport in metallic fuel based on the novel discovery of a Ôliquid-likeÕ transport mechanism will be studied analytically and experimentally. The project will develop a fundamental understanding of lanthanide fission product migration and redistribution in advanced metallic nuclear fuels, and theory and data to mitigate fuel-cladding chemical interactions.	Document	FCR&D	FY2014
Computational and Experimental Studies of Microstructure-Scale Porosity in Metallic Fuels for Improved Gas Swelling Behavior	University of Arkansas	$796,823	Researchers will study the microstructure of metallic uranium alloy fuels, and their resistance to densification, to minimize in-pile irradiation swelling through bimodal pore size distribution. The project will develop a predictive approach to design metallic fuel microstructures for optimal swelling resistance and fission gas retention.	Document	FCR&D	FY2014
Improved Hybrid Modeling of Spent Fuel Storage Facilities	University of California, Berkeley	$645,393	Researchers will develop a variance reduction method for computational transport that will improve the ability to design and operate monitoring systems for interim used fuel installations through enhanced modeling and simulation. This new tool will demonstrate that modeling calculations can be done more accurately in less time than with current tools and will perform studies characterizing how changes in material, cask configurations, and number of casks could impact monitoring systems.	Document	FCR&D	FY2014
Selective ligands for uranyl via combinatorial peptoid libraries: A synthetic, structural, thermodynamic and computational study	University of California, Berkeley	$400,000	Researchers will study how donor ligands bind to the uranyl ion, UO22+, with the longer-term goal of using this information to tackle selective recognition of uranyl in aqueous solution. The study will impact underlying approaches to controlling the behavior of uranium in these systems. The actinide separation technology could be used in several areas including uranium extraction from seawater, nuclear waste remediation and nuclear materials.	Document	FCR&D	FY2014
Combining Experiments and Simulations of Extraction Kinetics and Thermodynamics in Advanced Separation Processes for Used Nuclear Fuel	University of California, Irvine	$799,938	Researchers will study how the kinetics and thermodynamics of metal ion extraction in advanced separation processes for used nuclear fuel can be described by molecular dynamic (MD) simulations and how the simulations can be validated by experimental data. The project would have broad impacts on several separations processes including advanced TALSPEAK, ALSEP and GANEX by increasing the confidence and accuracy of computer modeling of metal ion extraction._	Document	FCR&D	FY2014
Effect of Metallic Li on the Behavior of Metals in Molten Salts	University of Nevada, Reno	$458,250	Researchers will identify the effect of metallic lithium on materials that are used in molten salt recycling. The study will try to understand how the presence of Li(0) in molten salts affects the degradation of alloys. Studying these changes will help accurately predict container material behavior and longevity.	Document	FCR&D	FY2014
Assessment of Corrosion Resistance of Promising Accident Tolerant Fuel Cladding under Reactor Conditions	University of Notre Dame	$800,000	Researchers will assess the corrosion behavior of accident tolerant fuel candidate iron-based alloys under normal LWR operating conditions consisting of high temperature, relevant water chemistry and irradiation. The assessment will produce data about possible irradiation-accelerated corrosion rates of iron-based alloys, and the mechanisms by which such corrosion rates are accelerated. The project will advance the selection of appropriate replacements for Zircaloy cladding.	Document	FCR&D	FY2014
Functionalized Porous Organic Polymers as Uranium Nano-Traps for Efficient Recovery of Uranium from Seawaterr	University of South Florida	$399,000	Researchers will develop functionalized porous organic polymers, or Ônano-trapsÕ for extraction of uranium from seawater. This technique allows for increased surface area and custom-designed pore size and chemistry to fit specific parameters. The adsorbent materials have high efficiency and effectiveness for uranium recovery from seawater, providing a potential supply for nuclear fuel.	Document	FCR&D	FY2014
Enhanced Accident-Tolerant Fuel Performance and Reliability for Aggressive iPWR/SMR Operation	University of Tennessee	$799,967	To develop a process that evaluates operational and safety performance of reactor-and-fuel combinations by integrating whole-core 3D neutronics with MOOSE/BISON fuel performance assessments via explicit time and space dependent fuel rod operational power histories. The project will be valuable in analyzing and evaluating accident tolerant fuel concepts and furthering the understanding of reactor physics and fuel performance aspects of key accident tolerant fuel concepts.	Document	FCR&D	FY2014
Nuclear Technology R&D Strategies in an Era of Energy Price Uncertainty	University of Texas, Austin	$799,112	Researchers will identify nuclear technology options that are competitive over a wide range of plausible future business environments. No single nuclear technology or business practice will be the best choice across all or even most future conditions. The study will focus on hybrid nuclear-fossil technologies, energy storage and conversion, which will result in an identification of nuclear strategies that can succeed under future market conditions.	Document	FCR&D	FY2014
Development and Optimization of Voltammetric Methods for Real Time Analysis of Electrorefiner Salt with High Concentrations of Actinides and Fission Products	University of Utah	$621,612	Researchers will develop an advanced voltammetry method to pursue the objective of real time monitoring of actinide concentrations in electrorefiner salt. This will include experimental measurement of key parameters such as activity coefficients and exchange current density. It will also involve simulation of voltammetry processes based on first principles. The project will allow for real time measurements that could support the commercialization of pyroprocessing.	Document	FCR&D	FY2014
Development of Self-Healing Zirconium-Silicide Coatings for Improved Performance of Zirconium-Alloy Fuel Cladding	University of Wisconsin, Madison	$798,621	Researchers will study the deposition of self-healing zirconium-silicide coatings on zirconium-alloy fuel cladding material to improve corrosion resistance under normal and accident conditions. Under these conditions, Zr-Si coating evolves into a highly protective functionally-graded multilayered system. The study will lead to improved performance of zirconium-alloy fuels._	Document	FCR&D	FY2014
Thermal Conductivity in Metallic Fuels	Virginia Polytechnic Institute and State University	$799,837	Researchers will calculate the thermal conductivity of metallic uranium and neptunium alloys, including the effects of noble gasses, using density functional theory. The experiments will validate the calculated effective thermal conductivity using the MARMOT code and by helping determine DFT simulation parameters. The study works to improve fuel lifetime by understanding its thermal behavior.	Document	FCR&D	FY2014
SiC-ODS Alloy Gradient Nanocomposites as Novel Cladding Materials	Virginia Polytechnic Institute and State University	$799,998	Researchers will combine nuclear nanomaterial design, processing, testing, and characterization efforts to develop revolutionary materials that can withstand neutron irradiation for long period of time using nanostructured SiC and oxide dispersion strengthened steel. The ultimate objective is to offer new cladding materials with increased corrosion resistance, strength, and creep resistance in both steady state and accident conditions.	Document	FCR&D	FY2014
Experimental Breeder Reactor II Benchmark Evaluation	Idaho State University	$400,000	Researchers will develop a benchmark evaluation of the Experimental Breeder Reactor II (EBR-II). During nearly 30 years of operation numerous experiments were conducted at EBR-II. The most significant of these experiments were conducted in 1986 demonstrating inherent safety features in loss of flow without reactor scram and loss of heat sink without reactor scram. Benchmark evaluation will be valuable for the reactor design efforts in the United States and South Korea.	Document	MSNE	FY2014
Integral full core multi-physics PWR benchmark with measured data	Massachusetts Institute of Technology	$400,000	Researchers will introduce BEAVRS, a new multi-cycle full-core Pressurized Water Reactor (PWR) depletion benchmark based on two operational cycles of a commercial nuclear power plant. This project aims at addressing the uncertainty quantification of the measured data and on making this benchmark a true non-proprietary international benchmark for the validation of high-fidelity multi-physics computational tools.	Document	MSNE	FY2014
Benchmark Evaluation of PROTEUS Gas-Cooled Reactor Experiments	University of Florida	$400,000	Researchers will create International Reactor Physics Experiment Evaluation Project (IRPhEP) benchmarks using data from 1970s experiments of the neutronics of gas-cooled fast reactor (GCFR) designs investigated in the PROTEUS reactor. The GCFR-PROTEUS experiments fill a gap in current integral benchmark data. These experiments can provide validation of computational models and nuclear data for next generation reactors.	Document	MSNE	FY2014
An Investigation To Establish Multiphysical Property Dataset Of Nuclear Materials Based On In-Situ Observations And Measurements	Purdue University	$800,000	Researchers will create an in-situ measurement based experimental approach to develop experimental validation dataset for NEAMS based code validation. Particular emphasis is on supplying data set for multiphysics simulations in extreme conditions as a function of material microstructure.	Document	NEAMS	FY2014
Experimental Validation of UO2 Microstructural Evolutions for NEAMS tool MARMOT	University of Florida	$798,000	Researchers will experimentally validate MARMOT for predicting the microstructural evolutions of UO2 oxide fuel under the driving forces of high temperatures and large temperature gradient in reactors. By performing the experiments and simulations simultaneously using precisely defined initial conditions, the experiment data will provide direct benchmarking of the MARMOT code.	Document	NEAMS	FY2014
High-resolution time-resolved experiments on mixing and entrainment of buoyant jets in stratified environments	University of Michigan	$799,983	Researchers will study high spatial and time-resolution experimental data of the fluid dynamics phenomena of flow jets interacting with a stratified layer. The issue plays an important role in the safety of several reactor designs, including sodium-cooled reactors. The data addresses the NEAMS needs for the validation of high fidelity computational fluid dynamics methodologies.	Document	NEAMS	FY2014
Fundamental study of key issues related to advanced S-CO2 Brayton Cycle: prototypic HX development and Cavitation	Georgia Institute of Technology	$799,000	Researchers will study scientific and operational issues pertinent to compact heat exchanger systems and turbo-machinery. The project will work to resolve issues with the fabrication of diffusion bonded compact heat exchangers, alternate heat exchange technology for recuperators, and resolution of issues with cavitation and fluid instabilities.	Document	RCRD&D	FY2014
Advanced Models for Nondestructive Evaluation of Aging Nuclear Power Plant Cables	Iowa State University	$787,291	Researchers will develop advanced models that relate environmentally induced microstructural and chemical changes in cable insulation polymers to their macroscopic electrical parameters. These parameters will be measured and modeled over a wide range of the electromagnetic spectrum, covering several potential nondestructive evaluation techniques, enabling identification of the most sensitive techniques for future development.	Document	RCRD&D	FY2014
Development of Novel Functionally Graded Transition Joints for Improving the Creep Strength of Dissimilar Metal Welds in Nuclear Applications	Lehigh University	$800,000	Researchers will develop graded transition joints and improved creep life models for increasing the life of dissimilar metal welds (DMWs) in nuclear reactors. The research represents the first application of functionally graded material concepts for solving the problem of DMW failures through an integrated approach of additive manufacturing, modeling, microstructural characterization, and advanced strain-sensing techniques.	Document	RCRD&D	FY2014
Feasibility Assessment of a Micro Modular Reactor (MMR)	North Carolina State University	$400,000	Researchers will develop an innovative compact reactor concept that integrates power production, power conversion and electricity generation in a single unit: the Micro Modular Reactor (MMR). It is designed to be absolutely melt-down proof (MDP) under all circumstances including complete loss of coolant scenarios with no possible release of radioactive material, to have a cycle length of greater than 10 years, and to be highly proliferation resistant.	Document	RCRD&D	FY2014
Scaling Studies for Advanced Gas Reactor Concepts	Oregon State University	$681,834	Researchers will expand the utilization of the Oregon State University High Temperature Test Facility (HTTF) to validate a broader range of advanced high temperature reactors and events. The facility will be revised to add a detailed scaling analysis of additional gas reactor concepts including advanced gas-cooled, molten salt, and sodium cooled reactors.	Document	RCRD&D	FY2014
Fluid Stratification Separate Effects Analysis, Testing and Benchmarking	Oregon State University	$800,000	Researchers will study fluid stratification in high temperature gas reactors. Coolant stratification is the result of incomplete mixing of one or more fluids, leading to a density gradient, which may or may not dissipate under diffusive or convective effects. This combined analytical and experimental project seeks to investigate stratification driven by diffusive and convective mechanisms and is expected to yield insight into this phenomenon.	Document	RCRD&D	FY2014
Probabilistic Economic Valuation of Safety Margin Management Analysis	Oregon State University	$795,364	Researchers will use RAVEN and develop a companion software package to facilitate economic analysis of safety margins. The project is a proof of concept that will use techniques to examine the cost of improving safety margins vs. the risk of accidents from not improving safety margins. This analysis can be used to evaluate the economic viability of various plant upgrades.	Document	RCRD&D	FY2014
Novel Dissimilar Joints Between Alloy 800H and 2.25%Cr and 1%Mo Steel	Pennsylvania State University	$800,000	Researchers will fabricate and test dissimilar metal joints between a nickel base alloy and a steel with gradual variations of chemical composition, microstructure and properties in a manner that reduces abrupt thermal expansion mismatch and the resulting residual stresses. Data on structure and properties will serve as valuable inputs for the initiation of an ASME code case.	Document	RCRD&D	FY2014
Multi-Phase Model Development to Assess RCIC System Capabilities under Severe Accident Conditions	Texas A&M University	$564,246	Researchers will develop physics-based models of the Reactor Core Isolation Cooling (RCIC) System and incorporating them into a multi-phase code for validation. The project will tackle the current major challenges in RCIC System analysis and enable evaluation of two-phase thermodynamic aspects.	Document	RCRD&D	FY2014
Experimental Investigation and CFD Analysis of Steam Ingress Accidents in HTGRs	The Ohio State University	$800,000	Researchers will study the steam ingress scenario for HTGRs. The study will investigate thermal-hydraulic behavior and graphite oxidation of stream ingress phenomena to validate predictive CFD models. This work will resolve concerns about possible steam generator tube ruptures in a HTGR He-Steam Rankine cycle.	Document	RCRD&D	FY2014
Coiled Tube Gas Heaters For Nuclear Gas-Brayton Power Conversion	University of California, Berkeley	$800,000	Researchers will develop heat exchangers for Brayton-cycle power conversion in reactors using sodium, NaK, or salt as intermediate coolants. The proposed coiled tube gas heaters (CTGHs) are expected to have excellent power density, thermal shock/creep, in-service inspection, and reparability characteristics.	Document	RCRD&D	FY2014
Fundamental Studies of Irradiation-Induced Modifications in Microstructural Evolution and Mechanical Properties of Advanced Alloys	University of Illinois, Urbana-Champaign	$800,000	Researchers will develop and test a mechanism for predicting neutron irradiation performance for optimized Grade 92 and Alloy 709 for applications in advanced reactor systems. The work will employ ion irradiations and available information from neutron irradiations of related alloys to develop a basis for predicting the neutron irradiation performance of the optimized alloys.	Document	RCRD&D	FY2014
Integrated Computational and Experimental Study of Radiation Damage Effects in Grade 92 Steel and Alloy 709	University of Tennessee	$800,000	Researchers will develop a mechanistic understanding and predictive models of irradiation-induced microstructural evolution and resulting mechanical properties in optimized ferritic-martensitic Grade 92 steel and austenitic alloy 709 using multiscale simulations coupled with rigorous experimental validation. The project will provide insights into the correlation between ion irradiation and fast neutron damage.	Document	RCRD&D	FY2014
Meta-Level Design Guidance and Operator Performance Measures for Hybrid Control Rooms	Vanderbilt University	$799,869	Researchers will apply human factors engineering methods and relevant expertise from non-nuclear high-risk high-consequence domains toward the measurement of operator performance in analog, digital, and hybrid main control rooms. Performance measures will be developed for evaluating the situation awareness and decision-making proficiencies to support the transition to digital or hybrid control room displays.	Document	RCRD&D	FY2014

FY 2012 Research and Development Awards

The Department of Energy is awarding $37.9 million in support of the Nuclear Energy University Programs for 48 nuclear energy research and development projects focused on four fields: Fuel Cycle Research & Development; Reactor Concepts Research, Development & Demonstration; Nuclear Energy Advanced Modeling & Simulation; and Transformative Research.

These projects, selected for negotiation of award, are led by 33 American universities and colleges in more than 22 states and the District of Columbia. Other universities, industry leaders and National Laboratories will serve as collaborators and research partners.

A complete list of R&D projects with their associated abstracts is available below.

Title	Institution	Estimated Funding*	Project Description	Abstract	Project Type	Fiscal Year
Neutron Damage and MAX Phase Ternary Compounds	Drexel University			Document	IIR	FY2009
Atomistic Calculations of the Effect of Minor Actinides on Thermodynamic and Kinetic Properties of UO2+x	Georgia Institute of Technology			Document	IIR	FY2009
Maximum Fuel Utilization in Fast Reactors without Chemical Reprocessing	University of California, Berkeley			Document	IIR	FY2009
Developing a High Thermal Conductivity Fuel with Silicon Carbide Additives	University of Florida			Document	IIR	FY2009
Fabrication of Tungsten-Rhenium Cladding Materials via Spark Plasma Sintering for Ultra High Temperature Reactor Applications	University of Idaho			Document	IIR	FY2009
Ionic Liquid and Supercritical Fluid Hyphenated Techniques for Dissolution and Separation of Lanthanides, Actinides, and Fission Products	University of Idaho			Document	IIR	FY2009
Improved Fission Neutron Data Base for Active Interrogation of Actinides	University of Michigan			Document	IIR	FY2009
Utilization of Methacrylates and Polymer Matrices for the Synthesis of Ion Specific Resins	University of Nevada, Las Vegas			Document	IIR	FY2009
Improved LWR Cladding Performance by EPD Surface Modification Technique	University of Wisconsin, Madison			Document	IIR	FY2009
Advanced Models of LWR Pressure Vessel Embrittlement for Low Flux-High Fluence Conditions	University of California, Santa Barbara			Document	LWRS	FY2009
Irradiation Creep in Graphite	Boise State University			Document	NGNP	FY2009
Modeling the Stress Strain Relationships and Predicting Failure Probabilities For Graphite Core Components	Cleveland State University			Document	NGNP	FY2009
TRISO-Coated Fuel Durability Under Extreme Conditions	Colorado School of Mines			Document	NGNP	FY2009
An Innovative and Advanced Coupled Neutron Transport and Thermal Hydraulic Method (Tool) for the Design, Analysis and Optimization of VHTR/NGNP Prismatic Reactors	Georgia Institute of Technology			Document	NGNP	FY2009
Removal of 14C from Irradiated Graphite for Graphite Recycle and Waste Volume Reduction	Idaho State University			Document	NGNP	FY2009
Millimeter-Wave Thermal Analysis Development and Application to Gen IV Reactor Materials	Massachusetts Institute of Technology			Document	NGNP	FY2009
Accurate Development of Thermal Neutron Scattering Cross Section Libraries	North Carolina State University			Document	NGNP	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
Understanding Creep Mechanisms in Graphite with Experiments, Multiscale Simulations, and Modeling	North Carolina State University			Document	NGNP	FY2009
Simulations of the Thermodynamic and Diffusion Properties of Actinide Oxide Fuel Materials	University of Michigan			Document	AFCI	FY2009
Verification & Validation of High-Order Short-Characteristics-Based Deterministic Transport Methodology on Unstructured Grids	North Carolina State University			Document	NGNP	FY2009
Adsorptive Separation and Sequestration of Krypton, I and C14 on Diamond Nanoparticles	University of Missouri, Columbia			Document	AFCI	FY2009
Microscale Heat Conduction Models and Doppler Feedback	North Carolina State University			Document	NGNP	FY2009
Fundamental Understanding of Ambient and High-Temperature Plasticity Phenomena in Structural Materials in Advanced Reactors	Georgia Institute of Technology			Document	AFCI	FY2009
Development of Alternative Technetium Waste Forms	University of Nevada, Las Vegas			Document	AFCI	FY2009
Optimizing Neutron Thermal Scattering Effects in Very High Temperature Reactors	North Carolina State University			Document	NGNP	FY2009
Advanced Elastic/Inelastic Nuclear Data Development Project	Idaho State University			Document	AFCI	FY2009
Heterogeneous Recycling in Fast Reactors	Massachusetts Institute of Technology			Document	AFCI	FY2009
Quantification of UV-Visible and Laser Spectroscopic Techniques for Materials Accountability and Process Control	University of Nevada, Las Vegas			Document	AFCI	FY2009
Multiaxial Creep-Fatigue and CreepRatcheting Failures of Grade 91 and Haynes 230 Alloys Toward Addressing Design Issues of Gen IV Nuclear Power Plants	North Carolina State University			Document	NGNP	FY2009
Thermodynamic Development of Corrosion Rate Modeling in Iron Phosphate Glasses	Missouri University of Science and Technology			Document	AFCI	FY2009
Development of Subspace-Based Hybrid Monte Carlo-Deterministic Algorithms for Reactor Physics Calculations	North Carolina State University			Document	AFCI	FY2009
High-Fidelity Space-Time Adaptive Multiphysics Simulations in Nuclear Engineering	University of Nevada, Reno			Document	AFCI	FY2009
Improvements to Nuclear Data and Its Uncertainties by Theoretical Modeling	Rensselaer Polytechnic Institute			Document	AFCI	FY2009
Investigation of Countercurrent Helium-air Flows in Air-ingress Accidents for VHTRs	Ohio State University			Document	NGNP	FY2009
Sharp Interface Tracking in Rotating Microflows of Solvent Extraction	State University of New York at Stony Brook			Document	AFCI	FY2009
Bulk Nanostructured FCC Steels with Enhanced Radiation Tolerance	Texas A&M University			Document	AFCI	FY2009
Simulations of Failure via Three-Dimensional Cracking in Fuel Cladding for Advanced Nuclear Fuels	University of Texas, Dallas			Document	AFCI	FY2009
Testing of Performance of Optical Fibers Under Irradiation in Intense Radiation Fields, When Subjected to Very High Temperatures	Ohio State University			Document	NGNP	FY2009
Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels	Texas A&M University			Document	AFCI	FY2009
SiC Schottky Diode Detectors for Measurement of Actinide Concentrations from Alpha Activities in Molten Salt Electrolyte	The Ohio State University			Document	AFCI	FY2009
Computational Design of Advanced Nuclear Fuels	University of California, Davis			Document	AFCI	FY2009
Advanced Mesh-Enabled Monte Carlo Capability for Multi-Physics Reactor Analysis	University of Wisconsin, Madison			Document	AFCI	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
A Distributed Fiber Optic Sensor Network for Online 3-D Temperature and Neutron Fluence Mapping in a VHTR Environment	Texas A&M University			Document	NGNP	FY2009
Ab Initio Enhanced Calphad Modeling of Actinide Rich Nuclear Fuels	University of Wisconsin, Madison			Document	AFCI	FY2009
Investigation on the Core Bypass Flow in a Very High Temperature Reactor	Texas A&M University			Document	NGNP	FY2009
Development of Diffusion Barrier Coatings and Deposition Technologies for Mitigating Fuel Cladding Chemical Interactions (FCCI)	University of Wisconsin, Madison			Document	AFCI	FY2009
CFD Model Development and Validation for High Temperature Gas Cooled Reactor Cavity Cooling System (RCCS) Applications	Texas A&M University			Document	NGNP	FY2009
Thermal Properties of LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin, Madison			Document	AFCI	FY2009
Study of Air ingress across the duct during the accident conditions	Texas A&M University			Document	NGNP	FY2009
Verification of the CENTRM Module for Adaptation of the SCALE Code to NGNP Prismatic and PBR Core Designs	University of Arizona			Document	NGNP	FY2009
Integral and Separate Effects Tests for Thermal Hydraulics Code Validation for Liquid-Salt Cooled Nuclear Reactors	University of California, Berkeley			Document	NGNP	FY2009
Mechanisms Governing the Creep Behavior of High Temperature Alloys for Generation IV Nuclear Energy Systems	University of Cincinnati			Document	NGNP	FY2009
ALD Produced B2O3, Al2O3 and TiO2 Coatings on Gd2O3 Burnable Poison Nanoparticles	University of Colorado, Boulder			Document	NGNP	FY2009
Experimental Study and Computational Simulations of Key Pebble Bed Thermomechanics Issues for Design and Safety	University of Idaho			Document	NGNP	FY2009
Prediction and Monitoring Systems of Creep-Fracture Behavior of 9Cr-1Mo Steels for Reactor Pressure Vessels	University of Idaho			Document	NGNP	FY2009
Understanding Fundamental Material Degradation Processes in High Temperature Aggressive Chemomechanical Environments	University of Illinois, Urbana-Champaign			Document	NGNP	FY2009
Multi-Scale Multi-physics Methods Development for the Calculation of Hot-Spots in the NGNP	University of Michigan			Document	NGNP	FY2009
Corrosion and Creep of Candidate Alloys in High Temperature Helium and Steam Environments for the NGNP	University of Michigan			Document	NGNP	FY2009
Creation of a Full-Core HTR Benchmark with the Fort St. Vrain Initial Core and Validation of the DHF Method with Helios for NGNP Configurations	University of Michigan			Document	NGNP	FY2009
Fission Product Sorptivity in Graphite	University of Missouri, Columbia			Document	NGNP	FY2009
Identifying and Understanding Environment-Induced Crack Propagation Behavior in Ni-Based Superalloy INCONEL 617	University of Nevada, Las Vegas			Document	NGNP	FY2009
Graphite Oxidation Simulation in HTR Accident Conditions	University of New Mexico			Document	NGNP	FY2009
Non Destructive Thermal Analysis and In Situ Investigation of Creep Mechanism of Graphite and Ceramic Composites using Phase-sensitive THz Imaging & Nonlinear Resonant Ultrasonic Spectroscopy	University of Rochester			Document	NGNP	FY2009
Tritium Sequestration in Gen IV NGNP Gas Stream via Proton Conducting Ceramic Pumps	University of South Carolina			Document	NGNP	FY2009
Materials, Turbomachinery and Heat Exchangers for Supercritical CO2 Systems	University of Wisconsin, Madison			Document	NGNP	FY2009
Experimental Studies of NGNP Reactor Cavity Cooling System with Water	University of Wisconsin, Madison			Document	NGNP	FY2009
Assessment of Embrittlement of VHTR Structural Alloys in Impure Helium Environments	University of Wisconsin, Madison			Document	NGNP	FY2009
Modeling Fission Product Sorption in Graphite Structures	University of Wisconsin, Madison			Document	NGNP	FY2009
Liquid Salt Heat Exchanger Technology for VHTR Based Applications	University of Wisconsin, Madison			Document	NGNP	FY2009
Effect of Post-Weld Heat Treatment on Creep Rupture Properties of Grade 91 Steel Heavy Section Welds	Utah State University			Document	NGNP	FY2009
Alpha Radiolysis of Nuclear Solvent Extraction Ligands used for An(III) and Ln(III) Separations	California State University, Long Beach	$1,390,252		Document	FCR&D	FY2010
Predictive Maturity of Multi-Scale Simulation Models for Fuel Performance	Clemson University	$614,690		Document	FCR&D	FY2010
Freeze-casting as a Novel Manufacturing Process for Fast Reactor Fuels	Drexel University	$1,149,327		Document	FCR&D	FY2010
Fuel Performance Experiments on the Atomistic Level, Studying Fuel Through Engineered Single Crystal UO2	Idaho State University	$650,000		Document	FCR&D	FY2010
Development of A Self Biased High Efficiency Solid-State Neutron Detector for MPACT Applications	Rensselaer Polytechnic Institute	$810,141		Document	FCR&D	FY2010
Development of a Innovative High Thermal Conductivity UO 2 Ceramic Composites Fuel Pellets with Carbon Nano-Tubes Using Spark Plasma Sintering	University of Florida	$894,042		Document	FCR&D	FY2010
Exploration and Modeling of Structural Changes in Waste Glass under Corrosion	Pennsylvania State University	$1,377,444		Document	FCR&D	FY2010
Evaluation of materials for interim storage of spent fuel for more than 100 years	University of Michigan	$931,603		Document	FCR&D	FY2010
Implementation of On-the-Fly Doppler Broadening in MCNP5 for Multiphysics Simulation of Nuclear Reactors	University of Michigan	$406,712		Document	FCR&D	FY2010
Methods and tools to allow molecular flow simulations to be coupled to higher level continuum descriptions of flows in porous/fractured media and aerosol/dust dynamics	University of Missouri-Columbi	$541,286		Document	FCR&D	FY2010
Characterization and Modeling of Materials for Kr-Xe Separations	University of Nevada-Las Vegas	$989,800		Document	FCR&D	FY2010
Modeling Solute Thermokinetics in LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin-Madison	$616,073		Document	FCR&D	FY2010
Advanced Aqueous Separation Systems for Actinide Partitioning: Develop Fundamental Understanding of An(III)/Ln(III) Separation	Washington State University	$1,451,784		Document	FCR&D	FY2010
Consistent Multigroup Theory Enabling Accurate Coarse-Group Simulation of GenIV Reactors	Georgia Institute of Technology	$1,046,277		Document	GEN IV	FY2010
Studies of Deteriorated Heat Transfer in Prismatic Cores Stemming from Irradiation-Induced Geometry Distortion	Idaho State University	$1,287,921		Document	GEN IV	FY2010
Carbide Coatings for Nickel Alloys, Graphite, and Carbon/Carbon Composites to be Used in Fluoride Salt Valves	Johns Hopkins University	$1,183,239		Document	GEN IV	FY2010
Design, Testing, and Modeling of the Direct Reactor Auxiliary Cooling System for AHTRs	Ohio State University	$1,366,627		Document	GEN IV	FY2010
Monitoring microstructural evolution of Alloy 617 with nonlinear acoustics for remaining useful life prediction; multiaxial creep-fatigue and creep-ratcheting	Pennsylvania State University	$1,000,000		Document	GEN IV	FY2010
Development and Validation of Multidimensional Models of Supercritical CO 2 Energy Conversion Systems for Nuclear Power Reactors	Rensselaer Polytechnic Institute	$475,005		Document	GEN IV	FY2010
Multiscale Concrete Modeling for Aging Degradation	Mississippi State University	$345,941		Document	LWRS	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term and Elevated Temperature Irradiation: Modeling and Experimental Investigation	University of California-Berkeley	$1,320,667		Document	GEN IV	FY2010
Development of an advanced computational fluid dynamics technology for the next-generation nuclear reactor system analysis and safety margin characterization code	North Carolina State University	$418,199		Document	LWRS	FY2010
Development of Barrier Layers for the Protection of Candidate Alloys in the VHTR	University of California-Santa Barbara	$995,232		Document	GEN IV	FY2010
Precursor Derived Nanostructured Si-C-X Materials for Nuclear Applications	University of Washington	$899,518		Document	MRIIR	FY2010
Investigation of a Novel NDE Method for Monitoring Thermo-Mechanical Damage and Microstructure Evolution in Ferritic-Martensitic Steels for Generation IV Nuclear Energy Systems	University of Cincinnati	$833,109		Document	GEN IV	FY2010
Development and Testing of an Open-Loop Oscillator for Small Reactivity Worth Samples	Idaho State University	$597,252		Document	MRIIR	FY2010
Fission Product Transport in TRISO Particle Layers under Operating and Off-Normal Conditions	University of Michigan	$966,581		Document	GEN IV	FY2010
Understanding the Irradiation Behavior of Zirconium Carbide	Pennsylvania State University	$870,613		Document	MRIIR	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term Irradiation at Elevated Temperature: Critical Experiments	University of Michigan	$1,181,379		Document	GEN IV	FY2010
Modeling investigation of the stability and irradiation-induced evolution of nanoscale precipitates in advanced structural materials	University of Tennessee-Knoxville	$380,653		Document	MRIIR	FY2010
Three-dimensional NDE of VHTR Core Components via Simulation-based Testing	University of Minnesota	$1,366,163		Document	GEN IV	FY2010
Investigation of Laser Shock Peening for Enhancing Fatigue and Stress Corrosion Cracking Resistance of Nuclear Energy Materials	University of Cincinnati	$1,242,019		Document	MRIIR	FY2010
Failure Predictions for VHTR Core Components using a Probabilistic Continuum Damage Mechanics Model	University of Minnesota	$854,542		Document	GEN IV	FY2010
Irradiation Accelerated Corrosion of Reactor Core Materials	University of Michigan	$798,943		Document	MRIIR	FY2010
Development of a Scanning Microscale Fast Neutron Irradiation Platform for Examining the Correlation Between Local Neutron Damage and Graphite Microstructure	University of Missouri-Columbia	$703,064		Document	GEN IV	FY2010
Study of Interfacial Interactions using Thin Film Surface Modification: Radiation and Oxidation Effects in Materials	University of Wisconsin-Madison	$538,032		Document	MRIIR	FY2010
Development of Thermal Transient Flow Rate Sensors for High Temperature, Irradiation, Corrosive Environment	University of Nevada-Las Vegas	$451,269		Document	GEN IV	FY2010
Novel Engineered Refractory Materials for Advanced Reactor Applications	North Carolina State University	$1,129,304		Document	MRIIR	FY2010
Novel Methods of Tritium Sequestration: High Temperature Gettering and Separation Membrane Materials Discovery for Nuclear Energy Systems	University of South Carolina	$1,366,626		Document	GEN IV	FY2010
Heat Transfer Salts for Nuclear Reactor Systems - Chemistry Control, Corrosion Mitigation, and Modeling	University of Wisconsin-Madison	$1,352,040		Document	GEN IV	FY2010
Pulsed Magnetic Welding for Advanced Core and Cladding Steels	University of Wisconsin-Madison	$525,206		Document	GEN IV	FY2010
Corrosion in Supercritical Carbon Dioxide: Materials, Environmental Purity, Surface Treatments, and Flow Issues	University of Wisconsin-Madison	$651,447		Document	GEN IV	FY2010
Quantification of Cation Sorption to Engineered Barrier Materials Under Extreme Conditions	Clemson University	$1,171,380		Document	FCR&D	FY2011
In-Pile Instrumentation Multi-Parameter System Utilizing Photonic Fibers and Nanovision	Idaho State University	$1,199,990		Document	FCR&D	FY2011
Development of Plasmonically Cloaked Nanoparticles	Idaho State University	$800,000		Document	FCR&D	FY2011
Fission Product Transmutation in Mixed Radiation Fields	Idaho State University	$800,000		Document	FCR&D	FY2011
Life Prediction of Spent Fuel Storage Canister Material	Massachusetts Institute of Technology	$899,826		Document	FCR&D	FY2011
Active Interrogation using Photofission Technique for Nuclear Materials Control and Accountability	Oregon State University	$900,000		Document	FCR&D	FY2011
Anisotropic Azimuthal Power and Temperature Distribution on Fuel Rod: Impact of Hydride Distribution	Pennsylvania State University	$631,956		Document	FCR&D	FY2011
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$1,000,000		Document	FCR&D	FY2011
Recovery of Uranium from Seawater: Preparation and Development of Polymer-Supported Extractants	City College of New York, Hunter	$363,716		Document	MSTR	FY2011
Microemulsions and Aggregation Formation in Extraction Processes for Used Nuclear Fuel: Thermodynamics and Structural Studies	University of California, Irvine	$1,000,000		Document	FCR&D	FY2011
One-Dimensional Nanostructures for Neutron Detection	North Carolina State University	$455,629		Document	MSTR	FY2011
Optimized Processing Fabrication Paths for Larger Heats of Nanostructured Ferritic Alloys	University of California, Santa Barbara	$1,000,000		Document	FCR&D	FY2011
Feasibility and Safety Assessment for Advanced Reactor Concepts Using Vented Fuel	Oregon State University	$600,000		Document	MSTR	FY2011
Basic Physics Data: Measurement of Neutron Multiplicity from Induced Fission	University of Michigan	$973,364		Document	FCR&D	FY2011
Development of an Efficient Meso-Scale Multi-Phase Flow Solver in Nuclear Applications	City College of New York	$505,858		Document	NEAMS	FY2011
High Temperature Transducers for Online Monitoring of Microstructure Evolution	Pennsylvania State University	$455,628		Document	MSTR	FY2011
Radionuclide Incorporation and Long Term Performance of Apatite Waste Forms	University of Michigan	$862,500		Document	FCR&D	FY2011
Multiscale Modeling and Uncertainty Quantification for Nuclear Fuel Performance	Colorado State University	$1,098,250		Document	NEAMS	FY2011
Laser-Arc Hybrid Welding of Thick Section Ni-base Alloys- Advanced Modeling and Experiments	Pennsylvania State University	$536,117		Document	MSTR	FY2011
Actinide Foil Production for MPACT Research	University of Nevada-Las Vegas	$156,897		Document	FCR&D	FY2011
Fundamental Studies of the Role of Grain Boundaries on Uniform Corrosion of Advanced Nuclear Reactor Materials	Drexel University	$1,098,250		Document	NEAMS	FY2011
Correlates of Sensitive Technologies	Texas A&M University	$509,467		Document	MSTR	FY2011
Enriched Boron-Doped Amorphous Selenium Based Position-Sensitive Solid-State Thermal Neutron Detector for MPACT Applications	University of South Carolina	$1,000,000		Document	FCR&D	FY2011
Phenomena-based Uncertainty Quantification in Predictive Coupled-Physics Reactor Simulations	Texas A&M University	$1,098,250		Document	NEAMS	FY2011
Improved Safety Margin Characterization of Risk from Loss of Offsite Power	Texas A&M University	$600,000		Document	MSTR	FY2011
Development of Advanced High Uranium Density Fuels for Light Water Reactors	University of Wisconsin-Madison	$1,000,000		Document	FCR&D	FY2011
Characterization of Modeling of Grain Boundary Chemistry Evolution in Ferritic Steels Under Irradiation	University of Michigan	$1,098,250		Document	NEAMS	FY2011
Diffusion, Thermal Properties and chemical Compatibilities of Select MAX Phases with Materials for Advanced Nuclear Systems	Drexel University	$535,927		Document	NEET	FY2011
A High Temperature-Tolerant and Radiation-Resistant In-Core Neutron Sensor for Advanced Reactors	The Ohio State University	$455,629		Document	MSTR	FY2011
Developing the User Experience for a Next Generation Nuclear Fuel Cycle Simulator	University of Wisconsin-Madison	$1,200,000		Document	FCR&D	FY2011
Development of Multiscale Materials Modeling Techniques and Coarse-Graining Strategies for Predicting Materials Degradation in Extreme Irradiation Environments	University of Tennessee, Knoxville	$750,000		Document	NEAMS	FY2011
A New Light Weight Structural Material for Nuclear Structures	North Carolina State University	$399,490		Document	NEET	FY2011
Pathway Aggregation in the Risk Assessment of Proliferation Resistance and Physical Protection (PR&PP) of Nuclear Energy Systems	The Ohio State University	$534,471		Document	MSTR	FY2011
Experimental Investigation of Convection and Heat Transfer in the Reactor Core for a VHTR	City College of New York	$1,118,856		Document	RCRD&D	FY2011
Preparation of High Purity, High Molecular-Weight Chitin from Ionic Liquids for Use as an Adsorbate for the Extraction of Uranium from Seawater	University of Alabama	$338,260		Document	MSTR	FY2011
Graphite Microstructural Characterization Using Time-Domain and Correlation-Based Ultrasonics	Johns Hopkins University	$1,199,997		Document	RCRD&D	FY2011
Selectivity in Ligand Binding to Uranyl Compounds: A Synthetic, Structural, Thermodynamic and Computational Study	University of California-Berkeley	$500,000		Document	MSTR	FY2011
Methodology Development for Passive Component Reliability Modeling in a Multi-Physics Simulation Environment	The Ohio State University	$533,457		Document	RCRD&D	FY2011
Development of Seismic Isolation Systems Using Periodic Materials	University of Houston	$538,154		Document	MSTR	FY2011
Pebble Fuel Handling and Reactivity Control for Salt-Cooled High Temperature Reactors	University of California, Berkeley	$612,721		Document	RCRD&D	FY2011
Innovative Elution Processes for Recovering Uranium from Seawater	University of Idaho	$400,000		Document	MSTR	FY2011
Self-Sustaining Thorium Boiling Water Reactors	University of California, Berkeley	$1,145,932		Document	RCRD&D	FY2011
Development of Austenitic ODS Strengthened Alloys for Very High Temperature Applications	University of Illinois-Urbana Champaign	$538,154		Document	MSTR	FY2011
High Fluency Low Flux Embrittlement Models of LWR Reactor Pressure Vessel Embrittlement and a Supporting Database from the UCSB ATR-2 Irradiation Experiment	University of California, Santa Barbara	$1,199,607		Document	RCRD&D	FY2011
Enhancement of the Extraction of the Uranium from Seawater	University of Maryland	$400,000		Document	MSTR	FY2011
A Research Program for Fission Product/Dust Transport in HTGR's	University of Missouri-Columbia	$1,157,367		Document	RCRD&D	FY2011
Transient Safety Analysis of Fast Spectrum TRU Burning LWR with Internal Blankets	University of Michigan	$599,475		Document	MSTR	FY2011
Development and Validation of a Lifecycle-based Prognostics Architecture with Test Bed Validation	University of Tennessee, Knoxville	$846,315		Document	RCRD&D	FY2011
Development of Novel Sorbents for Uranium Extraction from Seawater	University of North Carolina, Chapel Hill	$400,000		Document	MSTR	FY2011
In-situ Condition Monitoring of Components in Small Modular Reactors Using Process and Electrical Signature Analysis	University of Tennessee, Knoxville	$650,000		Document	RCRD&D	FY2011
Radiation Behavior of High-Entropy Alloys for Advanced Reactors	University of Tennessee, Knoxville	$538,159		Document	MSTR	FY2011
Technical Development for S-CO2 Advanced Energy Conversion	University of Wisconsin	$815,000		Document	RCRD&D	FY2011
Rapid Computer Aided Ligand Design and Screening of Precious Metal Extractants from TRUEX Raffinate with Experimental Validation	Washington State University	$500,000		Document	MSTR	FY2011
Ag Transport Through Non-Irradiated and Irradiated SiC	University of Wisconsin-Madison	$1,055,456		Document	RCRD&D	FY2011
Critical Heat Flux Phenomena at High Pressure and Low Mass Fluxes: Tests and Models	University of Wisconsin-Madison	$1,199,781		Document	RCRD&D	FY2011
Modeling and Test Validation of a Reactor Cavity Cooling System with Air	University of Wisconsin-Madison	$1,199,988		Document	RCRD&D	FY2011
Transient Mixed Convection Validation for NGNP	Utah State University	$635,860		Document	RCRD&D	FY2011
Alternative High-Performance Ceramic Waste Forms	Alfred University	$840,000	This project aims to advance fundamental understanding of the kinetics of structural evolution of crystalline ceramic waste forms. The structure/property relationships will be identified and will reveal new formulations, improved processing routes, and strategies for improved performance or ceramic waste forms.	Document	FCR&D	FY2012
Surface Layer Bulk Glass Interface Evolution with Aqueous Corrosion	Alfred University	$880,000	This project will investigate the links between the morphology, structure and chemistry of surface layer-bulk glass interface and the long-term corrosion-reaction kinetics using in-situ and ex-situ experiments. The understanding will result in improved models for long-term predictive behavior of high-level-waste (HLW) glasses under repository conditions.	Document	FCR&D	FY2012
Improved Accident Tolerance of Austenitic Stainless Steel Cladding through Colossal Supersaturation with Interstitial Solutes	Case Western Reserve University	$850,000	This project aims to develop new case-hardened austenitic stainless steels by saturating them with materials that improve their mechanical properties, corrosion resistance and radiation resistance. This project, if successful, will result in safer, longer-lasting, and more accident tolerant fuel claddings.	Document	FCR&D	FY2012
Optimization of Deep Borehole Systems for HLW Disposal	Massachusetts Institute of Technology	$850,000	Researchers aim to carry out a comprehensive evaluation of the deep borehole option for disposal of used nuclear fuel and high livel waste. The models developed will predict potential movement of water through natural and engineered barriers and release of radionuclides to the biosphere which will aide in site selection.	Document	FCR&D	FY2012
Scholarship for Nuclear Communications and Methods for Evaluation of Nuclear Project Acceptability	Massachusetts Institute of Technology	$800,000	Researchers will work to develop a model to characterize the factors affecting social acceptance of nuclear projects with potential stakeholders. The resultant model will strengthen the ability to design and implement large projects more efficiently, leading to higher rates of success of future nuclear projects.	Document	FCR&D	FY2012
Accurate Holdup Calculations with Predictive Modeling and Data Integration	North Carolina State University	$875,000	Researchers will develop and use state-of-the-art radiation transport codes to account accurately for the fissile material in a nuclear materials processing facility. An accurate estimation of the materials will allow for ensured radiological safety, security, waste management and efficient plant operation.	Document	FCR&D	FY2012
Novel Metal Sulfides to Achieve Effective Capture and Durable Consolidation of Radionuclides	Northwestern University	$760,000	Researchers will evaluate the effectiveness of chalcogenide based materials design novel metal sulfides to effectively capture and store of radioisotopes released during reprocessing of used nuclear fuel. This project will focus on understanding structure-property relationships to enable refined and direct synthesis approaches for improved and cost-efficient nuclear waste forms.	Document	FCR&D	FY2012
Nonlinear Ultrasonic Diagnosis and Prognosis of ASR Damage in Dry Cask Storage	Northwestern University	$885,000	Researchers aim to use nondestructive damage characterization methods to detect, manage and mitigate the degradation/damage mechanisms of dry cask storage systems for nuclear fuels. This project, if successful, will provide tools that will allow the prediction of the reliability and the safety of concrete structures in dry cask storage systems.	Document	FCR&D	FY2012
Prototype Demonstration of Gamma-Blind Tensioned Metastable Fluid Neutron/Multiplicity/Alpha Detector- Real Time Methods for Advanced Fuel Cycle Applications	Texas A&M University	$875,000	This project aims to create a prototype demonstration of a novel neutron/alpha detector based on a technology that is blind to gamma field used fuel. The prototype, if successful, will enhance instrumentation for monitoring real-time material balance during various stages of the nuclear cycle.	Document	FCR&D	FY2012
Testing of Sapphire Optical Fiber and Sensors in Intense Radiation Fields, when Subjected to Very High Temperatures	The Ohio State University	$885,000	The researchers on this project will investigate the performance of sapphire optical fibers and sensors in reactor environments. The project, if successful, will result in improved instrumentation to understand the behavior and predict performance of nuclear fuel systems at the microstructural level.	Document	FCR&D	FY2012
Concrete Materials with Ultra-High Damage Resistance and Self-Sensing Capacity for Extended Nuclear Fuel Storage Systems	University of California, Irvine	$800,000	Researchers aim to design a new class of multifunctional concrete materials. This project, if successful, will result in a novel multifunctional concrete material that possesses inherent degradation monitoring capability and is suitable for an extended storage system for the used nuclear fuel.	Document	FCR&D	FY2012
Development of Innovative Accident Tolerant High Thermal Conductivity UO2 Fuel Pellets with a Diamond Dopant	University of Florida	$800,000	Researchers will evaluate the use of diamond nanoparticles composite material in innovative accident tolerant fuel pellets. This could significantly improve both the thermal conductivity of fuel pellets and light water reactors' efficiency safety.	Document	FCR&D	FY2012
Probabilistic Multi-Hazard Assessment of Dry Cask Structures	University of Houston	$865,000	This project aims to investigate the performance of dry cask storage systems under multiple hazard systems (earthquake, tornados, combined with aging effects) using a probabilistic multi-hazard framework. This framework will be validated based on experimental research and will provide improved models for safety and reliability of spent nuclear fuels during storage and transportation.	Document	FCR&D	FY2012
Measurement of Irradiated Pyroprocessing Samples via Laser Induced Breakdown Spectroscopy	University of Idaho	$820,000	This project aims to use advanced characterization techniques to investigate microstructural changes and the micromechanisms related to irradiation induced damage in used nuclear fuels and waste forms. This project, if successful, will result in enhanced models to predict the structural and chemical response of used fuel and waster forms during interim storage and permanent disposal.	Document	FCR&D	FY2012
Elastic/Inelastic Measurement Project	University of Kentucky	$880,523	Researchers will measure nuclear data for elastic/inelastic scattered neutrons on coolants and structural materials. The data generated, will be useful for future R&D programs that will study innovative next generation LWR and future fast systems.	Document	FCR&D	FY2012
Electrochemical Corrosion Studies for Modeling Metallic Waste Form Release Rates	University of Nevada- Las Vegas	$790,000	This project aims to use advanced electrochemical methods to investigate the corrosion related degradation of metal alloys used for housing fission products. The data obtained from this study will allow for the prediction of the long-term behavior of the metallic host phase materials over geological time-scales.	Document	FCR&D	FY2012
Thermodynamic and Microstructural Mechanisms in the Corrosion of Advanced Ceramic Tc-bearing Waste Forms and Thermophysical Properties	University of Nevada- Las Vegas	$795,000	This project team will harvest thermodynamic and microstructural data on the evolution of ceramic based waste forms. The data will be used to advance the current state-of-the-art methodology used for isolation and stabilization of fission products and improve on nuclear fuel recycling processes.	Document	FCR&D	FY2012
Development and Experimental Benchmark of Simulations to Predict Used Nuclear Fuel Cladding Temperatures during Drying and Transfer Operations	University of Nevada- Reno	$745,000	Researchers will conduct experiments to investigate and develop advanced computational models of heat transfer in post-pool-storage drying operations. This project, if successful, will result in tools that can be used to design efficient drying processes to as to ensure suitability for dry-cask systems for long-term storage and transport.	Document	FCR&D	FY2012
Better Radiation Response and Accident Tolerance of Nanostructured Ceramic Fuel Materials?	University of Tennessee	$815,000	Researchers will use novel experimental methods to investigate the links between microstructure, phase stability and damage evolution in nanostructured ceramic fuel materials. The project will study fuel materials at temperatures and irradiation conditions relevant to operation and accidental scenarios.	Document	FCR&D	FY2012
Radiation and Thermal Effects on Used Nuclear Fuel and Nuclear Waste Forms	University of Tennesssee	$770,000	This project aims to investigate the structural and chemical response of used nuclear fuel and waste forms during interim storage and permanent disposal. If successful, this project will generate models that will allow the prediction of structural evolution and hence the radiological safety and security of nuclear fuel and waste forms.	Document	FCR&D	FY2012
Seismic Performance of Dry Casks Storage for Long-Term Exposure	University of Utah	$873,319	Researchers will evaluate the mechanical performance of dry-cask storage under seismic loading for mid-term operational periods. Simulations will include scenarios for freestanding, anchored, and vaulted casks. The experimental tests will also evaluate the dynamic seismic response of freestanding and anchored dry-cask storage prototypes, providing recommendations for optimal Interim Spent Fuel Storage Installations (ISFSIs) design.	Document	FCR&D	FY2012
Validation Experiments for Spent-Fuel Dry-Cask In-Basket Convection	Utah State University	$690,000	Researchers in this project aim to conduct experiments that generate data on natural convection through a fuel assembly. The data will be used to validate the computational models being developed for nuclear safety and design.	Document	FCR&D	FY2012
Re-Branding the Nuclear Fuel Cycle	Virginia Commonwealth University	$850,000	This project will create a comprehensive framework for the evaluation of alternative fuel cycle systems that will be used to identify and analyze key elements related to long-term management of nuclear fuels , with the ultimate goal to develop a communications strategy to reach stakeholders.	Document	FCR&D	FY2012
Advanced Characterization of Molecular Interactions in TALSPEAK-like Separations Systems	Washington State University	$875,000	Researchers will use advanced characterization techniques (experimental and computational) to improve understanding of the molecular level processes/interactions during separation processes for advanced fuel cycles. The understanding of these interactions will be used to develop more robust and streamlined separation processes for advanced fuel cycles.	Document	FCR&D	FY2012
Coupling of Nuclear Waste Form Corrosion and Radionuclide Transport in Presence of Relevant Repository Sediments	Washington State University	$885,000	Researchers will conduct experiments to understand the mechanisms responsible for the corrosion of nuclear waste forms in realistic chemical environments. The data generated from these experiments will enable increased reliability of the models used to predict the waste form performance in repository environments.	Document	FCR&D	FY2012
Stationary Liquid Fuel Fast Reactor (SLFFR) Concept for TRU Burning	Purdue University	$450,000	Reasearchers will investigate a new type of molten metallic fuel reactor concept that will consume hazardous transuranic waste. The liquid fuel alloy has several advantages over solid fuel fast reactors that are used for the same purpose.	Document	MSTR	FY2012
ABR for TRU Transmutation with Breed & Burn Thorium Blanket for Improved Economics and Resource Utilization	University of California- Berkeley	$450,000	The research team will use detailed neutronic analysis for a new Advanced Burner Reactor concept with low conversion ratio. The concept will use a new core shape to improve the utilization of neutrons to perform breed and burn.	Document	MSTR	FY2012
New Materials for High Temperature Thermoelecric Power Generation	University of California, Davis	$450,000	Reasearchers will work to develop nanostructured and other new materials to support the development of higher efficiency thermoelectric devices. These devices convert thermal energy to electricity with no moving parts. The new materials will operate at higher efficiencies and over a wider temperature range than those currently available--an important quality for future nuclear-powered deep space exploration.	Document	MSTR	FY2012
Microscopic Fuel Particles Produced by Self-Assembly of Actinide Nanoclusters on Carbon Nanomaterials	University of Notre Dame	$440,000	Reasearchers will develop the mechanisms, conditions and protocols to prepare uranium-carbon nanocomposite materials to make them more flexible. This could result in the generation of wholesale electricity, providing process heat, and providing power for households.	Document	MSTR	FY2012
High Hydrogen Content Graphene Hydride Compounds & High Cross-Section Cladding Coatings for Fast Neutron Detection	University of South Carolina	$430,000	This project will exploit recent breakthroughs to grow epitaxial graphene on commercial SiC wafers. This will allow researchers to develop a new detection method for fast neutrons. In addition, it will lead to better and more compact neutron detection system.	Document	MSTR	FY2012
Reducing Actinide Production Using Inert Matrix Fuels	University of Texas- Austin	$435,000	Reasearchers will perform a neutronic analysis, a thermal-hydraulic analysis and a simulation of fuel decay heat as a functionof fuel burnup, to determine if inert matrix fuel in coventional reactors will continue to be licensable. If successful, the inert matrix fuel mixtures will reduce harmful transuranic components in the fuel discharge streams at a level comparable to a fast reactcor burner.	Document	MSTR	FY2012
An Integrated Fuel Depletion Calculator for Fuel Cycle Options Analysis	University of Texas- Austin	$395,000	Reasearchers use new analysis techniques to better predict nuclear fuel behavior. The new model will allow improved fuel cycle for a larger number of users.	Document	MSTR	FY2012
Atomic-Scale to Meso-Scale Simulation Studies of Thermal Ageing and Irradiation Effects in Fe-Cr Alloys	Boston University	$874,997	Reasearchers will develop predictive, multi-scale simulation tools for iron-chromium alloys, which are expected to be key components of advanced steels envisioned as fuel cladding and structural components for Generation IV reactors. Such modeling is necessary to avoid resource intensive and costly thermal and neutron irradiation experiments to obtain required performance data.	Document	NEAMS	FY2012
Validation Data and Model Development for Fuel Assembly Response to Seismic Loads	George Washington University	$862,435	Reasearchers will conduct experiments that will provide comprehensive data characterizing the dynamics of the fluid and the structure in Pressurized Water Reactors (PWR) fuel assemblies under seismic loads (earthquakes and loss of coolant accidents). Completion of their project will greatly benefit the safety of existing and future nuclear reactors.	Document	NEAMS	FY2012
Uncertainty Quantification and Management for Multiscale Nuclear Materials Modeling	Georgia Institute of Technology	$743,444	Reasearchers will address the question of uncertainty propogation and error estimates associated with model prediction of material behavior under irradiation. Their work will facilitate a better understanding of the connection of various unit processes to collective responses in a multiscale model chain enabling the development of high strength and high ductility materials.	Document	NEAMS	FY2012
Fuel and Core Design Options to Overcome the Heavy Metal Loading Limit and Improve Performance and Safety of Liquid Salt Cooled Reactors	Georgia Insitute of Technology	$784,689	Reasearchers will examine new options for fuel and core designs in liquid salt cooled reactors where the current standard of TRISO type fuel has limitations due to loading characteristics. The research could enable new, more feasible fuel-core-reload options that will improve safety and performance parameters.	Document	RCRD&D	FY2012
Nonlinear Ultrasonic Techniques to Monitor Radiation Damage in RPV and Internal Components	Georgia Institute of Technology	$877,000	Reasearchers will explore new nondestructive materials evaluation and monitoring techniques utilizing nonlinear ultrasonic measurements . This technique will allow researchers to assess remaining useful life of select reactor components. Breakthroughs in this area will lead to the ability to characterize radiation damage in reactor pressure vessels and other components-leading to a clearer definition of reactor safety margins.	Document	RCRD&D	FY2012
Intergral Reactor Containment Condensation Model and Experimental Validation	Oregon State University	$871,119	Reasearchers will conduct experiments to enhance the safety and efficiency of small modular reactors (SMRs). This project will assess the impact of high-pressure steam condensation on steel containment vessels to be used for SMR deigns.	Document	RCRD&D	FY2012
Investigation of Natural Circulation Instability and Transients in Passively Safe Small Modular Reactors	Purdue University	$871,100	Reasearchers will perform scaled experiments to study the thermal-hydraulic instabilities that can occur in Small Modular Reactors (SMR) which rely on natural circulation cooling during normal operation and accident conditions. Their work will not only improve our understanding of general natural circulation instability but also lead to the development of stability criteria and predictability in the operation of SMRÃs.	Document	RCRD&D	FY2012
Thermoelectric-Driven Sustainable Sensing and Actuation Systems for Fault-Tolerant Nuclear Incidents	State University of New York, Stony Brook	$599,802	Reasearchers will examine the use of solid-state thermoelectric generators to produce electricity to sense and opeate during both normal and abnormal situations. This will provide indefinite monitoring of key components during power outages or station blackouts.	Document	RCRD&D	FY2012
Experimental and CFD Studies of Coolant Flow Mixing within Scaled Models of the Upper and Lower Plenums of NGNP Gas-Cooled Reactors	Texas A&M University	$713,051	Reasearchers will model the internal coolant flow of a prismatic core very high temperature reactor (VHTR) by using large eddy simulation tools. This method will enable more accurate prediction of flow field characteristics and better evaluation of VHTR behavior under operational and accidental conditions.	Document	RCRD&D	FY2012
Demonstrating Hybrid Heat Transport and Energy Conversion System Performance Characterization Using Intelligent Control Systems	University of Idaho	$877,000	Reasearchers will demonstrate an intelligent control systems in a hybrid energy conversion loop for a next generation nuclear power plant. Hybrid energy systems are a method of optimizing the use of natural resources for energy production. Hybrid systems present an opportunity to develop domestic energy sources to improve energy security.	Document	RCRD&D	FY2012
Advanced Reactor-Intermediate Heat Exchanger (IHX) Coupling: Theoretical Modeling and Experimental Validation	University of Idaho	$869,997	Reasearchers will model the behavior of the Advanced Reactor Intermediate Heat Exchanger Chemical Process system and develop advanced control techniques that take into account abnormal scenarios. The data and information obtained will assist in the development of intelligent control systems for next generation nuclear reactor systems.	Document	RCRD&D	FY2012
Irradiation Performance of Fe-Cr Base Alloys	University of Illinois- Urbana Champaign	$876,332	Reasearchers will perform post-radiation analysis and develop tools for future development and application of the Fe-Cr class of alloys. The results of this research will lead to better modeling of performance and development of an alloy designated as the primary choice for reactor fuel cladding and structural applications in advanced systems.	Document	RCRD&D	FY2012
Accelerated Irradiations for High Dose Microstructures in Fast Reactor Alloys	University of Michigan	$831,876	Reasearchers will determine the extent to which high dose rate irradiation can be used as an irradiation damage tool to understand microstructure evolution at high doses and temperatures relevant to advanced fast reactors. The project will provide fundamental understanding of the effectiveness of this process and thus of microstructure development in irradiated materials.	Document	RCRD&D	FY2012
Mitigating IASCC of Reactor Core Internals by Post-Irradiation Annealing Advanced Mitigation Strategies	University of Michigan	$876,985	Reasearchers will determine the optimum Post-irradiation annealing (PIA)-driven mitigation strategy to extend the potential lifetime of light water reactors. Samples that have already been irradiated in a light water reactor will be used to test PIA treatments to understand IASCC initiation and propoagation, annealing kinetics, the role of microstructure features in irradation hardening and localized deformation, and the optimum mitigation strategy based on PIA.	Document	RCRD&D	FY2012
Experimentally Validated Numerical Models for Effects of Non-Isothermal Turbulent Mixing on Wall Stresses in High Temperature Reactors	University of Pittsburgh	$876,422	Reasearchers will develop a comprehensive experimentally validated computational framework for the turbulent mixing in the lower plenum of a very high temperature reactor (VHTR). Through CFD modeling and experimental validation, the results from this project will lay the groundwork for future stress analysis, failure and fatigue studies, and uncertainty quantification for the VHTR system.	Document	RCRD&D	FY2012
Role of Defects in Swelling and Creep of Irradiated SiC	University of Wisconsin- Madison	$875,350	Reasearchers will study mechanisms controlling both radiation swelling and radiation creep in silicon carbide. These two effects are crucial to understanding the issues associated with the brittle silicon carbide composite. Success in this project will ground progress in the adoption of silicon carbide for reactor solutions, particularly as fuel cladding.	Document	RCRD&D	FY2012
Advanced Supercritical Carbon Dioxide Brayton Cycle Development	University of Wisconsin, Madison	$877,000	Reasearchers will investigate the benefits of utilizing advanced Brayton cycles with supercritical carbon dioxide in new reactor systems and components. Benefits of this research include improvement of analysis and performance of components currently utilizing these cycles as well as the potential for a large scale advanced CO2 power system.	Document	RCRD&D	FY2012
Mechanical Behavior of UO2 at Sub-grain Length Scales: Quantification of Elastic, Plastic and Creep Properties via Microscale Testing	Arizona State University	$800,000	Reasearchers will develop techniques to measure properties at sub-grain scales using depleted Uranium Oxide samples. The project will provide a framework to measure sub-grain scale mechanical properties, as well as provide experimental data to improve the understanding of advanced oxide fuels.	Document	FCR&D	FY2013
The Impacts of Pore-Scale Physical and Chemical Heterogeneities on the Transport of Radionuclide-Carrying Colloids	Colorado School of Mines	$800,000	Reasearchers will identify the dominant transport mechanisms to develop models that predict radionuclide distribution in porous materials. Experimental and computational models will be created that couple pore-scale geometric and interfacial structures. Simulators such as these are a necessary step towards fully predictive models for field-scale applications in the future.	Document	FCR&D	FY2013
Recovery of Uranium from Seawater: Polymer-Supported Aminophosphinates as Selective Extractants	Hunter College, CUNY	$399,999	Reasearchers will prepare a polymer-supported extractant for the recovery of uranium from seawater. The project will focus on primary amines that could provide a 3-fold increase in uranium capture capacity than current methods.	Document	FCR&D	FY2013
In-pile Thermal Conductivity Characterization with Single-laser Heating/Time Resolved Raman	Iowa State University	$800,000	Reasearchers will develop a time-resolved Raman-based thermal conductivity measurement system to improve remote in-pile thermal conductivity measurement. These measurements will provide new insights into the behavior of materials exposed to extreme radiation and temperature environments. Understanding the behavior of materials at the microstructural level will support optimized fuel designs.	Document	FCR&D	FY2013
Organic Speciation and Interactions in ALSEP - One Step Partitioning Process of Minor Actinides, Lanthanides, and Fission Products	Oregon State University	$600,000	Reasearchers will investigate the Actinide-Lanthanide Separation (ALSEP) process organic phase prior to aqueous phase separation and after aqueous separation phases of bare and metal-loaded acids. Quantifying these effects can be used to determine how an engineering scale process will perform and generate an accurate chemical model for the system.	Document	FCR&D	FY2013
Glass Composition and Solution Speciation Effects on Stage III Dissolution	Pennsylvania State University	$700,000	Reasearchers will study the chemical and structural triggers of long-term vitrified nuclear waste form behavior. They will study a range of waste glass compositions in corrosive environments. The study will improve understanding of the long-term residual rate and may provide new options for environmental control of glass dissolution rates.	Document	FCR&D	FY2013
Correlating Thermal, Mechanical, and Electrical Coupling Based Multiphysics Behavior of Nuclear Materials Through In-Situ Measurements	Purdue University	$800,000	Reasearchers will use in-situ experimental techniques to monitor the influence of extreme conditions on fuel cladding. The project will establish an in-situ experimental setup that can predict change in thermal properties and their correlation with mechanical properties and correlate such changes to changes in microstructural and chemical features.	Document	FCR&D	FY2013
Creation of a Geant4 Muon Tomography Package for Imaging of Nuclear Fuel in Dry Cask Storage	Purdue University	$440,000	Reasearchers will develop a simulation and analysis package to aid in the non-destructive assessment of sealed used nuclear fuel dry casks using cosmic ray muons. Cosmic ray muon tomography allows for non-destructive assessment that can independently verify and identify weapons grade material sealed within dense dry casks.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Two-stage Fast Reactor Fuel Cycle Options for Optimum Resource Utilization and Waste Management	Purdue University	$400,000	Reasearchers will evaluate the two different two-stage fast reactor fuel cycle options that will offer efficient use of uranium resources and the ability to burn actinides and long-live fission products. Evaluation of these fast fuel cycle options will serve as a useful complement to the options currently being considered in the Fuel Cycle Options Campaign.	Document	FCR&D	FY2013
Mixed Metal Phosphonate-Phosphate Resins for Separation of Lanthanides from Actinides	Texas A&M University	$650,000	Reasearchers will use ion exchangers to cleanly separate lanthanides and curium from reusable actinides. The study will assist in the development of an inexpensive, simple way in which to separate lanthanides from actinides found in used nuclear fuel rods and to recover a large portion of the usable fuel.	Document	FCR&D	FY2013
Safeguards in Pyroprocessing: an Integrated Model Development and Measurement Data Analysis	The Ohio State University	$626,151	Reasearchers will develop a comprehensive and effective safeguards approach for a pyroprocessing facility to support safeguards for future fuel cycles in the United States. The new approach and design will focus directly on the special nuclear materials in the electrorefiner where actinides are separated from fission products through electrochemical process.	Document	FCR&D	FY2013
Using Ionic Liquids for the Development of Renewable Biopolymer-Based Adsorbents for the Extraction of Uranium from Seawater and Testing Under Marine Conditions	University of Alabama	$400,000	Reasearchers will explore the fundamental engineering parameters for a renewable high-performance adsorbent for the extraction of uranium from sweater based on a recently proven ionic liquid (IL)-chitin platform. The project will use the platform to develop a versatile, modifiable adsorbent and characterize its performance and degradation in marine conditions.	Document	FCR&D	FY2013
Developing Ultra-Small Scale Mechanical Testing Methods and Microstructural Investigation Procedures for Irradiated Materials.	University of California, Berkeley	$800,000	Reasearchers will develop new small-scale mechanical testing techniques to allow for the estimation or direct measurement of bulk properties. The combined experiments and modeling will significantly enhance the statistics and information that can be obtained on small radioactive archived samples, as well as new ion beam irradiated specimens.	Document	FCR&D	FY2013
Improved Delayed-Neutron Spectroscopy Using Trapped Ions	University of California, Berkeley	$400,000	Reasearchers will develop innovative spectroscopy techniques to measure the decay of fission fragments. The resulting data from these new techniques will be used to better understand reactor kinetics under accident conditions and failure scenarios.	Document	FCR&D	FY2013
Thermally and Chemically Responsive Nanoporous Materials for Efficient Capture of Fission Product Gases	University of California, Davis	$750,000	Reasearchers will create new nanoporous materials that will be highly effective at capturing fission product gases. These materials would be relevant to both reactor fuels applications and reprocessing operations. Tests will be performed in carbon based and nitride based nanostructures, with the most promising materials from the modeling perspective undergoing further testing.	Document	FCR&D	FY2013
Multiphase Nanocrystalline Ceramic Concept for Nuclear Fuel	University of California, Irvine	$800,000	Researchers will study the use of nanoparticles and nanostructured ceramics to create new materials that can extend the service life and increase efficiency for nuclear fuel. Multiphase nanocrystalline ceramics will be used to design simulated nuclear fuel that can provide added plasticity, better radiation tolerance and improved thermal conductivity.	Document	FCR&D	FY2013
Development of Novel Porous Sorbents for Extraction of Uranium from Seawater	University of Chicago	$400,000	Reasearchers will develop a highly porous sorbent for the extraction of uranium from seawater. Previous research has established sorbent performance. This project will use past foundational studies to design and investigate a new nanocomposites that will be processed into tacks or braids for field tests in seawater tests. The technology may also be used for other metals.	Document	FCR&D	FY2013
Microwave Readout Techniques for Very Large Arrays of Nuclear Sensors	University of Colorado, Boulder	$799,937	Reasearchers will develop a powerful readout technique based on microwave transmission and reflection. The technique will enable very large arrays of diverse sensor types for nuclear materials quantification and tracking. It will provide more accurate data on material composition and quantity.	Document	FCR&D	FY2013
BiI3 Gamma-Ray Spectrometers for Reliable Room-Temperature Nuclear Materials Safeguarding	University of Florida	$799,999	Reasearchers will develop gamma-ray spectrometers based on BiI3 single crystals for MPACT applications such as burnup validation quantification, improved assay of plutonium, determination of uranium enrichment and overall monitoring spent fuel within the fuel cycle. The project will improve energy resolution, efficiency and environmental performance with this new gamma-ray detector.	Document	FCR&D	FY2013
Innovative Coating of Nanostructured Vanadium Carbide on the F/M Cladding Tube Inner Surface for Mitigating the Fuel Cladding Chemical Interactions	University of Florida	$760,276	Researchers will develop barrier coatings on the inner surface of fuel cladding tubes to improve performance of materials at elevated temperatures and high neutron exposures in fast reactors. The project will develop and test a low temperature coating process of nanostructured vanadium carbide that will provide a benchmark for use in future studies.	Document	FCR&D	FY2013
Doubling the Life of Concrete Structures	University of Idaho	$800,000	Reasearchers will use nanoscale techniques to develop methods for doubling the service life of concrete structures. They will study the effect of temperature load and temperature cycling (freezing and thawing) on the durability of concrete with nanoscale viscosity modifiers. The project will benefit from non-destructive evaluation of concrete performance through electrochemical techniques.	Document	FCR&D	FY2013
Off-Gas Treatment: Evaluation of Nano-structured Sorbents for Selective Removal of Contaminants	University of Idaho	$785,910	Reasearchers will evaluate nanostructured sorbent materials for their effectiveness in removing and immobilizing radionuclides for the off-gas treatment from used nuclear fuel recycling operations. The project aims at achieving near-zero emissions of radionuclides by capturing them from the off-gas of recycling operations, allowing for the development of advanced fuel cycles.	Document	FCR&D	FY2013
Innovative Elution Processes for Recovering Uranium and Transition Metals from Amidoxime-Based Sorbents	University of Idaho	$399,864	Reasearchers will develop a new two-step elution process to achieve total recovery of uranium and effective recycling of the sorbent. The extraction process would selectively remove uranium from the sorbent with little or no damage. The process would then remove transition metals and regenerate the sorbent for repeated use, making uranium extraction from seawater economically viable.	Document	FCR&D	FY2013
Performance of a Steel/Oxide Composite Waste Form for Combined Waste Streams from Advanced Electrochemical Processes over Geologic Time Scales	University of Illinois at Chicago	$700,000	Reasearchers will develop and validate a mechanistically-based corrosion model for cermet-type waste forms, creating a testing protocol and modeling approach for predicting long-term performance. The study will apply novel electrochemical testing and modeling methods to the behavior of metal/oxide phase boundaries to evaluate waste form performance.	Document	FCR&D	FY2013
Enhancement of the Extraction of Uranium from Seawater	University of Maryland, College Park	$400,000	Reasearchers will develop and optimize novel adsorbents for uranium recovery from seawater. The team will use radiation-induced grafting of organic phosphates onto polymers. The experiments will use ocean water, with mechanistic analysis, to provide a solid basis for large-scale demonstration of the performance of the new adsorbents in ocean environments.	Document	FCR&D	FY2013
Improving the Understanding of the Coupled Thermal-Mechanical-Hydrologic Behavior of Consolidating Granular Salt	University of New Mexico	$800,000	Reasearchers will increase the understanding of granular salt seal materials for shafts, drifts and boreholes. By coupling thermal, mechanical and hydrological responses, the study will result in greater confidence in granular salt consolidation as a principal strategy for closure and isolation of long-term waste repositories.	Document	FCR&D	FY2013
Fission Fragment Yield Data in Support of Advanced Reactor Technology	University of New Mexico	$399,816	Reasearchers will produce a highly accurate data set for thermal fission. These precision data are necessary for high-accuracy simulations of nuclear criticality, transmutation rates, radiation effects and heating as well as for nuclear fuel, material accounting and identification needs.	Document	FCR&D	FY2013
Molecular dynamics-based simulations of bulk/interfacial structures and diffusion behaviors in nuclear waste glasses	University of North Texas	$700,000	Reasearchers will generate accurate atomic structural models for use in Monte Carlo simulations of the dissolution of nuclear waste glasses. Large-scale molecular dynamics-based computer simulations will be used to investigate self-diffusion behaviors, interfacial structure, and other structures formed during dissolution of these glasses.	Document	FCR&D	FY2013
U3Si2 Fabrication and Testing for Implementation into the BISON Fuel Performance Code	University of South Carolina	$800,000	Reasearchers will fabricate, test and model a high uranium density, advanced nuclear fuel that operates at a much lower temperature and stores less energy. The work will deliver key research data on creep and grain growth, improving economics, through possible power uprates, and advancing accident tolerant fuels research.	Document	FCR&D	FY2013
Structural Health Monitoring of Nuclear Spent Fuel Storage Facilities	University of South Carolina	$738,618	Reasearchers will develop a nuclear structural health monitoring system based on a sensing technology that monitors material degradation and aging for dry cask storage systems. The low-cost, low-profile sensors will perform on-demand monitoring of the structural integrity of individual components as well as the entire system.	Document	FCR&D	FY2013
ORIGEN-based Nuclear Fuel Depletion Module for Fuel Cycle Assessment	University of Tennessee at Knoxville	$755,181	Reasearchers will develop a flexible reactor analysis module for the CYCLUS fuel cycle simulator based on established tools for reactor fuel depletion and decay. They will use ORIGEN, a mature and experimentally validated code, affording greater flexibility and allowing for accurate evaluations of impacts of both present and future fuel cycle options.	Document	FCR&D	FY2013
Cost and System Analysis of Innovative Fuel Resources Concepts	University of Texas at Austin	$295,960	_This project will develop and test braided polymer fiber adsorbents that surpass the sorption capacity, selectivity and durability of the best existing technology to recover uranium from seawater.	Document	FCR&D	FY2013
Risk Assessment of Structural Integrity of Transportation Casks	University of Utah	$789,296	Reasearchers will assess the loss of structural integrity of transportation casks and fuel cladding after extended storage. This risk assessment will conduct experimental tests and simulations to evaluate the structural performance of fuel, fuel assemblies and cask components when subjected to vibration and impact loads during transport.	Document	FCR&D	FY2013
Market-Based and System-Wide Fuel Cycle Optimization	University of Wisconsin, Madison	$612,731	Reasearchers will create market and economic optimizers to improve calculations for the CYCLUS fuel cycle simulator. The team will leverage existing optimization software frameworks within the simulator to resolve top level policy questions. The optimizations will allow CYCLUS to move beyond static material compositions, providing a holistic view of the fuel cycle system.		FCR&D	FY2013
Optical Fiber Based System for Multiple Thermophysical Properties for Glove Box, Hot Cell and In-Pile Applications	Utah State University	$799,975	Reasearchers will use a small pressure vessel to develop a robust technique for the measurement of multiple thermophysical properties at very high temperatures. The technique will lead to a system design moving toward the eventual measurement of irradiated fuels in a glovebox and/or hot cell with all sensors and electronics outside of the glovebox and/or hot cell.	Document	FCR&D	FY2013
Development of a Nano-Modified Concrete for Next Generation of Storage Systems	Vanderbilt University	$796,268	Reasearchers will use nano-sized and nano-structured particles based on enhanced reactivity to develop a superior concrete for the long-term storage of used nuclear fuel. The project will use state-of-the-art experimental chemical and mechanical characterizations and computation analysis to assess the performance of nano-modified concretes.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Thorium Fuel Cycle Options	Vanderbilt University	$797,995	Reasearchers will develop six fuel cycle data packages for multi-stage, thermal fuel cycles which incorporate thorium. These new fuel cycle data packages will provide the opportunity to examine fuel cycle options beyond those which have traditionally been considered. A thorium fuel cycle database will also be assembled as a basis for thorium literature for future evaluations of the thorium fuel cycle.	Document	FCR&D	FY2013
Enhanced Shielding Performance of HLW Storage Packages via Multi-Component Coatings	Virginia Polytechnic Institute and State University	$796,947	Reasearchers will develop a multi-layer composite that will enhance long-term storage and facilitate safe transport of storage packages. This novel multi-layer, multi-component coating would create an outer shield material that is resistant to the corrosion, radiation, diffusion and thermal cycling processes that affect fuel packages during long term storage.	Document	FCR&D	FY2013
Managing Zirconium Chemistry and Phase Compatibility in Combined Process Separations for Minor Actinide Partitioning	Washington State University	$700,000	Reasearchers will address unique challenges for combining TRUEX and TALSPEAK processes for partitioning of lanthanides and minor actinides. The project will develop improved information on the thermodynamics of fission product zirconium and develop a framework for an organic phase solvation model. Combined process development could streamline separations processes.	Document	FCR&D	FY2013
Advances in the Recovery of Uranium from Seawater: Studies Under Real Ocean Conditions	Woods Hole Oceanographic Institution	$398,882	Reasearchers will provide infrastructure and expertise for marine testing of currently available adsorbents in real ocean conditions. The team will move adsorbent research from the lab to field testing in order to quantify sorptive properties and uranium uptake. The project will provide valuable field data that will show the potential of large scale applications of these technologies.	Document	FCR&D	FY2013
NEUP Project 20-19172: Irradiation of Sensors and Adhesive Couplants for Application in LWR Primary Loop Piping and Components		$497,881	Reasearchers paln to attach ultrasonic transducers to substrates using various adhesive couplants that will be irradiated at elevated temperature to simulate LWR primary loop conditions at the PULSTAR reactor at North Carolina State University. Ultrasonic data will be taken in-situ. Subsequently, the sensors and couplant interfaces will be characterized using the LAMDA facility at ORNL. The results will be used to benefit a parallel EPRI project on online monitoring of cracks in LWR primary loop piping._	Document	R&D NSUF	FY2013
NEUP Project 20-19404: Extension of MSTDB to Provide a High-Quality, Validated Thermochemical Database for Predicting/Simulating Corrosion in Molten Salt Reactor SystemsUniversity of South Carolina		$600,000	Reasearchers will generate a validated, consistent database of initial fuel compositions and potential corrossion products of fluoride and chloride salts, allowing for important phenomena predictions in molten salt reactors to guide confident decisions. The database will be integral to the currently being developed Molten Salt Thermochemical Database (MSTDB), structured to allow use by commercial and open source codes._	Document	NEAMS	FY2013
Lower Length Scale Characterization and Validation of Formation and Stability of Helium Bubbles in Nano-structured Ferritic Alloys under Irradiation	Clemson University	$399,870	Reasearchers will provide a fundamental knowledge about the formation and stability of ultra-fine helium bubbles within 14YWT after neutron/ion irradiation for further design of new advanced structural materials with a characteristic high density nanoparticles feature which can increase the mechanical strength, hardness, irradiation resistance and the operational temperature range of materials.	Document	NEAMS	FY2013
Three-Dimensional Fuel Pin Model Validation by Prediction of Hydrogen Distribution in Cladding and Comparison with Experiment	Pennsylvania State University	$800,000	Reasearchers will validate important three-dimensional aspects of the fuel pin modeling by using specialized numerical modeling techniques coupled with laboratory experiments to validate existing models for predicting fuel performance in light water reactors.	Document	NEAMS	FY2013
Collocation-Based Surrogate Models for Uncertainty Quantification and Validation of Coupled, Multiphysics Fuel Performance Simulation Tools	University of Michigan	$596,835	Reasearchers will provide the necessary high fidelity, coupled, multiphysics fuel performance simulator for computational modeling and develop surrogates which will accelerate and focus the validation of the coupled codes. This will be achieved by utilizing the high fidelity coupled fuel performance, thermal-hydraulics and neutronics codes BISON/STAR-CCM+/MPACT and an innovative collocation-based surrogate methodology.	Document	NEAMS	FY2013
Multi-Resolution In-Situ Testing and Mutliscale Simulation for Creep Damage Fatigue Damage Analysis of Alloy 617	Arizona State University	$800,000	This project will develop novel testing and experimentally validated prediction methodologies for micro-structural damage mechanisms of structural materials for advanced reactor systems. The investigations will focus on the characterization and testing of specific metal alloys, but the proposed testing and life-prediction methodologies are applicable to other structural materials as well.	Document	RCRD&D	FY2013
Novel High Temperature and Radiation Resistant Infrared Glasses and Optical Fibers for Sensing in Advanced Small Modular Reactors	Clemson University	$800,000	Clemson University, in partnership with the Iowa State University and the Pacific Northwest National Laboratory, will develop novel optical materials with improved heat and radiation exposure resistance in order to enable in-vessel fiber optic sensing for advanced Small Modular Reactors.	Document	RCRD&D	FY2013
Validation Data Acquisition in HTTF during PCC Events	George Washington University	$800,000	Reasearchers at the George Washington University and Oregon State University will collaborate with NASA Langley Research Center to measure flow velocities in a high temperature test facility. This work supports the development of very-high temperature reactors with passive safety systems.	Document	RCRD&D	FY2013
Advanced High Temperature Inspection Capabilities for Small Modular Reactors	Iowa State University	$790,822	The objective of this project is to develop non-destructive evaluation techniques for advanced small modular reactors. The research will provide key enabling inspection technologies needed to support the design and the reactor component performance validation process for advanced small modular reactors.	Document	RCRD&D	FY2013
Experimental and Computational Investigations of Plenum-to-Plenum Heat Transfer under Natural Circulation in a Prismatic Very High Temperature Reactor	Missouri University of Science and Technology	$799,999	Reasearchers will perform experimental and computational investigations to study heat transfer and natural circulation phenomena in very-high temperature reactors. The study will assist in the ability to predict and analyze passive safety systems.	Document	RCRD&D	FY2013
New Mechanistic Models of Creep-Fatigue Crack Growth Interactions for Advanced High Temperature Reactor Components	Oregon State University	$790,790	Reasearchers will create and validate a robust, multi-scale, numerical model to predict material degradation in nickel-based reactor alloys. If successful, this project will provide better numerical tools for reactor designers and greatly improve their capability to design against material failures for reactor alloys in the long term.	Document	RCRD&D	FY2013
Self-Powered Wireless Dual-mode Langasite Sensor for Pressure/Temperature Monitoring of Nuclear Reactors	State University of New York, Stony Brook	$800,000	This research will develop a novel self-powered wireless hybrid sensor that can accurately monitor both pressure and temperature using a single device without requiring external electricity, even in extreme harsh environments.	Document	RCRD&D	FY2013
Compact Heat Exchanger Design and Testing for Advanced Nuclear Reactors and Advanced Power Cycles	The Ohio State University	$800,000	The goal of this project is to investigate optimal heat exchanger designs for advanced reactors. The research will study the optimization of printed circuit heat exchangers for specific fluids under a variety of conditions as well as perform numerical modeling. Experiments will focus on thermal performance and heat stress during extreme conditions.	Document	RCRD&D	FY2013
Fundamental Understanding of Creep-Fatigue Interactions in 9Cr-1MoV Steel Welds	The Ohio State University	$798,000	This project will advance the state of knowledge and fundamental understanding of deforming materials and welds under loading conditions. Specifically, new integrated testing procedures will be evaluated and applied for conditions that are most detrimental to material stability leading to improved predictions of life expectancy for reactor steels and welds.	Document	RCRD&D	FY2013
Advanced Mechanistic 3D Spatial Modeling and Analysis Methods to Accurately Represent Nuclear Facility External Event Scenarios	The Ohio State University	$800,000	Reasearchers will develop three-dimensional characterization uncertainty analysis for commercial power plants. The project will involve combining experts from the fields of seismic structural modeling and advanced methods of risk assessment. This effort is expected to result in next generation tools that can be used for assessment of seismic risks.	Document	RCRD&D	FY2013
Tritium Mitigation/Control for Advanced Reactor Systems	The Ohio State University	$400,000	Reasearchers will develop a fluoride salt cooled high-temperature reactor featuring a specialized system to control tritium production. If successful, this will result in a significant reduction in size and cost in comparison to other reactor designs.	Document	RCRD&D	FY2013
A Pebble-Bed Breed and Burn Reactor	University of California, Berkeley	$400,000	Reasearchers will assess the feasibility of designing a type of metal cooled reactor able to establish and maintain operation when fueled with depleted uranium. If successful, this reactor will offer at least a 30-fold increase in the uranium ore utilization versus that achieved in contemporary light water reactors without the need for fuel reprocessing and recycling.	Document	RCRD&D	FY2013
Investigation of Thermal Aging Effects on the Evolution of Microstructure and Mechanical Properties of Cast Duplex Stainless Steels	University of Maryland, College Park	$799,966	This research will provide a better understanding of the microstructural evolution and simultaneous change in mechanical response during aging. The results of the research will provide data that can be used to estimate degraded mechanical properties for an 80-year service life of light water reactors.	Document	RCRD&D	FY2013
Model validation using CFD-grade experimental database for NGNP Reactor Cavity Cooling Systems with water and air	University of Michigan	$799,348	Reasearchers will use advanced innovative instrumentation to build a high-resolution experimental database and to use the novel experimental data to assess and further develop the predictive capabilities of computer codes for thermal hydraulics and computational fluid dynamics. The improved models developed by this project will also have the direct benefit of improving the predictive capability of the passive systems of third generation light water reactors and small modular reactor systems.	Document	RCRD&D	FY2013
Long-Term Prediction of Emissivity of Structural Material for High Temperature Reactor Systems	University of Missouri	$799,117	Reasearchers will study specific types of emissivity driven cooling from a variety of materials that are relevant to nuclear reactors. The research will provide a basis for numerical modeling to support reactor development.	Document	RCRD&D	FY2013
Advanced I&C for Fault-Tolerant Supervisory Control of Small Modular Reactors	University of Pittsburgh	$800,000	The purpose of this research is to develop advanced instrumentation and control techniques for supervisory control of advanced small modular reactors. This research supports the operational goals of small modular reactor concepts through the development of improved oversight and surveillance techniques.	Document	RCRD&D	FY2013
Corrosion of Structural Materials for Advanced Supercritical Carbon-Dioxide Brayton Cycle	University of Wisconsin-Madison	$798,672	Reasearchers will study a variety of materials for corrosion resistance under conditions that improve power conversion. In addition to studying the corrosion resistance of the materials, researchers will study the effect of additives to mitigate corrosion. Development of corrosion theories and modeling aimed at prediction of long-term corrosion will be the underlying theme throughout the project.	Document	RCRD&D	FY2013
Component and Technology Development for Advanced Liquid Metal Reactors	University of Wisconsin-Madison	$798,920	In support of liquid metal cooled reactors, the University of Wisconsin, Madison will evaluate advanced alloys and ceramics that come in contact with liquid metals. Additionally, a robust oxygen sensor and for use in liquid metals will be developed in order to better evaluate corrosion profiles in support of diagnostic testing.	Document	RCRD&D	FY2013
A New Paradigm for Understanding Multi-phase Ceramic Waste Form Performance	Clemson University	$800,000	Researchers will use advanced characterization tools to develop 3-D microstructural data that can be incorporated into computer-based simulations in order to predict the performance of waste forms. Materials system modeling will incorporate elemental release and the interconnected microstructural network of phases to better understand performance and degradation, which will accelerate waste form acceptance in repository settings.	Document	FCR&D	FY2014
Controlling Hexavalent Americium: A Centerpiece to a Compact Nuclear Fuel Cycle	Colorado School of Mines	$800,000	Researchers will develop and exploit the fundamental chemistry of Americium to enable an industrially viable means to co-recover the major and minor actinide elements from used nuclear fuel. The results would be a significant step forward in the development of aqueous separations approaches designed to recover the U-Am actinides based on the availability of the hexavalent oxidation state.	Document	FCR&D	FY2014
Zeolite Membranes for Krypton/Xenon Separation from Spent Nuclear Fuel Reprocessing Off-Gas	Georgia Institute of Technology	$400,000	Researchers will develop a high-performance, lower-cost zeolitic membrane process for Kr/Xe separations during spent nuclear fuel processing. Current separation methods are not considered economical and a membrane process would have relatively lower cost, equipment size, and ambient operating temperature. The process would form a sound basis for further development of this transformative separation technology for the nuclear fuel cycle.	Document	FCR&D	FY2014
Optimizing Polymer-Grafted Amidoxime-based Adsorbents for Uranium Uptake from Seawater	Georgia Institute of Technology	$399,999	Researchers will work to increase the adsorbent capacity and selectivity toward uranium by optimizing the adsorbent morphology, synthesis variables, and conditioning parameters and by investigating the rate-limiting variables through transport and reaction modeling. A novel adsorption/partition concept that has the potential to substantially increase the adsorbent capacity will be tested, making uranium from seawater extraction more economically viable.	Document	FCR&D	FY2014
Extraction of Uranium from Seawater: Design and Testing of a Symbiotic System	Massachusetts Institute of Technology	$400,000	Researchers will develop a seawater uranium extraction system that will work symbiotically with an offshore windmill by utilizing the structure, mooring and power of the windmill, while increasing the energy harvested by the installation. Uranium will be extracted by an adsorbent polymer belt, which will be cycled through the seawater and an elution plant located at the base of the windmill tower. Increasing the frequency of harvesting could overcome current economic barriers to seawater uranium extraction.	Document	FCR&D	FY2014
Imaging a Dry Storage Cask with Cosmic Ray Muons	Oregon State University	$799,871	Researchers will develop an imaging system to monitor the content of a dry storage cask with cosmic ray muons. A very large amount of plutonium under nuclear safeguards is contained in used fuel assemblies stored in dry storage casks. Muon imaging will allow a cost effective and reliable way to evaluate dry storage cask content and integrity before transport.	Document	FCR&D	FY2014
Apatite and sodalite based glass-bonded waste forms for immobilization of 129I and mixed halide radioactive wastes	Rutgers University	$800,000	Researchers will develop advanced and chemically durable waste forms for immobilizing 129I (aqueous based reprocessing of fuel) and mixed-halide wastes (molten-salt processing of fuel) by low temperature synthesis. Halide-containing sodalite and calcium phosphate-based apatite minerals will be synthesized, consolidated and tested for chemical durability. The project will provide needed baseline data for the development of advanced waste forms for immobilization of iodine and mixed-halide wastes.	Document	FCR&D	FY2014
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$350,000	Researchers will develop modeling tools supported by experiments for off-gas capture from future nuclear-fuel recycling facilities. Target species include tritium, iodine, krypton, and xenon. The models are intended to provide path forward recommendations to develop off-gas treatment adsorption processes. The project will contribute to the evaluation of options for environmentally acceptable recycle systems.	Document	FCR&D	FY2014
Development of high performance ODS alloys	Texas A&M University	$800,000	Researchers will study swelling, radiation hardening and changes in mechanical properties of ODS alloys to develop two sets of advanced ODS alloys. Two sets of first-round candidate alloys that have already undergone extensive development and testing will evaluate irradiation performance. The study will meet the need for high strength, radiation-tolerant cladding and core components that have enhanced resistance to void swelling.	Document	FCR&D	FY2014
Rare Earth Electrochemical Property Measurements and Phase Diagram Development in a Complex Molten Salt Mixture for Molten Salt Recycle	The Ohio State University	$800,000	Researchers will investigate rare earth (RE) properties in complex molten salt mixtures. In a molten salt recycle approach, the RE drawdown by electrolysis is a key step in which REs are separated from salt containing other fission products. Investigation of RE electrolysis must consider the electrochemical properties of the REs. We propose to conduct studies of detailed experiments and corresponding models to provide the physical properties and phase diagrams required to predict the performance of RE drawdown for processing complex molten salts.	Document	FCR&D	FY2014
Studies of Lanthanide Transport in Metallic Nuclear Fuels	The Ohio State University	$800,000	Researchers will study the redistribution of lanthanides and migration of lanthanides to the fuel surface. The mechanisms of lanthanide transport in metallic fuel based on the novel discovery of a Ôliquid-likeÕ transport mechanism will be studied analytically and experimentally. The project will develop a fundamental understanding of lanthanide fission product migration and redistribution in advanced metallic nuclear fuels, and theory and data to mitigate fuel-cladding chemical interactions.	Document	FCR&D	FY2014
Computational and Experimental Studies of Microstructure-Scale Porosity in Metallic Fuels for Improved Gas Swelling Behavior	University of Arkansas	$796,823	Researchers will study the microstructure of metallic uranium alloy fuels, and their resistance to densification, to minimize in-pile irradiation swelling through bimodal pore size distribution. The project will develop a predictive approach to design metallic fuel microstructures for optimal swelling resistance and fission gas retention.	Document	FCR&D	FY2014
Improved Hybrid Modeling of Spent Fuel Storage Facilities	University of California, Berkeley	$645,393	Researchers will develop a variance reduction method for computational transport that will improve the ability to design and operate monitoring systems for interim used fuel installations through enhanced modeling and simulation. This new tool will demonstrate that modeling calculations can be done more accurately in less time than with current tools and will perform studies characterizing how changes in material, cask configurations, and number of casks could impact monitoring systems.	Document	FCR&D	FY2014
Selective ligands for uranyl via combinatorial peptoid libraries: A synthetic, structural, thermodynamic and computational study	University of California, Berkeley	$400,000	Researchers will study how donor ligands bind to the uranyl ion, UO22+, with the longer-term goal of using this information to tackle selective recognition of uranyl in aqueous solution. The study will impact underlying approaches to controlling the behavior of uranium in these systems. The actinide separation technology could be used in several areas including uranium extraction from seawater, nuclear waste remediation and nuclear materials.	Document	FCR&D	FY2014
Combining Experiments and Simulations of Extraction Kinetics and Thermodynamics in Advanced Separation Processes for Used Nuclear Fuel	University of California, Irvine	$799,938	Researchers will study how the kinetics and thermodynamics of metal ion extraction in advanced separation processes for used nuclear fuel can be described by molecular dynamic (MD) simulations and how the simulations can be validated by experimental data. The project would have broad impacts on several separations processes including advanced TALSPEAK, ALSEP and GANEX by increasing the confidence and accuracy of computer modeling of metal ion extraction._	Document	FCR&D	FY2014
Effect of Metallic Li on the Behavior of Metals in Molten Salts	University of Nevada, Reno	$458,250	Researchers will identify the effect of metallic lithium on materials that are used in molten salt recycling. The study will try to understand how the presence of Li(0) in molten salts affects the degradation of alloys. Studying these changes will help accurately predict container material behavior and longevity.	Document	FCR&D	FY2014
Assessment of Corrosion Resistance of Promising Accident Tolerant Fuel Cladding under Reactor Conditions	University of Notre Dame	$800,000	Researchers will assess the corrosion behavior of accident tolerant fuel candidate iron-based alloys under normal LWR operating conditions consisting of high temperature, relevant water chemistry and irradiation. The assessment will produce data about possible irradiation-accelerated corrosion rates of iron-based alloys, and the mechanisms by which such corrosion rates are accelerated. The project will advance the selection of appropriate replacements for Zircaloy cladding.	Document	FCR&D	FY2014
Functionalized Porous Organic Polymers as Uranium Nano-Traps for Efficient Recovery of Uranium from Seawaterr	University of South Florida	$399,000	Researchers will develop functionalized porous organic polymers, or Ônano-trapsÕ for extraction of uranium from seawater. This technique allows for increased surface area and custom-designed pore size and chemistry to fit specific parameters. The adsorbent materials have high efficiency and effectiveness for uranium recovery from seawater, providing a potential supply for nuclear fuel.	Document	FCR&D	FY2014
Enhanced Accident-Tolerant Fuel Performance and Reliability for Aggressive iPWR/SMR Operation	University of Tennessee	$799,967	To develop a process that evaluates operational and safety performance of reactor-and-fuel combinations by integrating whole-core 3D neutronics with MOOSE/BISON fuel performance assessments via explicit time and space dependent fuel rod operational power histories. The project will be valuable in analyzing and evaluating accident tolerant fuel concepts and furthering the understanding of reactor physics and fuel performance aspects of key accident tolerant fuel concepts.	Document	FCR&D	FY2014
Nuclear Technology R&D Strategies in an Era of Energy Price Uncertainty	University of Texas, Austin	$799,112	Researchers will identify nuclear technology options that are competitive over a wide range of plausible future business environments. No single nuclear technology or business practice will be the best choice across all or even most future conditions. The study will focus on hybrid nuclear-fossil technologies, energy storage and conversion, which will result in an identification of nuclear strategies that can succeed under future market conditions.	Document	FCR&D	FY2014
Development and Optimization of Voltammetric Methods for Real Time Analysis of Electrorefiner Salt with High Concentrations of Actinides and Fission Products	University of Utah	$621,612	Researchers will develop an advanced voltammetry method to pursue the objective of real time monitoring of actinide concentrations in electrorefiner salt. This will include experimental measurement of key parameters such as activity coefficients and exchange current density. It will also involve simulation of voltammetry processes based on first principles. The project will allow for real time measurements that could support the commercialization of pyroprocessing.	Document	FCR&D	FY2014
Development of Self-Healing Zirconium-Silicide Coatings for Improved Performance of Zirconium-Alloy Fuel Cladding	University of Wisconsin, Madison	$798,621	Researchers will study the deposition of self-healing zirconium-silicide coatings on zirconium-alloy fuel cladding material to improve corrosion resistance under normal and accident conditions. Under these conditions, Zr-Si coating evolves into a highly protective functionally-graded multilayered system. The study will lead to improved performance of zirconium-alloy fuels._	Document	FCR&D	FY2014
Thermal Conductivity in Metallic Fuels	Virginia Polytechnic Institute and State University	$799,837	Researchers will calculate the thermal conductivity of metallic uranium and neptunium alloys, including the effects of noble gasses, using density functional theory. The experiments will validate the calculated effective thermal conductivity using the MARMOT code and by helping determine DFT simulation parameters. The study works to improve fuel lifetime by understanding its thermal behavior.	Document	FCR&D	FY2014
SiC-ODS Alloy Gradient Nanocomposites as Novel Cladding Materials	Virginia Polytechnic Institute and State University	$799,998	Researchers will combine nuclear nanomaterial design, processing, testing, and characterization efforts to develop revolutionary materials that can withstand neutron irradiation for long period of time using nanostructured SiC and oxide dispersion strengthened steel. The ultimate objective is to offer new cladding materials with increased corrosion resistance, strength, and creep resistance in both steady state and accident conditions.	Document	FCR&D	FY2014
Experimental Breeder Reactor II Benchmark Evaluation	Idaho State University	$400,000	Researchers will develop a benchmark evaluation of the Experimental Breeder Reactor II (EBR-II). During nearly 30 years of operation numerous experiments were conducted at EBR-II. The most significant of these experiments were conducted in 1986 demonstrating inherent safety features in loss of flow without reactor scram and loss of heat sink without reactor scram. Benchmark evaluation will be valuable for the reactor design efforts in the United States and South Korea.	Document	MSNE	FY2014
Integral full core multi-physics PWR benchmark with measured data	Massachusetts Institute of Technology	$400,000	Researchers will introduce BEAVRS, a new multi-cycle full-core Pressurized Water Reactor (PWR) depletion benchmark based on two operational cycles of a commercial nuclear power plant. This project aims at addressing the uncertainty quantification of the measured data and on making this benchmark a true non-proprietary international benchmark for the validation of high-fidelity multi-physics computational tools.	Document	MSNE	FY2014
Benchmark Evaluation of PROTEUS Gas-Cooled Reactor Experiments	University of Florida	$400,000	Researchers will create International Reactor Physics Experiment Evaluation Project (IRPhEP) benchmarks using data from 1970s experiments of the neutronics of gas-cooled fast reactor (GCFR) designs investigated in the PROTEUS reactor. The GCFR-PROTEUS experiments fill a gap in current integral benchmark data. These experiments can provide validation of computational models and nuclear data for next generation reactors.	Document	MSNE	FY2014
An Investigation To Establish Multiphysical Property Dataset Of Nuclear Materials Based On In-Situ Observations And Measurements	Purdue University	$800,000	Researchers will create an in-situ measurement based experimental approach to develop experimental validation dataset for NEAMS based code validation. Particular emphasis is on supplying data set for multiphysics simulations in extreme conditions as a function of material microstructure.	Document	NEAMS	FY2014
Experimental Validation of UO2 Microstructural Evolutions for NEAMS tool MARMOT	University of Florida	$798,000	Researchers will experimentally validate MARMOT for predicting the microstructural evolutions of UO2 oxide fuel under the driving forces of high temperatures and large temperature gradient in reactors. By performing the experiments and simulations simultaneously using precisely defined initial conditions, the experiment data will provide direct benchmarking of the MARMOT code.	Document	NEAMS	FY2014
High-resolution time-resolved experiments on mixing and entrainment of buoyant jets in stratified environments	University of Michigan	$799,983	Researchers will study high spatial and time-resolution experimental data of the fluid dynamics phenomena of flow jets interacting with a stratified layer. The issue plays an important role in the safety of several reactor designs, including sodium-cooled reactors. The data addresses the NEAMS needs for the validation of high fidelity computational fluid dynamics methodologies.	Document	NEAMS	FY2014
Fundamental study of key issues related to advanced S-CO2 Brayton Cycle: prototypic HX development and Cavitation	Georgia Institute of Technology	$799,000	Researchers will study scientific and operational issues pertinent to compact heat exchanger systems and turbo-machinery. The project will work to resolve issues with the fabrication of diffusion bonded compact heat exchangers, alternate heat exchange technology for recuperators, and resolution of issues with cavitation and fluid instabilities.	Document	RCRD&D	FY2014
Advanced Models for Nondestructive Evaluation of Aging Nuclear Power Plant Cables	Iowa State University	$787,291	Researchers will develop advanced models that relate environmentally induced microstructural and chemical changes in cable insulation polymers to their macroscopic electrical parameters. These parameters will be measured and modeled over a wide range of the electromagnetic spectrum, covering several potential nondestructive evaluation techniques, enabling identification of the most sensitive techniques for future development.	Document	RCRD&D	FY2014
Development of Novel Functionally Graded Transition Joints for Improving the Creep Strength of Dissimilar Metal Welds in Nuclear Applications	Lehigh University	$800,000	Researchers will develop graded transition joints and improved creep life models for increasing the life of dissimilar metal welds (DMWs) in nuclear reactors. The research represents the first application of functionally graded material concepts for solving the problem of DMW failures through an integrated approach of additive manufacturing, modeling, microstructural characterization, and advanced strain-sensing techniques.	Document	RCRD&D	FY2014
Feasibility Assessment of a Micro Modular Reactor (MMR)	North Carolina State University	$400,000	Researchers will develop an innovative compact reactor concept that integrates power production, power conversion and electricity generation in a single unit: the Micro Modular Reactor (MMR). It is designed to be absolutely melt-down proof (MDP) under all circumstances including complete loss of coolant scenarios with no possible release of radioactive material, to have a cycle length of greater than 10 years, and to be highly proliferation resistant.	Document	RCRD&D	FY2014
Scaling Studies for Advanced Gas Reactor Concepts	Oregon State University	$681,834	Researchers will expand the utilization of the Oregon State University High Temperature Test Facility (HTTF) to validate a broader range of advanced high temperature reactors and events. The facility will be revised to add a detailed scaling analysis of additional gas reactor concepts including advanced gas-cooled, molten salt, and sodium cooled reactors.	Document	RCRD&D	FY2014
Fluid Stratification Separate Effects Analysis, Testing and Benchmarking	Oregon State University	$800,000	Researchers will study fluid stratification in high temperature gas reactors. Coolant stratification is the result of incomplete mixing of one or more fluids, leading to a density gradient, which may or may not dissipate under diffusive or convective effects. This combined analytical and experimental project seeks to investigate stratification driven by diffusive and convective mechanisms and is expected to yield insight into this phenomenon.	Document	RCRD&D	FY2014
Probabilistic Economic Valuation of Safety Margin Management Analysis	Oregon State University	$795,364	Researchers will use RAVEN and develop a companion software package to facilitate economic analysis of safety margins. The project is a proof of concept that will use techniques to examine the cost of improving safety margins vs. the risk of accidents from not improving safety margins. This analysis can be used to evaluate the economic viability of various plant upgrades.	Document	RCRD&D	FY2014
Novel Dissimilar Joints Between Alloy 800H and 2.25%Cr and 1%Mo Steel	Pennsylvania State University	$800,000	Researchers will fabricate and test dissimilar metal joints between a nickel base alloy and a steel with gradual variations of chemical composition, microstructure and properties in a manner that reduces abrupt thermal expansion mismatch and the resulting residual stresses. Data on structure and properties will serve as valuable inputs for the initiation of an ASME code case.	Document	RCRD&D	FY2014
Multi-Phase Model Development to Assess RCIC System Capabilities under Severe Accident Conditions	Texas A&M University	$564,246	Researchers will develop physics-based models of the Reactor Core Isolation Cooling (RCIC) System and incorporating them into a multi-phase code for validation. The project will tackle the current major challenges in RCIC System analysis and enable evaluation of two-phase thermodynamic aspects.	Document	RCRD&D	FY2014
Experimental Investigation and CFD Analysis of Steam Ingress Accidents in HTGRs	The Ohio State University	$800,000	Researchers will study the steam ingress scenario for HTGRs. The study will investigate thermal-hydraulic behavior and graphite oxidation of stream ingress phenomena to validate predictive CFD models. This work will resolve concerns about possible steam generator tube ruptures in a HTGR He-Steam Rankine cycle.	Document	RCRD&D	FY2014
Coiled Tube Gas Heaters For Nuclear Gas-Brayton Power Conversion	University of California, Berkeley	$800,000	Researchers will develop heat exchangers for Brayton-cycle power conversion in reactors using sodium, NaK, or salt as intermediate coolants. The proposed coiled tube gas heaters (CTGHs) are expected to have excellent power density, thermal shock/creep, in-service inspection, and reparability characteristics.	Document	RCRD&D	FY2014
Fundamental Studies of Irradiation-Induced Modifications in Microstructural Evolution and Mechanical Properties of Advanced Alloys	University of Illinois, Urbana-Champaign	$800,000	Researchers will develop and test a mechanism for predicting neutron irradiation performance for optimized Grade 92 and Alloy 709 for applications in advanced reactor systems. The work will employ ion irradiations and available information from neutron irradiations of related alloys to develop a basis for predicting the neutron irradiation performance of the optimized alloys.	Document	RCRD&D	FY2014
Integrated Computational and Experimental Study of Radiation Damage Effects in Grade 92 Steel and Alloy 709	University of Tennessee	$800,000	Researchers will develop a mechanistic understanding and predictive models of irradiation-induced microstructural evolution and resulting mechanical properties in optimized ferritic-martensitic Grade 92 steel and austenitic alloy 709 using multiscale simulations coupled with rigorous experimental validation. The project will provide insights into the correlation between ion irradiation and fast neutron damage.	Document	RCRD&D	FY2014
Meta-Level Design Guidance and Operator Performance Measures for Hybrid Control Rooms	Vanderbilt University	$799,869	Researchers will apply human factors engineering methods and relevant expertise from non-nuclear high-risk high-consequence domains toward the measurement of operator performance in analog, digital, and hybrid main control rooms. Performance measures will be developed for evaluating the situation awareness and decision-making proficiencies to support the transition to digital or hybrid control room displays.	Document	RCRD&D	FY2014

FY 2011 Research and Development Awards

A complete list of R&D projects with their associated abstracts is available below.

Title	Institution	Estimated Funding*	Project Description	Abstract	Project Type	Fiscal Year
Neutron Damage and MAX Phase Ternary Compounds	Drexel University			Document	IIR	FY2009
Atomistic Calculations of the Effect of Minor Actinides on Thermodynamic and Kinetic Properties of UO2+x	Georgia Institute of Technology			Document	IIR	FY2009
Maximum Fuel Utilization in Fast Reactors without Chemical Reprocessing	University of California, Berkeley			Document	IIR	FY2009
Developing a High Thermal Conductivity Fuel with Silicon Carbide Additives	University of Florida			Document	IIR	FY2009
Fabrication of Tungsten-Rhenium Cladding Materials via Spark Plasma Sintering for Ultra High Temperature Reactor Applications	University of Idaho			Document	IIR	FY2009
Ionic Liquid and Supercritical Fluid Hyphenated Techniques for Dissolution and Separation of Lanthanides, Actinides, and Fission Products	University of Idaho			Document	IIR	FY2009
Improved Fission Neutron Data Base for Active Interrogation of Actinides	University of Michigan			Document	IIR	FY2009
Utilization of Methacrylates and Polymer Matrices for the Synthesis of Ion Specific Resins	University of Nevada, Las Vegas			Document	IIR	FY2009
Improved LWR Cladding Performance by EPD Surface Modification Technique	University of Wisconsin, Madison			Document	IIR	FY2009
Advanced Models of LWR Pressure Vessel Embrittlement for Low Flux-High Fluence Conditions	University of California, Santa Barbara			Document	LWRS	FY2009
Irradiation Creep in Graphite	Boise State University			Document	NGNP	FY2009
Modeling the Stress Strain Relationships and Predicting Failure Probabilities For Graphite Core Components	Cleveland State University			Document	NGNP	FY2009
TRISO-Coated Fuel Durability Under Extreme Conditions	Colorado School of Mines			Document	NGNP	FY2009
An Innovative and Advanced Coupled Neutron Transport and Thermal Hydraulic Method (Tool) for the Design, Analysis and Optimization of VHTR/NGNP Prismatic Reactors	Georgia Institute of Technology			Document	NGNP	FY2009
Removal of 14C from Irradiated Graphite for Graphite Recycle and Waste Volume Reduction	Idaho State University			Document	NGNP	FY2009
Millimeter-Wave Thermal Analysis Development and Application to Gen IV Reactor Materials	Massachusetts Institute of Technology			Document	NGNP	FY2009
Accurate Development of Thermal Neutron Scattering Cross Section Libraries	North Carolina State University			Document	NGNP	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
Understanding Creep Mechanisms in Graphite with Experiments, Multiscale Simulations, and Modeling	North Carolina State University			Document	NGNP	FY2009
Simulations of the Thermodynamic and Diffusion Properties of Actinide Oxide Fuel Materials	University of Michigan			Document	AFCI	FY2009
Verification & Validation of High-Order Short-Characteristics-Based Deterministic Transport Methodology on Unstructured Grids	North Carolina State University			Document	NGNP	FY2009
Adsorptive Separation and Sequestration of Krypton, I and C14 on Diamond Nanoparticles	University of Missouri, Columbia			Document	AFCI	FY2009
Microscale Heat Conduction Models and Doppler Feedback	North Carolina State University			Document	NGNP	FY2009
Fundamental Understanding of Ambient and High-Temperature Plasticity Phenomena in Structural Materials in Advanced Reactors	Georgia Institute of Technology			Document	AFCI	FY2009
Development of Alternative Technetium Waste Forms	University of Nevada, Las Vegas			Document	AFCI	FY2009
Optimizing Neutron Thermal Scattering Effects in Very High Temperature Reactors	North Carolina State University			Document	NGNP	FY2009
Advanced Elastic/Inelastic Nuclear Data Development Project	Idaho State University			Document	AFCI	FY2009
Heterogeneous Recycling in Fast Reactors	Massachusetts Institute of Technology			Document	AFCI	FY2009
Quantification of UV-Visible and Laser Spectroscopic Techniques for Materials Accountability and Process Control	University of Nevada, Las Vegas			Document	AFCI	FY2009
Multiaxial Creep-Fatigue and CreepRatcheting Failures of Grade 91 and Haynes 230 Alloys Toward Addressing Design Issues of Gen IV Nuclear Power Plants	North Carolina State University			Document	NGNP	FY2009
Thermodynamic Development of Corrosion Rate Modeling in Iron Phosphate Glasses	Missouri University of Science and Technology			Document	AFCI	FY2009
Development of Subspace-Based Hybrid Monte Carlo-Deterministic Algorithms for Reactor Physics Calculations	North Carolina State University			Document	AFCI	FY2009
High-Fidelity Space-Time Adaptive Multiphysics Simulations in Nuclear Engineering	University of Nevada, Reno			Document	AFCI	FY2009
Improvements to Nuclear Data and Its Uncertainties by Theoretical Modeling	Rensselaer Polytechnic Institute			Document	AFCI	FY2009
Investigation of Countercurrent Helium-air Flows in Air-ingress Accidents for VHTRs	Ohio State University			Document	NGNP	FY2009
Sharp Interface Tracking in Rotating Microflows of Solvent Extraction	State University of New York at Stony Brook			Document	AFCI	FY2009
Bulk Nanostructured FCC Steels with Enhanced Radiation Tolerance	Texas A&M University			Document	AFCI	FY2009
Simulations of Failure via Three-Dimensional Cracking in Fuel Cladding for Advanced Nuclear Fuels	University of Texas, Dallas			Document	AFCI	FY2009
Testing of Performance of Optical Fibers Under Irradiation in Intense Radiation Fields, When Subjected to Very High Temperatures	Ohio State University			Document	NGNP	FY2009
Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels	Texas A&M University			Document	AFCI	FY2009
SiC Schottky Diode Detectors for Measurement of Actinide Concentrations from Alpha Activities in Molten Salt Electrolyte	The Ohio State University			Document	AFCI	FY2009
Computational Design of Advanced Nuclear Fuels	University of California, Davis			Document	AFCI	FY2009
Advanced Mesh-Enabled Monte Carlo Capability for Multi-Physics Reactor Analysis	University of Wisconsin, Madison			Document	AFCI	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
A Distributed Fiber Optic Sensor Network for Online 3-D Temperature and Neutron Fluence Mapping in a VHTR Environment	Texas A&M University			Document	NGNP	FY2009
Ab Initio Enhanced Calphad Modeling of Actinide Rich Nuclear Fuels	University of Wisconsin, Madison			Document	AFCI	FY2009
Investigation on the Core Bypass Flow in a Very High Temperature Reactor	Texas A&M University			Document	NGNP	FY2009
Development of Diffusion Barrier Coatings and Deposition Technologies for Mitigating Fuel Cladding Chemical Interactions (FCCI)	University of Wisconsin, Madison			Document	AFCI	FY2009
CFD Model Development and Validation for High Temperature Gas Cooled Reactor Cavity Cooling System (RCCS) Applications	Texas A&M University			Document	NGNP	FY2009
Thermal Properties of LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin, Madison			Document	AFCI	FY2009
Study of Air ingress across the duct during the accident conditions	Texas A&M University			Document	NGNP	FY2009
Verification of the CENTRM Module for Adaptation of the SCALE Code to NGNP Prismatic and PBR Core Designs	University of Arizona			Document	NGNP	FY2009
Integral and Separate Effects Tests for Thermal Hydraulics Code Validation for Liquid-Salt Cooled Nuclear Reactors	University of California, Berkeley			Document	NGNP	FY2009
Mechanisms Governing the Creep Behavior of High Temperature Alloys for Generation IV Nuclear Energy Systems	University of Cincinnati			Document	NGNP	FY2009
ALD Produced B2O3, Al2O3 and TiO2 Coatings on Gd2O3 Burnable Poison Nanoparticles	University of Colorado, Boulder			Document	NGNP	FY2009
Experimental Study and Computational Simulations of Key Pebble Bed Thermomechanics Issues for Design and Safety	University of Idaho			Document	NGNP	FY2009
Prediction and Monitoring Systems of Creep-Fracture Behavior of 9Cr-1Mo Steels for Reactor Pressure Vessels	University of Idaho			Document	NGNP	FY2009
Understanding Fundamental Material Degradation Processes in High Temperature Aggressive Chemomechanical Environments	University of Illinois, Urbana-Champaign			Document	NGNP	FY2009
Multi-Scale Multi-physics Methods Development for the Calculation of Hot-Spots in the NGNP	University of Michigan			Document	NGNP	FY2009
Corrosion and Creep of Candidate Alloys in High Temperature Helium and Steam Environments for the NGNP	University of Michigan			Document	NGNP	FY2009
Creation of a Full-Core HTR Benchmark with the Fort St. Vrain Initial Core and Validation of the DHF Method with Helios for NGNP Configurations	University of Michigan			Document	NGNP	FY2009
Fission Product Sorptivity in Graphite	University of Missouri, Columbia			Document	NGNP	FY2009
Identifying and Understanding Environment-Induced Crack Propagation Behavior in Ni-Based Superalloy INCONEL 617	University of Nevada, Las Vegas			Document	NGNP	FY2009
Graphite Oxidation Simulation in HTR Accident Conditions	University of New Mexico			Document	NGNP	FY2009
Non Destructive Thermal Analysis and In Situ Investigation of Creep Mechanism of Graphite and Ceramic Composites using Phase-sensitive THz Imaging & Nonlinear Resonant Ultrasonic Spectroscopy	University of Rochester			Document	NGNP	FY2009
Tritium Sequestration in Gen IV NGNP Gas Stream via Proton Conducting Ceramic Pumps	University of South Carolina			Document	NGNP	FY2009
Materials, Turbomachinery and Heat Exchangers for Supercritical CO2 Systems	University of Wisconsin, Madison			Document	NGNP	FY2009
Experimental Studies of NGNP Reactor Cavity Cooling System with Water	University of Wisconsin, Madison			Document	NGNP	FY2009
Assessment of Embrittlement of VHTR Structural Alloys in Impure Helium Environments	University of Wisconsin, Madison			Document	NGNP	FY2009
Modeling Fission Product Sorption in Graphite Structures	University of Wisconsin, Madison			Document	NGNP	FY2009
Liquid Salt Heat Exchanger Technology for VHTR Based Applications	University of Wisconsin, Madison			Document	NGNP	FY2009
Effect of Post-Weld Heat Treatment on Creep Rupture Properties of Grade 91 Steel Heavy Section Welds	Utah State University			Document	NGNP	FY2009
Alpha Radiolysis of Nuclear Solvent Extraction Ligands used for An(III) and Ln(III) Separations	California State University, Long Beach	$1,390,252		Document	FCR&D	FY2010
Predictive Maturity of Multi-Scale Simulation Models for Fuel Performance	Clemson University	$614,690		Document	FCR&D	FY2010
Freeze-casting as a Novel Manufacturing Process for Fast Reactor Fuels	Drexel University	$1,149,327		Document	FCR&D	FY2010
Fuel Performance Experiments on the Atomistic Level, Studying Fuel Through Engineered Single Crystal UO2	Idaho State University	$650,000		Document	FCR&D	FY2010
Development of A Self Biased High Efficiency Solid-State Neutron Detector for MPACT Applications	Rensselaer Polytechnic Institute	$810,141		Document	FCR&D	FY2010
Development of a Innovative High Thermal Conductivity UO 2 Ceramic Composites Fuel Pellets with Carbon Nano-Tubes Using Spark Plasma Sintering	University of Florida	$894,042		Document	FCR&D	FY2010
Exploration and Modeling of Structural Changes in Waste Glass under Corrosion	Pennsylvania State University	$1,377,444		Document	FCR&D	FY2010
Evaluation of materials for interim storage of spent fuel for more than 100 years	University of Michigan	$931,603		Document	FCR&D	FY2010
Implementation of On-the-Fly Doppler Broadening in MCNP5 for Multiphysics Simulation of Nuclear Reactors	University of Michigan	$406,712		Document	FCR&D	FY2010
Methods and tools to allow molecular flow simulations to be coupled to higher level continuum descriptions of flows in porous/fractured media and aerosol/dust dynamics	University of Missouri-Columbi	$541,286		Document	FCR&D	FY2010
Characterization and Modeling of Materials for Kr-Xe Separations	University of Nevada-Las Vegas	$989,800		Document	FCR&D	FY2010
Modeling Solute Thermokinetics in LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin-Madison	$616,073		Document	FCR&D	FY2010
Advanced Aqueous Separation Systems for Actinide Partitioning: Develop Fundamental Understanding of An(III)/Ln(III) Separation	Washington State University	$1,451,784		Document	FCR&D	FY2010
Consistent Multigroup Theory Enabling Accurate Coarse-Group Simulation of GenIV Reactors	Georgia Institute of Technology	$1,046,277		Document	GEN IV	FY2010
Studies of Deteriorated Heat Transfer in Prismatic Cores Stemming from Irradiation-Induced Geometry Distortion	Idaho State University	$1,287,921		Document	GEN IV	FY2010
Carbide Coatings for Nickel Alloys, Graphite, and Carbon/Carbon Composites to be Used in Fluoride Salt Valves	Johns Hopkins University	$1,183,239		Document	GEN IV	FY2010
Design, Testing, and Modeling of the Direct Reactor Auxiliary Cooling System for AHTRs	Ohio State University	$1,366,627		Document	GEN IV	FY2010
Monitoring microstructural evolution of Alloy 617 with nonlinear acoustics for remaining useful life prediction; multiaxial creep-fatigue and creep-ratcheting	Pennsylvania State University	$1,000,000		Document	GEN IV	FY2010
Development and Validation of Multidimensional Models of Supercritical CO 2 Energy Conversion Systems for Nuclear Power Reactors	Rensselaer Polytechnic Institute	$475,005		Document	GEN IV	FY2010
Multiscale Concrete Modeling for Aging Degradation	Mississippi State University	$345,941		Document	LWRS	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term and Elevated Temperature Irradiation: Modeling and Experimental Investigation	University of California-Berkeley	$1,320,667		Document	GEN IV	FY2010
Development of an advanced computational fluid dynamics technology for the next-generation nuclear reactor system analysis and safety margin characterization code	North Carolina State University	$418,199		Document	LWRS	FY2010
Development of Barrier Layers for the Protection of Candidate Alloys in the VHTR	University of California-Santa Barbara	$995,232		Document	GEN IV	FY2010
Precursor Derived Nanostructured Si-C-X Materials for Nuclear Applications	University of Washington	$899,518		Document	MRIIR	FY2010
Investigation of a Novel NDE Method for Monitoring Thermo-Mechanical Damage and Microstructure Evolution in Ferritic-Martensitic Steels for Generation IV Nuclear Energy Systems	University of Cincinnati	$833,109		Document	GEN IV	FY2010
Development and Testing of an Open-Loop Oscillator for Small Reactivity Worth Samples	Idaho State University	$597,252		Document	MRIIR	FY2010
Fission Product Transport in TRISO Particle Layers under Operating and Off-Normal Conditions	University of Michigan	$966,581		Document	GEN IV	FY2010
Understanding the Irradiation Behavior of Zirconium Carbide	Pennsylvania State University	$870,613		Document	MRIIR	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term Irradiation at Elevated Temperature: Critical Experiments	University of Michigan	$1,181,379		Document	GEN IV	FY2010
Modeling investigation of the stability and irradiation-induced evolution of nanoscale precipitates in advanced structural materials	University of Tennessee-Knoxville	$380,653		Document	MRIIR	FY2010
Three-dimensional NDE of VHTR Core Components via Simulation-based Testing	University of Minnesota	$1,366,163		Document	GEN IV	FY2010
Investigation of Laser Shock Peening for Enhancing Fatigue and Stress Corrosion Cracking Resistance of Nuclear Energy Materials	University of Cincinnati	$1,242,019		Document	MRIIR	FY2010
Failure Predictions for VHTR Core Components using a Probabilistic Continuum Damage Mechanics Model	University of Minnesota	$854,542		Document	GEN IV	FY2010
Irradiation Accelerated Corrosion of Reactor Core Materials	University of Michigan	$798,943		Document	MRIIR	FY2010
Development of a Scanning Microscale Fast Neutron Irradiation Platform for Examining the Correlation Between Local Neutron Damage and Graphite Microstructure	University of Missouri-Columbia	$703,064		Document	GEN IV	FY2010
Study of Interfacial Interactions using Thin Film Surface Modification: Radiation and Oxidation Effects in Materials	University of Wisconsin-Madison	$538,032		Document	MRIIR	FY2010
Development of Thermal Transient Flow Rate Sensors for High Temperature, Irradiation, Corrosive Environment	University of Nevada-Las Vegas	$451,269		Document	GEN IV	FY2010
Novel Engineered Refractory Materials for Advanced Reactor Applications	North Carolina State University	$1,129,304		Document	MRIIR	FY2010
Novel Methods of Tritium Sequestration: High Temperature Gettering and Separation Membrane Materials Discovery for Nuclear Energy Systems	University of South Carolina	$1,366,626		Document	GEN IV	FY2010
Heat Transfer Salts for Nuclear Reactor Systems - Chemistry Control, Corrosion Mitigation, and Modeling	University of Wisconsin-Madison	$1,352,040		Document	GEN IV	FY2010
Pulsed Magnetic Welding for Advanced Core and Cladding Steels	University of Wisconsin-Madison	$525,206		Document	GEN IV	FY2010
Corrosion in Supercritical Carbon Dioxide: Materials, Environmental Purity, Surface Treatments, and Flow Issues	University of Wisconsin-Madison	$651,447		Document	GEN IV	FY2010
Quantification of Cation Sorption to Engineered Barrier Materials Under Extreme Conditions	Clemson University	$1,171,380		Document	FCR&D	FY2011
In-Pile Instrumentation Multi-Parameter System Utilizing Photonic Fibers and Nanovision	Idaho State University	$1,199,990		Document	FCR&D	FY2011
Development of Plasmonically Cloaked Nanoparticles	Idaho State University	$800,000		Document	FCR&D	FY2011
Fission Product Transmutation in Mixed Radiation Fields	Idaho State University	$800,000		Document	FCR&D	FY2011
Life Prediction of Spent Fuel Storage Canister Material	Massachusetts Institute of Technology	$899,826		Document	FCR&D	FY2011
Active Interrogation using Photofission Technique for Nuclear Materials Control and Accountability	Oregon State University	$900,000		Document	FCR&D	FY2011
Anisotropic Azimuthal Power and Temperature Distribution on Fuel Rod: Impact of Hydride Distribution	Pennsylvania State University	$631,956		Document	FCR&D	FY2011
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$1,000,000		Document	FCR&D	FY2011
Recovery of Uranium from Seawater: Preparation and Development of Polymer-Supported Extractants	City College of New York, Hunter	$363,716		Document	MSTR	FY2011
Microemulsions and Aggregation Formation in Extraction Processes for Used Nuclear Fuel: Thermodynamics and Structural Studies	University of California, Irvine	$1,000,000		Document	FCR&D	FY2011
One-Dimensional Nanostructures for Neutron Detection	North Carolina State University	$455,629		Document	MSTR	FY2011
Optimized Processing Fabrication Paths for Larger Heats of Nanostructured Ferritic Alloys	University of California, Santa Barbara	$1,000,000		Document	FCR&D	FY2011
Feasibility and Safety Assessment for Advanced Reactor Concepts Using Vented Fuel	Oregon State University	$600,000		Document	MSTR	FY2011
Basic Physics Data: Measurement of Neutron Multiplicity from Induced Fission	University of Michigan	$973,364		Document	FCR&D	FY2011
Development of an Efficient Meso-Scale Multi-Phase Flow Solver in Nuclear Applications	City College of New York	$505,858		Document	NEAMS	FY2011
High Temperature Transducers for Online Monitoring of Microstructure Evolution	Pennsylvania State University	$455,628		Document	MSTR	FY2011
Radionuclide Incorporation and Long Term Performance of Apatite Waste Forms	University of Michigan	$862,500		Document	FCR&D	FY2011
Multiscale Modeling and Uncertainty Quantification for Nuclear Fuel Performance	Colorado State University	$1,098,250		Document	NEAMS	FY2011
Laser-Arc Hybrid Welding of Thick Section Ni-base Alloys- Advanced Modeling and Experiments	Pennsylvania State University	$536,117		Document	MSTR	FY2011
Actinide Foil Production for MPACT Research	University of Nevada-Las Vegas	$156,897		Document	FCR&D	FY2011
Fundamental Studies of the Role of Grain Boundaries on Uniform Corrosion of Advanced Nuclear Reactor Materials	Drexel University	$1,098,250		Document	NEAMS	FY2011
Correlates of Sensitive Technologies	Texas A&M University	$509,467		Document	MSTR	FY2011
Enriched Boron-Doped Amorphous Selenium Based Position-Sensitive Solid-State Thermal Neutron Detector for MPACT Applications	University of South Carolina	$1,000,000		Document	FCR&D	FY2011
Phenomena-based Uncertainty Quantification in Predictive Coupled-Physics Reactor Simulations	Texas A&M University	$1,098,250		Document	NEAMS	FY2011
Improved Safety Margin Characterization of Risk from Loss of Offsite Power	Texas A&M University	$600,000		Document	MSTR	FY2011
Development of Advanced High Uranium Density Fuels for Light Water Reactors	University of Wisconsin-Madison	$1,000,000		Document	FCR&D	FY2011
Characterization of Modeling of Grain Boundary Chemistry Evolution in Ferritic Steels Under Irradiation	University of Michigan	$1,098,250		Document	NEAMS	FY2011
Diffusion, Thermal Properties and chemical Compatibilities of Select MAX Phases with Materials for Advanced Nuclear Systems	Drexel University	$535,927		Document	NEET	FY2011
A High Temperature-Tolerant and Radiation-Resistant In-Core Neutron Sensor for Advanced Reactors	The Ohio State University	$455,629		Document	MSTR	FY2011
Developing the User Experience for a Next Generation Nuclear Fuel Cycle Simulator	University of Wisconsin-Madison	$1,200,000		Document	FCR&D	FY2011
Development of Multiscale Materials Modeling Techniques and Coarse-Graining Strategies for Predicting Materials Degradation in Extreme Irradiation Environments	University of Tennessee, Knoxville	$750,000		Document	NEAMS	FY2011
A New Light Weight Structural Material for Nuclear Structures	North Carolina State University	$399,490		Document	NEET	FY2011
Pathway Aggregation in the Risk Assessment of Proliferation Resistance and Physical Protection (PR&PP) of Nuclear Energy Systems	The Ohio State University	$534,471		Document	MSTR	FY2011
Experimental Investigation of Convection and Heat Transfer in the Reactor Core for a VHTR	City College of New York	$1,118,856		Document	RCRD&D	FY2011
Preparation of High Purity, High Molecular-Weight Chitin from Ionic Liquids for Use as an Adsorbate for the Extraction of Uranium from Seawater	University of Alabama	$338,260		Document	MSTR	FY2011
Graphite Microstructural Characterization Using Time-Domain and Correlation-Based Ultrasonics	Johns Hopkins University	$1,199,997		Document	RCRD&D	FY2011
Selectivity in Ligand Binding to Uranyl Compounds: A Synthetic, Structural, Thermodynamic and Computational Study	University of California-Berkeley	$500,000		Document	MSTR	FY2011
Methodology Development for Passive Component Reliability Modeling in a Multi-Physics Simulation Environment	The Ohio State University	$533,457		Document	RCRD&D	FY2011
Development of Seismic Isolation Systems Using Periodic Materials	University of Houston	$538,154		Document	MSTR	FY2011
Pebble Fuel Handling and Reactivity Control for Salt-Cooled High Temperature Reactors	University of California, Berkeley	$612,721		Document	RCRD&D	FY2011
Innovative Elution Processes for Recovering Uranium from Seawater	University of Idaho	$400,000		Document	MSTR	FY2011
Self-Sustaining Thorium Boiling Water Reactors	University of California, Berkeley	$1,145,932		Document	RCRD&D	FY2011
Development of Austenitic ODS Strengthened Alloys for Very High Temperature Applications	University of Illinois-Urbana Champaign	$538,154		Document	MSTR	FY2011
High Fluency Low Flux Embrittlement Models of LWR Reactor Pressure Vessel Embrittlement and a Supporting Database from the UCSB ATR-2 Irradiation Experiment	University of California, Santa Barbara	$1,199,607		Document	RCRD&D	FY2011
Enhancement of the Extraction of the Uranium from Seawater	University of Maryland	$400,000		Document	MSTR	FY2011
A Research Program for Fission Product/Dust Transport in HTGR's	University of Missouri-Columbia	$1,157,367		Document	RCRD&D	FY2011
Transient Safety Analysis of Fast Spectrum TRU Burning LWR with Internal Blankets	University of Michigan	$599,475		Document	MSTR	FY2011
Development and Validation of a Lifecycle-based Prognostics Architecture with Test Bed Validation	University of Tennessee, Knoxville	$846,315		Document	RCRD&D	FY2011
Development of Novel Sorbents for Uranium Extraction from Seawater	University of North Carolina, Chapel Hill	$400,000		Document	MSTR	FY2011
In-situ Condition Monitoring of Components in Small Modular Reactors Using Process and Electrical Signature Analysis	University of Tennessee, Knoxville	$650,000		Document	RCRD&D	FY2011
Radiation Behavior of High-Entropy Alloys for Advanced Reactors	University of Tennessee, Knoxville	$538,159		Document	MSTR	FY2011
Technical Development for S-CO2 Advanced Energy Conversion	University of Wisconsin	$815,000		Document	RCRD&D	FY2011
Rapid Computer Aided Ligand Design and Screening of Precious Metal Extractants from TRUEX Raffinate with Experimental Validation	Washington State University	$500,000		Document	MSTR	FY2011
Ag Transport Through Non-Irradiated and Irradiated SiC	University of Wisconsin-Madison	$1,055,456		Document	RCRD&D	FY2011
Critical Heat Flux Phenomena at High Pressure and Low Mass Fluxes: Tests and Models	University of Wisconsin-Madison	$1,199,781		Document	RCRD&D	FY2011
Modeling and Test Validation of a Reactor Cavity Cooling System with Air	University of Wisconsin-Madison	$1,199,988		Document	RCRD&D	FY2011
Transient Mixed Convection Validation for NGNP	Utah State University	$635,860		Document	RCRD&D	FY2011
Alternative High-Performance Ceramic Waste Forms	Alfred University	$840,000	This project aims to advance fundamental understanding of the kinetics of structural evolution of crystalline ceramic waste forms. The structure/property relationships will be identified and will reveal new formulations, improved processing routes, and strategies for improved performance or ceramic waste forms.	Document	FCR&D	FY2012
Surface Layer Bulk Glass Interface Evolution with Aqueous Corrosion	Alfred University	$880,000	This project will investigate the links between the morphology, structure and chemistry of surface layer-bulk glass interface and the long-term corrosion-reaction kinetics using in-situ and ex-situ experiments. The understanding will result in improved models for long-term predictive behavior of high-level-waste (HLW) glasses under repository conditions.	Document	FCR&D	FY2012
Improved Accident Tolerance of Austenitic Stainless Steel Cladding through Colossal Supersaturation with Interstitial Solutes	Case Western Reserve University	$850,000	This project aims to develop new case-hardened austenitic stainless steels by saturating them with materials that improve their mechanical properties, corrosion resistance and radiation resistance. This project, if successful, will result in safer, longer-lasting, and more accident tolerant fuel claddings.	Document	FCR&D	FY2012
Optimization of Deep Borehole Systems for HLW Disposal	Massachusetts Institute of Technology	$850,000	Researchers aim to carry out a comprehensive evaluation of the deep borehole option for disposal of used nuclear fuel and high livel waste. The models developed will predict potential movement of water through natural and engineered barriers and release of radionuclides to the biosphere which will aide in site selection.	Document	FCR&D	FY2012
Scholarship for Nuclear Communications and Methods for Evaluation of Nuclear Project Acceptability	Massachusetts Institute of Technology	$800,000	Researchers will work to develop a model to characterize the factors affecting social acceptance of nuclear projects with potential stakeholders. The resultant model will strengthen the ability to design and implement large projects more efficiently, leading to higher rates of success of future nuclear projects.	Document	FCR&D	FY2012
Accurate Holdup Calculations with Predictive Modeling and Data Integration	North Carolina State University	$875,000	Researchers will develop and use state-of-the-art radiation transport codes to account accurately for the fissile material in a nuclear materials processing facility. An accurate estimation of the materials will allow for ensured radiological safety, security, waste management and efficient plant operation.	Document	FCR&D	FY2012
Novel Metal Sulfides to Achieve Effective Capture and Durable Consolidation of Radionuclides	Northwestern University	$760,000	Researchers will evaluate the effectiveness of chalcogenide based materials design novel metal sulfides to effectively capture and store of radioisotopes released during reprocessing of used nuclear fuel. This project will focus on understanding structure-property relationships to enable refined and direct synthesis approaches for improved and cost-efficient nuclear waste forms.	Document	FCR&D	FY2012
Nonlinear Ultrasonic Diagnosis and Prognosis of ASR Damage in Dry Cask Storage	Northwestern University	$885,000	Researchers aim to use nondestructive damage characterization methods to detect, manage and mitigate the degradation/damage mechanisms of dry cask storage systems for nuclear fuels. This project, if successful, will provide tools that will allow the prediction of the reliability and the safety of concrete structures in dry cask storage systems.	Document	FCR&D	FY2012
Prototype Demonstration of Gamma-Blind Tensioned Metastable Fluid Neutron/Multiplicity/Alpha Detector- Real Time Methods for Advanced Fuel Cycle Applications	Texas A&M University	$875,000	This project aims to create a prototype demonstration of a novel neutron/alpha detector based on a technology that is blind to gamma field used fuel. The prototype, if successful, will enhance instrumentation for monitoring real-time material balance during various stages of the nuclear cycle.	Document	FCR&D	FY2012
Testing of Sapphire Optical Fiber and Sensors in Intense Radiation Fields, when Subjected to Very High Temperatures	The Ohio State University	$885,000	The researchers on this project will investigate the performance of sapphire optical fibers and sensors in reactor environments. The project, if successful, will result in improved instrumentation to understand the behavior and predict performance of nuclear fuel systems at the microstructural level.	Document	FCR&D	FY2012
Concrete Materials with Ultra-High Damage Resistance and Self-Sensing Capacity for Extended Nuclear Fuel Storage Systems	University of California, Irvine	$800,000	Researchers aim to design a new class of multifunctional concrete materials. This project, if successful, will result in a novel multifunctional concrete material that possesses inherent degradation monitoring capability and is suitable for an extended storage system for the used nuclear fuel.	Document	FCR&D	FY2012
Development of Innovative Accident Tolerant High Thermal Conductivity UO2 Fuel Pellets with a Diamond Dopant	University of Florida	$800,000	Researchers will evaluate the use of diamond nanoparticles composite material in innovative accident tolerant fuel pellets. This could significantly improve both the thermal conductivity of fuel pellets and light water reactors' efficiency safety.	Document	FCR&D	FY2012
Probabilistic Multi-Hazard Assessment of Dry Cask Structures	University of Houston	$865,000	This project aims to investigate the performance of dry cask storage systems under multiple hazard systems (earthquake, tornados, combined with aging effects) using a probabilistic multi-hazard framework. This framework will be validated based on experimental research and will provide improved models for safety and reliability of spent nuclear fuels during storage and transportation.	Document	FCR&D	FY2012
Measurement of Irradiated Pyroprocessing Samples via Laser Induced Breakdown Spectroscopy	University of Idaho	$820,000	This project aims to use advanced characterization techniques to investigate microstructural changes and the micromechanisms related to irradiation induced damage in used nuclear fuels and waste forms. This project, if successful, will result in enhanced models to predict the structural and chemical response of used fuel and waster forms during interim storage and permanent disposal.	Document	FCR&D	FY2012
Elastic/Inelastic Measurement Project	University of Kentucky	$880,523	Researchers will measure nuclear data for elastic/inelastic scattered neutrons on coolants and structural materials. The data generated, will be useful for future R&D programs that will study innovative next generation LWR and future fast systems.	Document	FCR&D	FY2012
Electrochemical Corrosion Studies for Modeling Metallic Waste Form Release Rates	University of Nevada- Las Vegas	$790,000	This project aims to use advanced electrochemical methods to investigate the corrosion related degradation of metal alloys used for housing fission products. The data obtained from this study will allow for the prediction of the long-term behavior of the metallic host phase materials over geological time-scales.	Document	FCR&D	FY2012
Thermodynamic and Microstructural Mechanisms in the Corrosion of Advanced Ceramic Tc-bearing Waste Forms and Thermophysical Properties	University of Nevada- Las Vegas	$795,000	This project team will harvest thermodynamic and microstructural data on the evolution of ceramic based waste forms. The data will be used to advance the current state-of-the-art methodology used for isolation and stabilization of fission products and improve on nuclear fuel recycling processes.	Document	FCR&D	FY2012
Development and Experimental Benchmark of Simulations to Predict Used Nuclear Fuel Cladding Temperatures during Drying and Transfer Operations	University of Nevada- Reno	$745,000	Researchers will conduct experiments to investigate and develop advanced computational models of heat transfer in post-pool-storage drying operations. This project, if successful, will result in tools that can be used to design efficient drying processes to as to ensure suitability for dry-cask systems for long-term storage and transport.	Document	FCR&D	FY2012
Better Radiation Response and Accident Tolerance of Nanostructured Ceramic Fuel Materials?	University of Tennessee	$815,000	Researchers will use novel experimental methods to investigate the links between microstructure, phase stability and damage evolution in nanostructured ceramic fuel materials. The project will study fuel materials at temperatures and irradiation conditions relevant to operation and accidental scenarios.	Document	FCR&D	FY2012
Radiation and Thermal Effects on Used Nuclear Fuel and Nuclear Waste Forms	University of Tennesssee	$770,000	This project aims to investigate the structural and chemical response of used nuclear fuel and waste forms during interim storage and permanent disposal. If successful, this project will generate models that will allow the prediction of structural evolution and hence the radiological safety and security of nuclear fuel and waste forms.	Document	FCR&D	FY2012
Seismic Performance of Dry Casks Storage for Long-Term Exposure	University of Utah	$873,319	Researchers will evaluate the mechanical performance of dry-cask storage under seismic loading for mid-term operational periods. Simulations will include scenarios for freestanding, anchored, and vaulted casks. The experimental tests will also evaluate the dynamic seismic response of freestanding and anchored dry-cask storage prototypes, providing recommendations for optimal Interim Spent Fuel Storage Installations (ISFSIs) design.	Document	FCR&D	FY2012
Validation Experiments for Spent-Fuel Dry-Cask In-Basket Convection	Utah State University	$690,000	Researchers in this project aim to conduct experiments that generate data on natural convection through a fuel assembly. The data will be used to validate the computational models being developed for nuclear safety and design.	Document	FCR&D	FY2012
Re-Branding the Nuclear Fuel Cycle	Virginia Commonwealth University	$850,000	This project will create a comprehensive framework for the evaluation of alternative fuel cycle systems that will be used to identify and analyze key elements related to long-term management of nuclear fuels , with the ultimate goal to develop a communications strategy to reach stakeholders.	Document	FCR&D	FY2012
Advanced Characterization of Molecular Interactions in TALSPEAK-like Separations Systems	Washington State University	$875,000	Researchers will use advanced characterization techniques (experimental and computational) to improve understanding of the molecular level processes/interactions during separation processes for advanced fuel cycles. The understanding of these interactions will be used to develop more robust and streamlined separation processes for advanced fuel cycles.	Document	FCR&D	FY2012
Coupling of Nuclear Waste Form Corrosion and Radionuclide Transport in Presence of Relevant Repository Sediments	Washington State University	$885,000	Researchers will conduct experiments to understand the mechanisms responsible for the corrosion of nuclear waste forms in realistic chemical environments. The data generated from these experiments will enable increased reliability of the models used to predict the waste form performance in repository environments.	Document	FCR&D	FY2012
Stationary Liquid Fuel Fast Reactor (SLFFR) Concept for TRU Burning	Purdue University	$450,000	Reasearchers will investigate a new type of molten metallic fuel reactor concept that will consume hazardous transuranic waste. The liquid fuel alloy has several advantages over solid fuel fast reactors that are used for the same purpose.	Document	MSTR	FY2012
ABR for TRU Transmutation with Breed & Burn Thorium Blanket for Improved Economics and Resource Utilization	University of California- Berkeley	$450,000	The research team will use detailed neutronic analysis for a new Advanced Burner Reactor concept with low conversion ratio. The concept will use a new core shape to improve the utilization of neutrons to perform breed and burn.	Document	MSTR	FY2012
New Materials for High Temperature Thermoelecric Power Generation	University of California, Davis	$450,000	Reasearchers will work to develop nanostructured and other new materials to support the development of higher efficiency thermoelectric devices. These devices convert thermal energy to electricity with no moving parts. The new materials will operate at higher efficiencies and over a wider temperature range than those currently available--an important quality for future nuclear-powered deep space exploration.	Document	MSTR	FY2012
Microscopic Fuel Particles Produced by Self-Assembly of Actinide Nanoclusters on Carbon Nanomaterials	University of Notre Dame	$440,000	Reasearchers will develop the mechanisms, conditions and protocols to prepare uranium-carbon nanocomposite materials to make them more flexible. This could result in the generation of wholesale electricity, providing process heat, and providing power for households.	Document	MSTR	FY2012
High Hydrogen Content Graphene Hydride Compounds & High Cross-Section Cladding Coatings for Fast Neutron Detection	University of South Carolina	$430,000	This project will exploit recent breakthroughs to grow epitaxial graphene on commercial SiC wafers. This will allow researchers to develop a new detection method for fast neutrons. In addition, it will lead to better and more compact neutron detection system.	Document	MSTR	FY2012
Reducing Actinide Production Using Inert Matrix Fuels	University of Texas- Austin	$435,000	Reasearchers will perform a neutronic analysis, a thermal-hydraulic analysis and a simulation of fuel decay heat as a functionof fuel burnup, to determine if inert matrix fuel in coventional reactors will continue to be licensable. If successful, the inert matrix fuel mixtures will reduce harmful transuranic components in the fuel discharge streams at a level comparable to a fast reactcor burner.	Document	MSTR	FY2012
An Integrated Fuel Depletion Calculator for Fuel Cycle Options Analysis	University of Texas- Austin	$395,000	Reasearchers use new analysis techniques to better predict nuclear fuel behavior. The new model will allow improved fuel cycle for a larger number of users.	Document	MSTR	FY2012
Atomic-Scale to Meso-Scale Simulation Studies of Thermal Ageing and Irradiation Effects in Fe-Cr Alloys	Boston University	$874,997	Reasearchers will develop predictive, multi-scale simulation tools for iron-chromium alloys, which are expected to be key components of advanced steels envisioned as fuel cladding and structural components for Generation IV reactors. Such modeling is necessary to avoid resource intensive and costly thermal and neutron irradiation experiments to obtain required performance data.	Document	NEAMS	FY2012
Validation Data and Model Development for Fuel Assembly Response to Seismic Loads	George Washington University	$862,435	Reasearchers will conduct experiments that will provide comprehensive data characterizing the dynamics of the fluid and the structure in Pressurized Water Reactors (PWR) fuel assemblies under seismic loads (earthquakes and loss of coolant accidents). Completion of their project will greatly benefit the safety of existing and future nuclear reactors.	Document	NEAMS	FY2012
Uncertainty Quantification and Management for Multiscale Nuclear Materials Modeling	Georgia Institute of Technology	$743,444	Reasearchers will address the question of uncertainty propogation and error estimates associated with model prediction of material behavior under irradiation. Their work will facilitate a better understanding of the connection of various unit processes to collective responses in a multiscale model chain enabling the development of high strength and high ductility materials.	Document	NEAMS	FY2012
Fuel and Core Design Options to Overcome the Heavy Metal Loading Limit and Improve Performance and Safety of Liquid Salt Cooled Reactors	Georgia Insitute of Technology	$784,689	Reasearchers will examine new options for fuel and core designs in liquid salt cooled reactors where the current standard of TRISO type fuel has limitations due to loading characteristics. The research could enable new, more feasible fuel-core-reload options that will improve safety and performance parameters.	Document	RCRD&D	FY2012
Nonlinear Ultrasonic Techniques to Monitor Radiation Damage in RPV and Internal Components	Georgia Institute of Technology	$877,000	Reasearchers will explore new nondestructive materials evaluation and monitoring techniques utilizing nonlinear ultrasonic measurements . This technique will allow researchers to assess remaining useful life of select reactor components. Breakthroughs in this area will lead to the ability to characterize radiation damage in reactor pressure vessels and other components-leading to a clearer definition of reactor safety margins.	Document	RCRD&D	FY2012
Intergral Reactor Containment Condensation Model and Experimental Validation	Oregon State University	$871,119	Reasearchers will conduct experiments to enhance the safety and efficiency of small modular reactors (SMRs). This project will assess the impact of high-pressure steam condensation on steel containment vessels to be used for SMR deigns.	Document	RCRD&D	FY2012
Investigation of Natural Circulation Instability and Transients in Passively Safe Small Modular Reactors	Purdue University	$871,100	Reasearchers will perform scaled experiments to study the thermal-hydraulic instabilities that can occur in Small Modular Reactors (SMR) which rely on natural circulation cooling during normal operation and accident conditions. Their work will not only improve our understanding of general natural circulation instability but also lead to the development of stability criteria and predictability in the operation of SMRÃs.	Document	RCRD&D	FY2012
Thermoelectric-Driven Sustainable Sensing and Actuation Systems for Fault-Tolerant Nuclear Incidents	State University of New York, Stony Brook	$599,802	Reasearchers will examine the use of solid-state thermoelectric generators to produce electricity to sense and opeate during both normal and abnormal situations. This will provide indefinite monitoring of key components during power outages or station blackouts.	Document	RCRD&D	FY2012
Experimental and CFD Studies of Coolant Flow Mixing within Scaled Models of the Upper and Lower Plenums of NGNP Gas-Cooled Reactors	Texas A&M University	$713,051	Reasearchers will model the internal coolant flow of a prismatic core very high temperature reactor (VHTR) by using large eddy simulation tools. This method will enable more accurate prediction of flow field characteristics and better evaluation of VHTR behavior under operational and accidental conditions.	Document	RCRD&D	FY2012
Demonstrating Hybrid Heat Transport and Energy Conversion System Performance Characterization Using Intelligent Control Systems	University of Idaho	$877,000	Reasearchers will demonstrate an intelligent control systems in a hybrid energy conversion loop for a next generation nuclear power plant. Hybrid energy systems are a method of optimizing the use of natural resources for energy production. Hybrid systems present an opportunity to develop domestic energy sources to improve energy security.	Document	RCRD&D	FY2012
Advanced Reactor-Intermediate Heat Exchanger (IHX) Coupling: Theoretical Modeling and Experimental Validation	University of Idaho	$869,997	Reasearchers will model the behavior of the Advanced Reactor Intermediate Heat Exchanger Chemical Process system and develop advanced control techniques that take into account abnormal scenarios. The data and information obtained will assist in the development of intelligent control systems for next generation nuclear reactor systems.	Document	RCRD&D	FY2012
Irradiation Performance of Fe-Cr Base Alloys	University of Illinois- Urbana Champaign	$876,332	Reasearchers will perform post-radiation analysis and develop tools for future development and application of the Fe-Cr class of alloys. The results of this research will lead to better modeling of performance and development of an alloy designated as the primary choice for reactor fuel cladding and structural applications in advanced systems.	Document	RCRD&D	FY2012
Accelerated Irradiations for High Dose Microstructures in Fast Reactor Alloys	University of Michigan	$831,876	Reasearchers will determine the extent to which high dose rate irradiation can be used as an irradiation damage tool to understand microstructure evolution at high doses and temperatures relevant to advanced fast reactors. The project will provide fundamental understanding of the effectiveness of this process and thus of microstructure development in irradiated materials.	Document	RCRD&D	FY2012
Mitigating IASCC of Reactor Core Internals by Post-Irradiation Annealing Advanced Mitigation Strategies	University of Michigan	$876,985	Reasearchers will determine the optimum Post-irradiation annealing (PIA)-driven mitigation strategy to extend the potential lifetime of light water reactors. Samples that have already been irradiated in a light water reactor will be used to test PIA treatments to understand IASCC initiation and propoagation, annealing kinetics, the role of microstructure features in irradation hardening and localized deformation, and the optimum mitigation strategy based on PIA.	Document	RCRD&D	FY2012
Experimentally Validated Numerical Models for Effects of Non-Isothermal Turbulent Mixing on Wall Stresses in High Temperature Reactors	University of Pittsburgh	$876,422	Reasearchers will develop a comprehensive experimentally validated computational framework for the turbulent mixing in the lower plenum of a very high temperature reactor (VHTR). Through CFD modeling and experimental validation, the results from this project will lay the groundwork for future stress analysis, failure and fatigue studies, and uncertainty quantification for the VHTR system.	Document	RCRD&D	FY2012
Role of Defects in Swelling and Creep of Irradiated SiC	University of Wisconsin- Madison	$875,350	Reasearchers will study mechanisms controlling both radiation swelling and radiation creep in silicon carbide. These two effects are crucial to understanding the issues associated with the brittle silicon carbide composite. Success in this project will ground progress in the adoption of silicon carbide for reactor solutions, particularly as fuel cladding.	Document	RCRD&D	FY2012
Advanced Supercritical Carbon Dioxide Brayton Cycle Development	University of Wisconsin, Madison	$877,000	Reasearchers will investigate the benefits of utilizing advanced Brayton cycles with supercritical carbon dioxide in new reactor systems and components. Benefits of this research include improvement of analysis and performance of components currently utilizing these cycles as well as the potential for a large scale advanced CO2 power system.	Document	RCRD&D	FY2012
Mechanical Behavior of UO2 at Sub-grain Length Scales: Quantification of Elastic, Plastic and Creep Properties via Microscale Testing	Arizona State University	$800,000	Reasearchers will develop techniques to measure properties at sub-grain scales using depleted Uranium Oxide samples. The project will provide a framework to measure sub-grain scale mechanical properties, as well as provide experimental data to improve the understanding of advanced oxide fuels.	Document	FCR&D	FY2013
The Impacts of Pore-Scale Physical and Chemical Heterogeneities on the Transport of Radionuclide-Carrying Colloids	Colorado School of Mines	$800,000	Reasearchers will identify the dominant transport mechanisms to develop models that predict radionuclide distribution in porous materials. Experimental and computational models will be created that couple pore-scale geometric and interfacial structures. Simulators such as these are a necessary step towards fully predictive models for field-scale applications in the future.	Document	FCR&D	FY2013
Recovery of Uranium from Seawater: Polymer-Supported Aminophosphinates as Selective Extractants	Hunter College, CUNY	$399,999	Reasearchers will prepare a polymer-supported extractant for the recovery of uranium from seawater. The project will focus on primary amines that could provide a 3-fold increase in uranium capture capacity than current methods.	Document	FCR&D	FY2013
In-pile Thermal Conductivity Characterization with Single-laser Heating/Time Resolved Raman	Iowa State University	$800,000	Reasearchers will develop a time-resolved Raman-based thermal conductivity measurement system to improve remote in-pile thermal conductivity measurement. These measurements will provide new insights into the behavior of materials exposed to extreme radiation and temperature environments. Understanding the behavior of materials at the microstructural level will support optimized fuel designs.	Document	FCR&D	FY2013
Organic Speciation and Interactions in ALSEP - One Step Partitioning Process of Minor Actinides, Lanthanides, and Fission Products	Oregon State University	$600,000	Reasearchers will investigate the Actinide-Lanthanide Separation (ALSEP) process organic phase prior to aqueous phase separation and after aqueous separation phases of bare and metal-loaded acids. Quantifying these effects can be used to determine how an engineering scale process will perform and generate an accurate chemical model for the system.	Document	FCR&D	FY2013
Glass Composition and Solution Speciation Effects on Stage III Dissolution	Pennsylvania State University	$700,000	Reasearchers will study the chemical and structural triggers of long-term vitrified nuclear waste form behavior. They will study a range of waste glass compositions in corrosive environments. The study will improve understanding of the long-term residual rate and may provide new options for environmental control of glass dissolution rates.	Document	FCR&D	FY2013
Correlating Thermal, Mechanical, and Electrical Coupling Based Multiphysics Behavior of Nuclear Materials Through In-Situ Measurements	Purdue University	$800,000	Reasearchers will use in-situ experimental techniques to monitor the influence of extreme conditions on fuel cladding. The project will establish an in-situ experimental setup that can predict change in thermal properties and their correlation with mechanical properties and correlate such changes to changes in microstructural and chemical features.	Document	FCR&D	FY2013
Creation of a Geant4 Muon Tomography Package for Imaging of Nuclear Fuel in Dry Cask Storage	Purdue University	$440,000	Reasearchers will develop a simulation and analysis package to aid in the non-destructive assessment of sealed used nuclear fuel dry casks using cosmic ray muons. Cosmic ray muon tomography allows for non-destructive assessment that can independently verify and identify weapons grade material sealed within dense dry casks.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Two-stage Fast Reactor Fuel Cycle Options for Optimum Resource Utilization and Waste Management	Purdue University	$400,000	Reasearchers will evaluate the two different two-stage fast reactor fuel cycle options that will offer efficient use of uranium resources and the ability to burn actinides and long-live fission products. Evaluation of these fast fuel cycle options will serve as a useful complement to the options currently being considered in the Fuel Cycle Options Campaign.	Document	FCR&D	FY2013
Mixed Metal Phosphonate-Phosphate Resins for Separation of Lanthanides from Actinides	Texas A&M University	$650,000	Reasearchers will use ion exchangers to cleanly separate lanthanides and curium from reusable actinides. The study will assist in the development of an inexpensive, simple way in which to separate lanthanides from actinides found in used nuclear fuel rods and to recover a large portion of the usable fuel.	Document	FCR&D	FY2013
Safeguards in Pyroprocessing: an Integrated Model Development and Measurement Data Analysis	The Ohio State University	$626,151	Reasearchers will develop a comprehensive and effective safeguards approach for a pyroprocessing facility to support safeguards for future fuel cycles in the United States. The new approach and design will focus directly on the special nuclear materials in the electrorefiner where actinides are separated from fission products through electrochemical process.	Document	FCR&D	FY2013
Using Ionic Liquids for the Development of Renewable Biopolymer-Based Adsorbents for the Extraction of Uranium from Seawater and Testing Under Marine Conditions	University of Alabama	$400,000	Reasearchers will explore the fundamental engineering parameters for a renewable high-performance adsorbent for the extraction of uranium from sweater based on a recently proven ionic liquid (IL)-chitin platform. The project will use the platform to develop a versatile, modifiable adsorbent and characterize its performance and degradation in marine conditions.	Document	FCR&D	FY2013
Developing Ultra-Small Scale Mechanical Testing Methods and Microstructural Investigation Procedures for Irradiated Materials.	University of California, Berkeley	$800,000	Reasearchers will develop new small-scale mechanical testing techniques to allow for the estimation or direct measurement of bulk properties. The combined experiments and modeling will significantly enhance the statistics and information that can be obtained on small radioactive archived samples, as well as new ion beam irradiated specimens.	Document	FCR&D	FY2013
Improved Delayed-Neutron Spectroscopy Using Trapped Ions	University of California, Berkeley	$400,000	Reasearchers will develop innovative spectroscopy techniques to measure the decay of fission fragments. The resulting data from these new techniques will be used to better understand reactor kinetics under accident conditions and failure scenarios.	Document	FCR&D	FY2013
Thermally and Chemically Responsive Nanoporous Materials for Efficient Capture of Fission Product Gases	University of California, Davis	$750,000	Reasearchers will create new nanoporous materials that will be highly effective at capturing fission product gases. These materials would be relevant to both reactor fuels applications and reprocessing operations. Tests will be performed in carbon based and nitride based nanostructures, with the most promising materials from the modeling perspective undergoing further testing.	Document	FCR&D	FY2013
Multiphase Nanocrystalline Ceramic Concept for Nuclear Fuel	University of California, Irvine	$800,000	Researchers will study the use of nanoparticles and nanostructured ceramics to create new materials that can extend the service life and increase efficiency for nuclear fuel. Multiphase nanocrystalline ceramics will be used to design simulated nuclear fuel that can provide added plasticity, better radiation tolerance and improved thermal conductivity.	Document	FCR&D	FY2013
Development of Novel Porous Sorbents for Extraction of Uranium from Seawater	University of Chicago	$400,000	Reasearchers will develop a highly porous sorbent for the extraction of uranium from seawater. Previous research has established sorbent performance. This project will use past foundational studies to design and investigate a new nanocomposites that will be processed into tacks or braids for field tests in seawater tests. The technology may also be used for other metals.	Document	FCR&D	FY2013
Microwave Readout Techniques for Very Large Arrays of Nuclear Sensors	University of Colorado, Boulder	$799,937	Reasearchers will develop a powerful readout technique based on microwave transmission and reflection. The technique will enable very large arrays of diverse sensor types for nuclear materials quantification and tracking. It will provide more accurate data on material composition and quantity.	Document	FCR&D	FY2013
BiI3 Gamma-Ray Spectrometers for Reliable Room-Temperature Nuclear Materials Safeguarding	University of Florida	$799,999	Reasearchers will develop gamma-ray spectrometers based on BiI3 single crystals for MPACT applications such as burnup validation quantification, improved assay of plutonium, determination of uranium enrichment and overall monitoring spent fuel within the fuel cycle. The project will improve energy resolution, efficiency and environmental performance with this new gamma-ray detector.	Document	FCR&D	FY2013
Innovative Coating of Nanostructured Vanadium Carbide on the F/M Cladding Tube Inner Surface for Mitigating the Fuel Cladding Chemical Interactions	University of Florida	$760,276	Researchers will develop barrier coatings on the inner surface of fuel cladding tubes to improve performance of materials at elevated temperatures and high neutron exposures in fast reactors. The project will develop and test a low temperature coating process of nanostructured vanadium carbide that will provide a benchmark for use in future studies.	Document	FCR&D	FY2013
Doubling the Life of Concrete Structures	University of Idaho	$800,000	Reasearchers will use nanoscale techniques to develop methods for doubling the service life of concrete structures. They will study the effect of temperature load and temperature cycling (freezing and thawing) on the durability of concrete with nanoscale viscosity modifiers. The project will benefit from non-destructive evaluation of concrete performance through electrochemical techniques.	Document	FCR&D	FY2013
Off-Gas Treatment: Evaluation of Nano-structured Sorbents for Selective Removal of Contaminants	University of Idaho	$785,910	Reasearchers will evaluate nanostructured sorbent materials for their effectiveness in removing and immobilizing radionuclides for the off-gas treatment from used nuclear fuel recycling operations. The project aims at achieving near-zero emissions of radionuclides by capturing them from the off-gas of recycling operations, allowing for the development of advanced fuel cycles.	Document	FCR&D	FY2013
Innovative Elution Processes for Recovering Uranium and Transition Metals from Amidoxime-Based Sorbents	University of Idaho	$399,864	Reasearchers will develop a new two-step elution process to achieve total recovery of uranium and effective recycling of the sorbent. The extraction process would selectively remove uranium from the sorbent with little or no damage. The process would then remove transition metals and regenerate the sorbent for repeated use, making uranium extraction from seawater economically viable.	Document	FCR&D	FY2013
Performance of a Steel/Oxide Composite Waste Form for Combined Waste Streams from Advanced Electrochemical Processes over Geologic Time Scales	University of Illinois at Chicago	$700,000	Reasearchers will develop and validate a mechanistically-based corrosion model for cermet-type waste forms, creating a testing protocol and modeling approach for predicting long-term performance. The study will apply novel electrochemical testing and modeling methods to the behavior of metal/oxide phase boundaries to evaluate waste form performance.	Document	FCR&D	FY2013
Enhancement of the Extraction of Uranium from Seawater	University of Maryland, College Park	$400,000	Reasearchers will develop and optimize novel adsorbents for uranium recovery from seawater. The team will use radiation-induced grafting of organic phosphates onto polymers. The experiments will use ocean water, with mechanistic analysis, to provide a solid basis for large-scale demonstration of the performance of the new adsorbents in ocean environments.	Document	FCR&D	FY2013
Improving the Understanding of the Coupled Thermal-Mechanical-Hydrologic Behavior of Consolidating Granular Salt	University of New Mexico	$800,000	Reasearchers will increase the understanding of granular salt seal materials for shafts, drifts and boreholes. By coupling thermal, mechanical and hydrological responses, the study will result in greater confidence in granular salt consolidation as a principal strategy for closure and isolation of long-term waste repositories.	Document	FCR&D	FY2013
Fission Fragment Yield Data in Support of Advanced Reactor Technology	University of New Mexico	$399,816	Reasearchers will produce a highly accurate data set for thermal fission. These precision data are necessary for high-accuracy simulations of nuclear criticality, transmutation rates, radiation effects and heating as well as for nuclear fuel, material accounting and identification needs.	Document	FCR&D	FY2013
Molecular dynamics-based simulations of bulk/interfacial structures and diffusion behaviors in nuclear waste glasses	University of North Texas	$700,000	Reasearchers will generate accurate atomic structural models for use in Monte Carlo simulations of the dissolution of nuclear waste glasses. Large-scale molecular dynamics-based computer simulations will be used to investigate self-diffusion behaviors, interfacial structure, and other structures formed during dissolution of these glasses.	Document	FCR&D	FY2013
U3Si2 Fabrication and Testing for Implementation into the BISON Fuel Performance Code	University of South Carolina	$800,000	Reasearchers will fabricate, test and model a high uranium density, advanced nuclear fuel that operates at a much lower temperature and stores less energy. The work will deliver key research data on creep and grain growth, improving economics, through possible power uprates, and advancing accident tolerant fuels research.	Document	FCR&D	FY2013
Structural Health Monitoring of Nuclear Spent Fuel Storage Facilities	University of South Carolina	$738,618	Reasearchers will develop a nuclear structural health monitoring system based on a sensing technology that monitors material degradation and aging for dry cask storage systems. The low-cost, low-profile sensors will perform on-demand monitoring of the structural integrity of individual components as well as the entire system.	Document	FCR&D	FY2013
ORIGEN-based Nuclear Fuel Depletion Module for Fuel Cycle Assessment	University of Tennessee at Knoxville	$755,181	Reasearchers will develop a flexible reactor analysis module for the CYCLUS fuel cycle simulator based on established tools for reactor fuel depletion and decay. They will use ORIGEN, a mature and experimentally validated code, affording greater flexibility and allowing for accurate evaluations of impacts of both present and future fuel cycle options.	Document	FCR&D	FY2013
Cost and System Analysis of Innovative Fuel Resources Concepts	University of Texas at Austin	$295,960	_This project will develop and test braided polymer fiber adsorbents that surpass the sorption capacity, selectivity and durability of the best existing technology to recover uranium from seawater.	Document	FCR&D	FY2013
Risk Assessment of Structural Integrity of Transportation Casks	University of Utah	$789,296	Reasearchers will assess the loss of structural integrity of transportation casks and fuel cladding after extended storage. This risk assessment will conduct experimental tests and simulations to evaluate the structural performance of fuel, fuel assemblies and cask components when subjected to vibration and impact loads during transport.	Document	FCR&D	FY2013
Market-Based and System-Wide Fuel Cycle Optimization	University of Wisconsin, Madison	$612,731	Reasearchers will create market and economic optimizers to improve calculations for the CYCLUS fuel cycle simulator. The team will leverage existing optimization software frameworks within the simulator to resolve top level policy questions. The optimizations will allow CYCLUS to move beyond static material compositions, providing a holistic view of the fuel cycle system.		FCR&D	FY2013
Optical Fiber Based System for Multiple Thermophysical Properties for Glove Box, Hot Cell and In-Pile Applications	Utah State University	$799,975	Reasearchers will use a small pressure vessel to develop a robust technique for the measurement of multiple thermophysical properties at very high temperatures. The technique will lead to a system design moving toward the eventual measurement of irradiated fuels in a glovebox and/or hot cell with all sensors and electronics outside of the glovebox and/or hot cell.	Document	FCR&D	FY2013
Development of a Nano-Modified Concrete for Next Generation of Storage Systems	Vanderbilt University	$796,268	Reasearchers will use nano-sized and nano-structured particles based on enhanced reactivity to develop a superior concrete for the long-term storage of used nuclear fuel. The project will use state-of-the-art experimental chemical and mechanical characterizations and computation analysis to assess the performance of nano-modified concretes.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Thorium Fuel Cycle Options	Vanderbilt University	$797,995	Reasearchers will develop six fuel cycle data packages for multi-stage, thermal fuel cycles which incorporate thorium. These new fuel cycle data packages will provide the opportunity to examine fuel cycle options beyond those which have traditionally been considered. A thorium fuel cycle database will also be assembled as a basis for thorium literature for future evaluations of the thorium fuel cycle.	Document	FCR&D	FY2013
Enhanced Shielding Performance of HLW Storage Packages via Multi-Component Coatings	Virginia Polytechnic Institute and State University	$796,947	Reasearchers will develop a multi-layer composite that will enhance long-term storage and facilitate safe transport of storage packages. This novel multi-layer, multi-component coating would create an outer shield material that is resistant to the corrosion, radiation, diffusion and thermal cycling processes that affect fuel packages during long term storage.	Document	FCR&D	FY2013
Managing Zirconium Chemistry and Phase Compatibility in Combined Process Separations for Minor Actinide Partitioning	Washington State University	$700,000	Reasearchers will address unique challenges for combining TRUEX and TALSPEAK processes for partitioning of lanthanides and minor actinides. The project will develop improved information on the thermodynamics of fission product zirconium and develop a framework for an organic phase solvation model. Combined process development could streamline separations processes.	Document	FCR&D	FY2013
Advances in the Recovery of Uranium from Seawater: Studies Under Real Ocean Conditions	Woods Hole Oceanographic Institution	$398,882	Reasearchers will provide infrastructure and expertise for marine testing of currently available adsorbents in real ocean conditions. The team will move adsorbent research from the lab to field testing in order to quantify sorptive properties and uranium uptake. The project will provide valuable field data that will show the potential of large scale applications of these technologies.	Document	FCR&D	FY2013
NEUP Project 20-19172: Irradiation of Sensors and Adhesive Couplants for Application in LWR Primary Loop Piping and Components		$497,881	Reasearchers paln to attach ultrasonic transducers to substrates using various adhesive couplants that will be irradiated at elevated temperature to simulate LWR primary loop conditions at the PULSTAR reactor at North Carolina State University. Ultrasonic data will be taken in-situ. Subsequently, the sensors and couplant interfaces will be characterized using the LAMDA facility at ORNL. The results will be used to benefit a parallel EPRI project on online monitoring of cracks in LWR primary loop piping._	Document	R&D NSUF	FY2013
NEUP Project 20-19404: Extension of MSTDB to Provide a High-Quality, Validated Thermochemical Database for Predicting/Simulating Corrosion in Molten Salt Reactor SystemsUniversity of South Carolina		$600,000	Reasearchers will generate a validated, consistent database of initial fuel compositions and potential corrossion products of fluoride and chloride salts, allowing for important phenomena predictions in molten salt reactors to guide confident decisions. The database will be integral to the currently being developed Molten Salt Thermochemical Database (MSTDB), structured to allow use by commercial and open source codes._	Document	NEAMS	FY2013
Lower Length Scale Characterization and Validation of Formation and Stability of Helium Bubbles in Nano-structured Ferritic Alloys under Irradiation	Clemson University	$399,870	Reasearchers will provide a fundamental knowledge about the formation and stability of ultra-fine helium bubbles within 14YWT after neutron/ion irradiation for further design of new advanced structural materials with a characteristic high density nanoparticles feature which can increase the mechanical strength, hardness, irradiation resistance and the operational temperature range of materials.	Document	NEAMS	FY2013
Three-Dimensional Fuel Pin Model Validation by Prediction of Hydrogen Distribution in Cladding and Comparison with Experiment	Pennsylvania State University	$800,000	Reasearchers will validate important three-dimensional aspects of the fuel pin modeling by using specialized numerical modeling techniques coupled with laboratory experiments to validate existing models for predicting fuel performance in light water reactors.	Document	NEAMS	FY2013
Collocation-Based Surrogate Models for Uncertainty Quantification and Validation of Coupled, Multiphysics Fuel Performance Simulation Tools	University of Michigan	$596,835	Reasearchers will provide the necessary high fidelity, coupled, multiphysics fuel performance simulator for computational modeling and develop surrogates which will accelerate and focus the validation of the coupled codes. This will be achieved by utilizing the high fidelity coupled fuel performance, thermal-hydraulics and neutronics codes BISON/STAR-CCM+/MPACT and an innovative collocation-based surrogate methodology.	Document	NEAMS	FY2013
Multi-Resolution In-Situ Testing and Mutliscale Simulation for Creep Damage Fatigue Damage Analysis of Alloy 617	Arizona State University	$800,000	This project will develop novel testing and experimentally validated prediction methodologies for micro-structural damage mechanisms of structural materials for advanced reactor systems. The investigations will focus on the characterization and testing of specific metal alloys, but the proposed testing and life-prediction methodologies are applicable to other structural materials as well.	Document	RCRD&D	FY2013
Novel High Temperature and Radiation Resistant Infrared Glasses and Optical Fibers for Sensing in Advanced Small Modular Reactors	Clemson University	$800,000	Clemson University, in partnership with the Iowa State University and the Pacific Northwest National Laboratory, will develop novel optical materials with improved heat and radiation exposure resistance in order to enable in-vessel fiber optic sensing for advanced Small Modular Reactors.	Document	RCRD&D	FY2013
Validation Data Acquisition in HTTF during PCC Events	George Washington University	$800,000	Reasearchers at the George Washington University and Oregon State University will collaborate with NASA Langley Research Center to measure flow velocities in a high temperature test facility. This work supports the development of very-high temperature reactors with passive safety systems.	Document	RCRD&D	FY2013
Advanced High Temperature Inspection Capabilities for Small Modular Reactors	Iowa State University	$790,822	The objective of this project is to develop non-destructive evaluation techniques for advanced small modular reactors. The research will provide key enabling inspection technologies needed to support the design and the reactor component performance validation process for advanced small modular reactors.	Document	RCRD&D	FY2013
Experimental and Computational Investigations of Plenum-to-Plenum Heat Transfer under Natural Circulation in a Prismatic Very High Temperature Reactor	Missouri University of Science and Technology	$799,999	Reasearchers will perform experimental and computational investigations to study heat transfer and natural circulation phenomena in very-high temperature reactors. The study will assist in the ability to predict and analyze passive safety systems.	Document	RCRD&D	FY2013
New Mechanistic Models of Creep-Fatigue Crack Growth Interactions for Advanced High Temperature Reactor Components	Oregon State University	$790,790	Reasearchers will create and validate a robust, multi-scale, numerical model to predict material degradation in nickel-based reactor alloys. If successful, this project will provide better numerical tools for reactor designers and greatly improve their capability to design against material failures for reactor alloys in the long term.	Document	RCRD&D	FY2013
Self-Powered Wireless Dual-mode Langasite Sensor for Pressure/Temperature Monitoring of Nuclear Reactors	State University of New York, Stony Brook	$800,000	This research will develop a novel self-powered wireless hybrid sensor that can accurately monitor both pressure and temperature using a single device without requiring external electricity, even in extreme harsh environments.	Document	RCRD&D	FY2013
Compact Heat Exchanger Design and Testing for Advanced Nuclear Reactors and Advanced Power Cycles	The Ohio State University	$800,000	The goal of this project is to investigate optimal heat exchanger designs for advanced reactors. The research will study the optimization of printed circuit heat exchangers for specific fluids under a variety of conditions as well as perform numerical modeling. Experiments will focus on thermal performance and heat stress during extreme conditions.	Document	RCRD&D	FY2013
Fundamental Understanding of Creep-Fatigue Interactions in 9Cr-1MoV Steel Welds	The Ohio State University	$798,000	This project will advance the state of knowledge and fundamental understanding of deforming materials and welds under loading conditions. Specifically, new integrated testing procedures will be evaluated and applied for conditions that are most detrimental to material stability leading to improved predictions of life expectancy for reactor steels and welds.	Document	RCRD&D	FY2013
Advanced Mechanistic 3D Spatial Modeling and Analysis Methods to Accurately Represent Nuclear Facility External Event Scenarios	The Ohio State University	$800,000	Reasearchers will develop three-dimensional characterization uncertainty analysis for commercial power plants. The project will involve combining experts from the fields of seismic structural modeling and advanced methods of risk assessment. This effort is expected to result in next generation tools that can be used for assessment of seismic risks.	Document	RCRD&D	FY2013
Tritium Mitigation/Control for Advanced Reactor Systems	The Ohio State University	$400,000	Reasearchers will develop a fluoride salt cooled high-temperature reactor featuring a specialized system to control tritium production. If successful, this will result in a significant reduction in size and cost in comparison to other reactor designs.	Document	RCRD&D	FY2013
A Pebble-Bed Breed and Burn Reactor	University of California, Berkeley	$400,000	Reasearchers will assess the feasibility of designing a type of metal cooled reactor able to establish and maintain operation when fueled with depleted uranium. If successful, this reactor will offer at least a 30-fold increase in the uranium ore utilization versus that achieved in contemporary light water reactors without the need for fuel reprocessing and recycling.	Document	RCRD&D	FY2013
Investigation of Thermal Aging Effects on the Evolution of Microstructure and Mechanical Properties of Cast Duplex Stainless Steels	University of Maryland, College Park	$799,966	This research will provide a better understanding of the microstructural evolution and simultaneous change in mechanical response during aging. The results of the research will provide data that can be used to estimate degraded mechanical properties for an 80-year service life of light water reactors.	Document	RCRD&D	FY2013
Model validation using CFD-grade experimental database for NGNP Reactor Cavity Cooling Systems with water and air	University of Michigan	$799,348	Reasearchers will use advanced innovative instrumentation to build a high-resolution experimental database and to use the novel experimental data to assess and further develop the predictive capabilities of computer codes for thermal hydraulics and computational fluid dynamics. The improved models developed by this project will also have the direct benefit of improving the predictive capability of the passive systems of third generation light water reactors and small modular reactor systems.	Document	RCRD&D	FY2013
Long-Term Prediction of Emissivity of Structural Material for High Temperature Reactor Systems	University of Missouri	$799,117	Reasearchers will study specific types of emissivity driven cooling from a variety of materials that are relevant to nuclear reactors. The research will provide a basis for numerical modeling to support reactor development.	Document	RCRD&D	FY2013
Advanced I&C for Fault-Tolerant Supervisory Control of Small Modular Reactors	University of Pittsburgh	$800,000	The purpose of this research is to develop advanced instrumentation and control techniques for supervisory control of advanced small modular reactors. This research supports the operational goals of small modular reactor concepts through the development of improved oversight and surveillance techniques.	Document	RCRD&D	FY2013
Corrosion of Structural Materials for Advanced Supercritical Carbon-Dioxide Brayton Cycle	University of Wisconsin-Madison	$798,672	Reasearchers will study a variety of materials for corrosion resistance under conditions that improve power conversion. In addition to studying the corrosion resistance of the materials, researchers will study the effect of additives to mitigate corrosion. Development of corrosion theories and modeling aimed at prediction of long-term corrosion will be the underlying theme throughout the project.	Document	RCRD&D	FY2013
Component and Technology Development for Advanced Liquid Metal Reactors	University of Wisconsin-Madison	$798,920	In support of liquid metal cooled reactors, the University of Wisconsin, Madison will evaluate advanced alloys and ceramics that come in contact with liquid metals. Additionally, a robust oxygen sensor and for use in liquid metals will be developed in order to better evaluate corrosion profiles in support of diagnostic testing.	Document	RCRD&D	FY2013
A New Paradigm for Understanding Multi-phase Ceramic Waste Form Performance	Clemson University	$800,000	Researchers will use advanced characterization tools to develop 3-D microstructural data that can be incorporated into computer-based simulations in order to predict the performance of waste forms. Materials system modeling will incorporate elemental release and the interconnected microstructural network of phases to better understand performance and degradation, which will accelerate waste form acceptance in repository settings.	Document	FCR&D	FY2014
Controlling Hexavalent Americium: A Centerpiece to a Compact Nuclear Fuel Cycle	Colorado School of Mines	$800,000	Researchers will develop and exploit the fundamental chemistry of Americium to enable an industrially viable means to co-recover the major and minor actinide elements from used nuclear fuel. The results would be a significant step forward in the development of aqueous separations approaches designed to recover the U-Am actinides based on the availability of the hexavalent oxidation state.	Document	FCR&D	FY2014
Zeolite Membranes for Krypton/Xenon Separation from Spent Nuclear Fuel Reprocessing Off-Gas	Georgia Institute of Technology	$400,000	Researchers will develop a high-performance, lower-cost zeolitic membrane process for Kr/Xe separations during spent nuclear fuel processing. Current separation methods are not considered economical and a membrane process would have relatively lower cost, equipment size, and ambient operating temperature. The process would form a sound basis for further development of this transformative separation technology for the nuclear fuel cycle.	Document	FCR&D	FY2014
Optimizing Polymer-Grafted Amidoxime-based Adsorbents for Uranium Uptake from Seawater	Georgia Institute of Technology	$399,999	Researchers will work to increase the adsorbent capacity and selectivity toward uranium by optimizing the adsorbent morphology, synthesis variables, and conditioning parameters and by investigating the rate-limiting variables through transport and reaction modeling. A novel adsorption/partition concept that has the potential to substantially increase the adsorbent capacity will be tested, making uranium from seawater extraction more economically viable.	Document	FCR&D	FY2014
Extraction of Uranium from Seawater: Design and Testing of a Symbiotic System	Massachusetts Institute of Technology	$400,000	Researchers will develop a seawater uranium extraction system that will work symbiotically with an offshore windmill by utilizing the structure, mooring and power of the windmill, while increasing the energy harvested by the installation. Uranium will be extracted by an adsorbent polymer belt, which will be cycled through the seawater and an elution plant located at the base of the windmill tower. Increasing the frequency of harvesting could overcome current economic barriers to seawater uranium extraction.	Document	FCR&D	FY2014
Imaging a Dry Storage Cask with Cosmic Ray Muons	Oregon State University	$799,871	Researchers will develop an imaging system to monitor the content of a dry storage cask with cosmic ray muons. A very large amount of plutonium under nuclear safeguards is contained in used fuel assemblies stored in dry storage casks. Muon imaging will allow a cost effective and reliable way to evaluate dry storage cask content and integrity before transport.	Document	FCR&D	FY2014
Apatite and sodalite based glass-bonded waste forms for immobilization of 129I and mixed halide radioactive wastes	Rutgers University	$800,000	Researchers will develop advanced and chemically durable waste forms for immobilizing 129I (aqueous based reprocessing of fuel) and mixed-halide wastes (molten-salt processing of fuel) by low temperature synthesis. Halide-containing sodalite and calcium phosphate-based apatite minerals will be synthesized, consolidated and tested for chemical durability. The project will provide needed baseline data for the development of advanced waste forms for immobilization of iodine and mixed-halide wastes.	Document	FCR&D	FY2014
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$350,000	Researchers will develop modeling tools supported by experiments for off-gas capture from future nuclear-fuel recycling facilities. Target species include tritium, iodine, krypton, and xenon. The models are intended to provide path forward recommendations to develop off-gas treatment adsorption processes. The project will contribute to the evaluation of options for environmentally acceptable recycle systems.	Document	FCR&D	FY2014
Development of high performance ODS alloys	Texas A&M University	$800,000	Researchers will study swelling, radiation hardening and changes in mechanical properties of ODS alloys to develop two sets of advanced ODS alloys. Two sets of first-round candidate alloys that have already undergone extensive development and testing will evaluate irradiation performance. The study will meet the need for high strength, radiation-tolerant cladding and core components that have enhanced resistance to void swelling.	Document	FCR&D	FY2014
Rare Earth Electrochemical Property Measurements and Phase Diagram Development in a Complex Molten Salt Mixture for Molten Salt Recycle	The Ohio State University	$800,000	Researchers will investigate rare earth (RE) properties in complex molten salt mixtures. In a molten salt recycle approach, the RE drawdown by electrolysis is a key step in which REs are separated from salt containing other fission products. Investigation of RE electrolysis must consider the electrochemical properties of the REs. We propose to conduct studies of detailed experiments and corresponding models to provide the physical properties and phase diagrams required to predict the performance of RE drawdown for processing complex molten salts.	Document	FCR&D	FY2014
Studies of Lanthanide Transport in Metallic Nuclear Fuels	The Ohio State University	$800,000	Researchers will study the redistribution of lanthanides and migration of lanthanides to the fuel surface. The mechanisms of lanthanide transport in metallic fuel based on the novel discovery of a Ôliquid-likeÕ transport mechanism will be studied analytically and experimentally. The project will develop a fundamental understanding of lanthanide fission product migration and redistribution in advanced metallic nuclear fuels, and theory and data to mitigate fuel-cladding chemical interactions.	Document	FCR&D	FY2014
Computational and Experimental Studies of Microstructure-Scale Porosity in Metallic Fuels for Improved Gas Swelling Behavior	University of Arkansas	$796,823	Researchers will study the microstructure of metallic uranium alloy fuels, and their resistance to densification, to minimize in-pile irradiation swelling through bimodal pore size distribution. The project will develop a predictive approach to design metallic fuel microstructures for optimal swelling resistance and fission gas retention.	Document	FCR&D	FY2014
Improved Hybrid Modeling of Spent Fuel Storage Facilities	University of California, Berkeley	$645,393	Researchers will develop a variance reduction method for computational transport that will improve the ability to design and operate monitoring systems for interim used fuel installations through enhanced modeling and simulation. This new tool will demonstrate that modeling calculations can be done more accurately in less time than with current tools and will perform studies characterizing how changes in material, cask configurations, and number of casks could impact monitoring systems.	Document	FCR&D	FY2014
Selective ligands for uranyl via combinatorial peptoid libraries: A synthetic, structural, thermodynamic and computational study	University of California, Berkeley	$400,000	Researchers will study how donor ligands bind to the uranyl ion, UO22+, with the longer-term goal of using this information to tackle selective recognition of uranyl in aqueous solution. The study will impact underlying approaches to controlling the behavior of uranium in these systems. The actinide separation technology could be used in several areas including uranium extraction from seawater, nuclear waste remediation and nuclear materials.	Document	FCR&D	FY2014
Combining Experiments and Simulations of Extraction Kinetics and Thermodynamics in Advanced Separation Processes for Used Nuclear Fuel	University of California, Irvine	$799,938	Researchers will study how the kinetics and thermodynamics of metal ion extraction in advanced separation processes for used nuclear fuel can be described by molecular dynamic (MD) simulations and how the simulations can be validated by experimental data. The project would have broad impacts on several separations processes including advanced TALSPEAK, ALSEP and GANEX by increasing the confidence and accuracy of computer modeling of metal ion extraction._	Document	FCR&D	FY2014
Effect of Metallic Li on the Behavior of Metals in Molten Salts	University of Nevada, Reno	$458,250	Researchers will identify the effect of metallic lithium on materials that are used in molten salt recycling. The study will try to understand how the presence of Li(0) in molten salts affects the degradation of alloys. Studying these changes will help accurately predict container material behavior and longevity.	Document	FCR&D	FY2014
Assessment of Corrosion Resistance of Promising Accident Tolerant Fuel Cladding under Reactor Conditions	University of Notre Dame	$800,000	Researchers will assess the corrosion behavior of accident tolerant fuel candidate iron-based alloys under normal LWR operating conditions consisting of high temperature, relevant water chemistry and irradiation. The assessment will produce data about possible irradiation-accelerated corrosion rates of iron-based alloys, and the mechanisms by which such corrosion rates are accelerated. The project will advance the selection of appropriate replacements for Zircaloy cladding.	Document	FCR&D	FY2014
Functionalized Porous Organic Polymers as Uranium Nano-Traps for Efficient Recovery of Uranium from Seawaterr	University of South Florida	$399,000	Researchers will develop functionalized porous organic polymers, or Ônano-trapsÕ for extraction of uranium from seawater. This technique allows for increased surface area and custom-designed pore size and chemistry to fit specific parameters. The adsorbent materials have high efficiency and effectiveness for uranium recovery from seawater, providing a potential supply for nuclear fuel.	Document	FCR&D	FY2014
Enhanced Accident-Tolerant Fuel Performance and Reliability for Aggressive iPWR/SMR Operation	University of Tennessee	$799,967	To develop a process that evaluates operational and safety performance of reactor-and-fuel combinations by integrating whole-core 3D neutronics with MOOSE/BISON fuel performance assessments via explicit time and space dependent fuel rod operational power histories. The project will be valuable in analyzing and evaluating accident tolerant fuel concepts and furthering the understanding of reactor physics and fuel performance aspects of key accident tolerant fuel concepts.	Document	FCR&D	FY2014
Nuclear Technology R&D Strategies in an Era of Energy Price Uncertainty	University of Texas, Austin	$799,112	Researchers will identify nuclear technology options that are competitive over a wide range of plausible future business environments. No single nuclear technology or business practice will be the best choice across all or even most future conditions. The study will focus on hybrid nuclear-fossil technologies, energy storage and conversion, which will result in an identification of nuclear strategies that can succeed under future market conditions.	Document	FCR&D	FY2014
Development and Optimization of Voltammetric Methods for Real Time Analysis of Electrorefiner Salt with High Concentrations of Actinides and Fission Products	University of Utah	$621,612	Researchers will develop an advanced voltammetry method to pursue the objective of real time monitoring of actinide concentrations in electrorefiner salt. This will include experimental measurement of key parameters such as activity coefficients and exchange current density. It will also involve simulation of voltammetry processes based on first principles. The project will allow for real time measurements that could support the commercialization of pyroprocessing.	Document	FCR&D	FY2014
Development of Self-Healing Zirconium-Silicide Coatings for Improved Performance of Zirconium-Alloy Fuel Cladding	University of Wisconsin, Madison	$798,621	Researchers will study the deposition of self-healing zirconium-silicide coatings on zirconium-alloy fuel cladding material to improve corrosion resistance under normal and accident conditions. Under these conditions, Zr-Si coating evolves into a highly protective functionally-graded multilayered system. The study will lead to improved performance of zirconium-alloy fuels._	Document	FCR&D	FY2014
Thermal Conductivity in Metallic Fuels	Virginia Polytechnic Institute and State University	$799,837	Researchers will calculate the thermal conductivity of metallic uranium and neptunium alloys, including the effects of noble gasses, using density functional theory. The experiments will validate the calculated effective thermal conductivity using the MARMOT code and by helping determine DFT simulation parameters. The study works to improve fuel lifetime by understanding its thermal behavior.	Document	FCR&D	FY2014
SiC-ODS Alloy Gradient Nanocomposites as Novel Cladding Materials	Virginia Polytechnic Institute and State University	$799,998	Researchers will combine nuclear nanomaterial design, processing, testing, and characterization efforts to develop revolutionary materials that can withstand neutron irradiation for long period of time using nanostructured SiC and oxide dispersion strengthened steel. The ultimate objective is to offer new cladding materials with increased corrosion resistance, strength, and creep resistance in both steady state and accident conditions.	Document	FCR&D	FY2014
Experimental Breeder Reactor II Benchmark Evaluation	Idaho State University	$400,000	Researchers will develop a benchmark evaluation of the Experimental Breeder Reactor II (EBR-II). During nearly 30 years of operation numerous experiments were conducted at EBR-II. The most significant of these experiments were conducted in 1986 demonstrating inherent safety features in loss of flow without reactor scram and loss of heat sink without reactor scram. Benchmark evaluation will be valuable for the reactor design efforts in the United States and South Korea.	Document	MSNE	FY2014
Integral full core multi-physics PWR benchmark with measured data	Massachusetts Institute of Technology	$400,000	Researchers will introduce BEAVRS, a new multi-cycle full-core Pressurized Water Reactor (PWR) depletion benchmark based on two operational cycles of a commercial nuclear power plant. This project aims at addressing the uncertainty quantification of the measured data and on making this benchmark a true non-proprietary international benchmark for the validation of high-fidelity multi-physics computational tools.	Document	MSNE	FY2014
Benchmark Evaluation of PROTEUS Gas-Cooled Reactor Experiments	University of Florida	$400,000	Researchers will create International Reactor Physics Experiment Evaluation Project (IRPhEP) benchmarks using data from 1970s experiments of the neutronics of gas-cooled fast reactor (GCFR) designs investigated in the PROTEUS reactor. The GCFR-PROTEUS experiments fill a gap in current integral benchmark data. These experiments can provide validation of computational models and nuclear data for next generation reactors.	Document	MSNE	FY2014
An Investigation To Establish Multiphysical Property Dataset Of Nuclear Materials Based On In-Situ Observations And Measurements	Purdue University	$800,000	Researchers will create an in-situ measurement based experimental approach to develop experimental validation dataset for NEAMS based code validation. Particular emphasis is on supplying data set for multiphysics simulations in extreme conditions as a function of material microstructure.	Document	NEAMS	FY2014
Experimental Validation of UO2 Microstructural Evolutions for NEAMS tool MARMOT	University of Florida	$798,000	Researchers will experimentally validate MARMOT for predicting the microstructural evolutions of UO2 oxide fuel under the driving forces of high temperatures and large temperature gradient in reactors. By performing the experiments and simulations simultaneously using precisely defined initial conditions, the experiment data will provide direct benchmarking of the MARMOT code.	Document	NEAMS	FY2014
High-resolution time-resolved experiments on mixing and entrainment of buoyant jets in stratified environments	University of Michigan	$799,983	Researchers will study high spatial and time-resolution experimental data of the fluid dynamics phenomena of flow jets interacting with a stratified layer. The issue plays an important role in the safety of several reactor designs, including sodium-cooled reactors. The data addresses the NEAMS needs for the validation of high fidelity computational fluid dynamics methodologies.	Document	NEAMS	FY2014
Fundamental study of key issues related to advanced S-CO2 Brayton Cycle: prototypic HX development and Cavitation	Georgia Institute of Technology	$799,000	Researchers will study scientific and operational issues pertinent to compact heat exchanger systems and turbo-machinery. The project will work to resolve issues with the fabrication of diffusion bonded compact heat exchangers, alternate heat exchange technology for recuperators, and resolution of issues with cavitation and fluid instabilities.	Document	RCRD&D	FY2014
Advanced Models for Nondestructive Evaluation of Aging Nuclear Power Plant Cables	Iowa State University	$787,291	Researchers will develop advanced models that relate environmentally induced microstructural and chemical changes in cable insulation polymers to their macroscopic electrical parameters. These parameters will be measured and modeled over a wide range of the electromagnetic spectrum, covering several potential nondestructive evaluation techniques, enabling identification of the most sensitive techniques for future development.	Document	RCRD&D	FY2014
Development of Novel Functionally Graded Transition Joints for Improving the Creep Strength of Dissimilar Metal Welds in Nuclear Applications	Lehigh University	$800,000	Researchers will develop graded transition joints and improved creep life models for increasing the life of dissimilar metal welds (DMWs) in nuclear reactors. The research represents the first application of functionally graded material concepts for solving the problem of DMW failures through an integrated approach of additive manufacturing, modeling, microstructural characterization, and advanced strain-sensing techniques.	Document	RCRD&D	FY2014
Feasibility Assessment of a Micro Modular Reactor (MMR)	North Carolina State University	$400,000	Researchers will develop an innovative compact reactor concept that integrates power production, power conversion and electricity generation in a single unit: the Micro Modular Reactor (MMR). It is designed to be absolutely melt-down proof (MDP) under all circumstances including complete loss of coolant scenarios with no possible release of radioactive material, to have a cycle length of greater than 10 years, and to be highly proliferation resistant.	Document	RCRD&D	FY2014
Scaling Studies for Advanced Gas Reactor Concepts	Oregon State University	$681,834	Researchers will expand the utilization of the Oregon State University High Temperature Test Facility (HTTF) to validate a broader range of advanced high temperature reactors and events. The facility will be revised to add a detailed scaling analysis of additional gas reactor concepts including advanced gas-cooled, molten salt, and sodium cooled reactors.	Document	RCRD&D	FY2014
Fluid Stratification Separate Effects Analysis, Testing and Benchmarking	Oregon State University	$800,000	Researchers will study fluid stratification in high temperature gas reactors. Coolant stratification is the result of incomplete mixing of one or more fluids, leading to a density gradient, which may or may not dissipate under diffusive or convective effects. This combined analytical and experimental project seeks to investigate stratification driven by diffusive and convective mechanisms and is expected to yield insight into this phenomenon.	Document	RCRD&D	FY2014
Probabilistic Economic Valuation of Safety Margin Management Analysis	Oregon State University	$795,364	Researchers will use RAVEN and develop a companion software package to facilitate economic analysis of safety margins. The project is a proof of concept that will use techniques to examine the cost of improving safety margins vs. the risk of accidents from not improving safety margins. This analysis can be used to evaluate the economic viability of various plant upgrades.	Document	RCRD&D	FY2014
Novel Dissimilar Joints Between Alloy 800H and 2.25%Cr and 1%Mo Steel	Pennsylvania State University	$800,000	Researchers will fabricate and test dissimilar metal joints between a nickel base alloy and a steel with gradual variations of chemical composition, microstructure and properties in a manner that reduces abrupt thermal expansion mismatch and the resulting residual stresses. Data on structure and properties will serve as valuable inputs for the initiation of an ASME code case.	Document	RCRD&D	FY2014
Multi-Phase Model Development to Assess RCIC System Capabilities under Severe Accident Conditions	Texas A&M University	$564,246	Researchers will develop physics-based models of the Reactor Core Isolation Cooling (RCIC) System and incorporating them into a multi-phase code for validation. The project will tackle the current major challenges in RCIC System analysis and enable evaluation of two-phase thermodynamic aspects.	Document	RCRD&D	FY2014
Experimental Investigation and CFD Analysis of Steam Ingress Accidents in HTGRs	The Ohio State University	$800,000	Researchers will study the steam ingress scenario for HTGRs. The study will investigate thermal-hydraulic behavior and graphite oxidation of stream ingress phenomena to validate predictive CFD models. This work will resolve concerns about possible steam generator tube ruptures in a HTGR He-Steam Rankine cycle.	Document	RCRD&D	FY2014
Coiled Tube Gas Heaters For Nuclear Gas-Brayton Power Conversion	University of California, Berkeley	$800,000	Researchers will develop heat exchangers for Brayton-cycle power conversion in reactors using sodium, NaK, or salt as intermediate coolants. The proposed coiled tube gas heaters (CTGHs) are expected to have excellent power density, thermal shock/creep, in-service inspection, and reparability characteristics.	Document	RCRD&D	FY2014
Fundamental Studies of Irradiation-Induced Modifications in Microstructural Evolution and Mechanical Properties of Advanced Alloys	University of Illinois, Urbana-Champaign	$800,000	Researchers will develop and test a mechanism for predicting neutron irradiation performance for optimized Grade 92 and Alloy 709 for applications in advanced reactor systems. The work will employ ion irradiations and available information from neutron irradiations of related alloys to develop a basis for predicting the neutron irradiation performance of the optimized alloys.	Document	RCRD&D	FY2014
Integrated Computational and Experimental Study of Radiation Damage Effects in Grade 92 Steel and Alloy 709	University of Tennessee	$800,000	Researchers will develop a mechanistic understanding and predictive models of irradiation-induced microstructural evolution and resulting mechanical properties in optimized ferritic-martensitic Grade 92 steel and austenitic alloy 709 using multiscale simulations coupled with rigorous experimental validation. The project will provide insights into the correlation between ion irradiation and fast neutron damage.	Document	RCRD&D	FY2014
Meta-Level Design Guidance and Operator Performance Measures for Hybrid Control Rooms	Vanderbilt University	$799,869	Researchers will apply human factors engineering methods and relevant expertise from non-nuclear high-risk high-consequence domains toward the measurement of operator performance in analog, digital, and hybrid main control rooms. Performance measures will be developed for evaluating the situation awareness and decision-making proficiencies to support the transition to digital or hybrid control room displays.	Document	RCRD&D	FY2014

FY 2010 Research and Development Awards

A complete list of R&D projects with their associated abstracts is available below.

Title	Institution	Estimated Funding*	Project Description	Abstract	Project Type	Fiscal Year
Neutron Damage and MAX Phase Ternary Compounds	Drexel University			Document	IIR	FY2009
Atomistic Calculations of the Effect of Minor Actinides on Thermodynamic and Kinetic Properties of UO2+x	Georgia Institute of Technology			Document	IIR	FY2009
Maximum Fuel Utilization in Fast Reactors without Chemical Reprocessing	University of California, Berkeley			Document	IIR	FY2009
Developing a High Thermal Conductivity Fuel with Silicon Carbide Additives	University of Florida			Document	IIR	FY2009
Fabrication of Tungsten-Rhenium Cladding Materials via Spark Plasma Sintering for Ultra High Temperature Reactor Applications	University of Idaho			Document	IIR	FY2009
Ionic Liquid and Supercritical Fluid Hyphenated Techniques for Dissolution and Separation of Lanthanides, Actinides, and Fission Products	University of Idaho			Document	IIR	FY2009
Improved Fission Neutron Data Base for Active Interrogation of Actinides	University of Michigan			Document	IIR	FY2009
Utilization of Methacrylates and Polymer Matrices for the Synthesis of Ion Specific Resins	University of Nevada, Las Vegas			Document	IIR	FY2009
Improved LWR Cladding Performance by EPD Surface Modification Technique	University of Wisconsin, Madison			Document	IIR	FY2009
Advanced Models of LWR Pressure Vessel Embrittlement for Low Flux-High Fluence Conditions	University of California, Santa Barbara			Document	LWRS	FY2009
Irradiation Creep in Graphite	Boise State University			Document	NGNP	FY2009
Modeling the Stress Strain Relationships and Predicting Failure Probabilities For Graphite Core Components	Cleveland State University			Document	NGNP	FY2009
TRISO-Coated Fuel Durability Under Extreme Conditions	Colorado School of Mines			Document	NGNP	FY2009
An Innovative and Advanced Coupled Neutron Transport and Thermal Hydraulic Method (Tool) for the Design, Analysis and Optimization of VHTR/NGNP Prismatic Reactors	Georgia Institute of Technology			Document	NGNP	FY2009
Removal of 14C from Irradiated Graphite for Graphite Recycle and Waste Volume Reduction	Idaho State University			Document	NGNP	FY2009
Millimeter-Wave Thermal Analysis Development and Application to Gen IV Reactor Materials	Massachusetts Institute of Technology			Document	NGNP	FY2009
Accurate Development of Thermal Neutron Scattering Cross Section Libraries	North Carolina State University			Document	NGNP	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
Understanding Creep Mechanisms in Graphite with Experiments, Multiscale Simulations, and Modeling	North Carolina State University			Document	NGNP	FY2009
Simulations of the Thermodynamic and Diffusion Properties of Actinide Oxide Fuel Materials	University of Michigan			Document	AFCI	FY2009
Verification & Validation of High-Order Short-Characteristics-Based Deterministic Transport Methodology on Unstructured Grids	North Carolina State University			Document	NGNP	FY2009
Adsorptive Separation and Sequestration of Krypton, I and C14 on Diamond Nanoparticles	University of Missouri, Columbia			Document	AFCI	FY2009
Microscale Heat Conduction Models and Doppler Feedback	North Carolina State University			Document	NGNP	FY2009
Fundamental Understanding of Ambient and High-Temperature Plasticity Phenomena in Structural Materials in Advanced Reactors	Georgia Institute of Technology			Document	AFCI	FY2009
Development of Alternative Technetium Waste Forms	University of Nevada, Las Vegas			Document	AFCI	FY2009
Optimizing Neutron Thermal Scattering Effects in Very High Temperature Reactors	North Carolina State University			Document	NGNP	FY2009
Advanced Elastic/Inelastic Nuclear Data Development Project	Idaho State University			Document	AFCI	FY2009
Heterogeneous Recycling in Fast Reactors	Massachusetts Institute of Technology			Document	AFCI	FY2009
Quantification of UV-Visible and Laser Spectroscopic Techniques for Materials Accountability and Process Control	University of Nevada, Las Vegas			Document	AFCI	FY2009
Multiaxial Creep-Fatigue and CreepRatcheting Failures of Grade 91 and Haynes 230 Alloys Toward Addressing Design Issues of Gen IV Nuclear Power Plants	North Carolina State University			Document	NGNP	FY2009
Thermodynamic Development of Corrosion Rate Modeling in Iron Phosphate Glasses	Missouri University of Science and Technology			Document	AFCI	FY2009
Development of Subspace-Based Hybrid Monte Carlo-Deterministic Algorithms for Reactor Physics Calculations	North Carolina State University			Document	AFCI	FY2009
High-Fidelity Space-Time Adaptive Multiphysics Simulations in Nuclear Engineering	University of Nevada, Reno			Document	AFCI	FY2009
Improvements to Nuclear Data and Its Uncertainties by Theoretical Modeling	Rensselaer Polytechnic Institute			Document	AFCI	FY2009
Investigation of Countercurrent Helium-air Flows in Air-ingress Accidents for VHTRs	Ohio State University			Document	NGNP	FY2009
Sharp Interface Tracking in Rotating Microflows of Solvent Extraction	State University of New York at Stony Brook			Document	AFCI	FY2009
Bulk Nanostructured FCC Steels with Enhanced Radiation Tolerance	Texas A&M University			Document	AFCI	FY2009
Simulations of Failure via Three-Dimensional Cracking in Fuel Cladding for Advanced Nuclear Fuels	University of Texas, Dallas			Document	AFCI	FY2009
Testing of Performance of Optical Fibers Under Irradiation in Intense Radiation Fields, When Subjected to Very High Temperatures	Ohio State University			Document	NGNP	FY2009
Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels	Texas A&M University			Document	AFCI	FY2009
SiC Schottky Diode Detectors for Measurement of Actinide Concentrations from Alpha Activities in Molten Salt Electrolyte	The Ohio State University			Document	AFCI	FY2009
Computational Design of Advanced Nuclear Fuels	University of California, Davis			Document	AFCI	FY2009
Advanced Mesh-Enabled Monte Carlo Capability for Multi-Physics Reactor Analysis	University of Wisconsin, Madison			Document	AFCI	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
A Distributed Fiber Optic Sensor Network for Online 3-D Temperature and Neutron Fluence Mapping in a VHTR Environment	Texas A&M University			Document	NGNP	FY2009
Ab Initio Enhanced Calphad Modeling of Actinide Rich Nuclear Fuels	University of Wisconsin, Madison			Document	AFCI	FY2009
Investigation on the Core Bypass Flow in a Very High Temperature Reactor	Texas A&M University			Document	NGNP	FY2009
Development of Diffusion Barrier Coatings and Deposition Technologies for Mitigating Fuel Cladding Chemical Interactions (FCCI)	University of Wisconsin, Madison			Document	AFCI	FY2009
CFD Model Development and Validation for High Temperature Gas Cooled Reactor Cavity Cooling System (RCCS) Applications	Texas A&M University			Document	NGNP	FY2009
Thermal Properties of LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin, Madison			Document	AFCI	FY2009
Study of Air ingress across the duct during the accident conditions	Texas A&M University			Document	NGNP	FY2009
Verification of the CENTRM Module for Adaptation of the SCALE Code to NGNP Prismatic and PBR Core Designs	University of Arizona			Document	NGNP	FY2009
Integral and Separate Effects Tests for Thermal Hydraulics Code Validation for Liquid-Salt Cooled Nuclear Reactors	University of California, Berkeley			Document	NGNP	FY2009
Mechanisms Governing the Creep Behavior of High Temperature Alloys for Generation IV Nuclear Energy Systems	University of Cincinnati			Document	NGNP	FY2009
ALD Produced B2O3, Al2O3 and TiO2 Coatings on Gd2O3 Burnable Poison Nanoparticles	University of Colorado, Boulder			Document	NGNP	FY2009
Experimental Study and Computational Simulations of Key Pebble Bed Thermomechanics Issues for Design and Safety	University of Idaho			Document	NGNP	FY2009
Prediction and Monitoring Systems of Creep-Fracture Behavior of 9Cr-1Mo Steels for Reactor Pressure Vessels	University of Idaho			Document	NGNP	FY2009
Understanding Fundamental Material Degradation Processes in High Temperature Aggressive Chemomechanical Environments	University of Illinois, Urbana-Champaign			Document	NGNP	FY2009
Multi-Scale Multi-physics Methods Development for the Calculation of Hot-Spots in the NGNP	University of Michigan			Document	NGNP	FY2009
Corrosion and Creep of Candidate Alloys in High Temperature Helium and Steam Environments for the NGNP	University of Michigan			Document	NGNP	FY2009
Creation of a Full-Core HTR Benchmark with the Fort St. Vrain Initial Core and Validation of the DHF Method with Helios for NGNP Configurations	University of Michigan			Document	NGNP	FY2009
Fission Product Sorptivity in Graphite	University of Missouri, Columbia			Document	NGNP	FY2009
Identifying and Understanding Environment-Induced Crack Propagation Behavior in Ni-Based Superalloy INCONEL 617	University of Nevada, Las Vegas			Document	NGNP	FY2009
Graphite Oxidation Simulation in HTR Accident Conditions	University of New Mexico			Document	NGNP	FY2009
Non Destructive Thermal Analysis and In Situ Investigation of Creep Mechanism of Graphite and Ceramic Composites using Phase-sensitive THz Imaging & Nonlinear Resonant Ultrasonic Spectroscopy	University of Rochester			Document	NGNP	FY2009
Tritium Sequestration in Gen IV NGNP Gas Stream via Proton Conducting Ceramic Pumps	University of South Carolina			Document	NGNP	FY2009
Materials, Turbomachinery and Heat Exchangers for Supercritical CO2 Systems	University of Wisconsin, Madison			Document	NGNP	FY2009
Experimental Studies of NGNP Reactor Cavity Cooling System with Water	University of Wisconsin, Madison			Document	NGNP	FY2009
Assessment of Embrittlement of VHTR Structural Alloys in Impure Helium Environments	University of Wisconsin, Madison			Document	NGNP	FY2009
Modeling Fission Product Sorption in Graphite Structures	University of Wisconsin, Madison			Document	NGNP	FY2009
Liquid Salt Heat Exchanger Technology for VHTR Based Applications	University of Wisconsin, Madison			Document	NGNP	FY2009
Effect of Post-Weld Heat Treatment on Creep Rupture Properties of Grade 91 Steel Heavy Section Welds	Utah State University			Document	NGNP	FY2009
Alpha Radiolysis of Nuclear Solvent Extraction Ligands used for An(III) and Ln(III) Separations	California State University, Long Beach	$1,390,252		Document	FCR&D	FY2010
Predictive Maturity of Multi-Scale Simulation Models for Fuel Performance	Clemson University	$614,690		Document	FCR&D	FY2010
Freeze-casting as a Novel Manufacturing Process for Fast Reactor Fuels	Drexel University	$1,149,327		Document	FCR&D	FY2010
Fuel Performance Experiments on the Atomistic Level, Studying Fuel Through Engineered Single Crystal UO2	Idaho State University	$650,000		Document	FCR&D	FY2010
Development of A Self Biased High Efficiency Solid-State Neutron Detector for MPACT Applications	Rensselaer Polytechnic Institute	$810,141		Document	FCR&D	FY2010
Development of a Innovative High Thermal Conductivity UO 2 Ceramic Composites Fuel Pellets with Carbon Nano-Tubes Using Spark Plasma Sintering	University of Florida	$894,042		Document	FCR&D	FY2010
Exploration and Modeling of Structural Changes in Waste Glass under Corrosion	Pennsylvania State University	$1,377,444		Document	FCR&D	FY2010
Evaluation of materials for interim storage of spent fuel for more than 100 years	University of Michigan	$931,603		Document	FCR&D	FY2010
Implementation of On-the-Fly Doppler Broadening in MCNP5 for Multiphysics Simulation of Nuclear Reactors	University of Michigan	$406,712		Document	FCR&D	FY2010
Methods and tools to allow molecular flow simulations to be coupled to higher level continuum descriptions of flows in porous/fractured media and aerosol/dust dynamics	University of Missouri-Columbi	$541,286		Document	FCR&D	FY2010
Characterization and Modeling of Materials for Kr-Xe Separations	University of Nevada-Las Vegas	$989,800		Document	FCR&D	FY2010
Modeling Solute Thermokinetics in LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin-Madison	$616,073		Document	FCR&D	FY2010
Advanced Aqueous Separation Systems for Actinide Partitioning: Develop Fundamental Understanding of An(III)/Ln(III) Separation	Washington State University	$1,451,784		Document	FCR&D	FY2010
Consistent Multigroup Theory Enabling Accurate Coarse-Group Simulation of GenIV Reactors	Georgia Institute of Technology	$1,046,277		Document	GEN IV	FY2010
Studies of Deteriorated Heat Transfer in Prismatic Cores Stemming from Irradiation-Induced Geometry Distortion	Idaho State University	$1,287,921		Document	GEN IV	FY2010
Carbide Coatings for Nickel Alloys, Graphite, and Carbon/Carbon Composites to be Used in Fluoride Salt Valves	Johns Hopkins University	$1,183,239		Document	GEN IV	FY2010
Design, Testing, and Modeling of the Direct Reactor Auxiliary Cooling System for AHTRs	Ohio State University	$1,366,627		Document	GEN IV	FY2010
Monitoring microstructural evolution of Alloy 617 with nonlinear acoustics for remaining useful life prediction; multiaxial creep-fatigue and creep-ratcheting	Pennsylvania State University	$1,000,000		Document	GEN IV	FY2010
Development and Validation of Multidimensional Models of Supercritical CO 2 Energy Conversion Systems for Nuclear Power Reactors	Rensselaer Polytechnic Institute	$475,005		Document	GEN IV	FY2010
Multiscale Concrete Modeling for Aging Degradation	Mississippi State University	$345,941		Document	LWRS	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term and Elevated Temperature Irradiation: Modeling and Experimental Investigation	University of California-Berkeley	$1,320,667		Document	GEN IV	FY2010
Development of an advanced computational fluid dynamics technology for the next-generation nuclear reactor system analysis and safety margin characterization code	North Carolina State University	$418,199		Document	LWRS	FY2010
Development of Barrier Layers for the Protection of Candidate Alloys in the VHTR	University of California-Santa Barbara	$995,232		Document	GEN IV	FY2010
Precursor Derived Nanostructured Si-C-X Materials for Nuclear Applications	University of Washington	$899,518		Document	MRIIR	FY2010
Investigation of a Novel NDE Method for Monitoring Thermo-Mechanical Damage and Microstructure Evolution in Ferritic-Martensitic Steels for Generation IV Nuclear Energy Systems	University of Cincinnati	$833,109		Document	GEN IV	FY2010
Development and Testing of an Open-Loop Oscillator for Small Reactivity Worth Samples	Idaho State University	$597,252		Document	MRIIR	FY2010
Fission Product Transport in TRISO Particle Layers under Operating and Off-Normal Conditions	University of Michigan	$966,581		Document	GEN IV	FY2010
Understanding the Irradiation Behavior of Zirconium Carbide	Pennsylvania State University	$870,613		Document	MRIIR	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term Irradiation at Elevated Temperature: Critical Experiments	University of Michigan	$1,181,379		Document	GEN IV	FY2010
Modeling investigation of the stability and irradiation-induced evolution of nanoscale precipitates in advanced structural materials	University of Tennessee-Knoxville	$380,653		Document	MRIIR	FY2010
Three-dimensional NDE of VHTR Core Components via Simulation-based Testing	University of Minnesota	$1,366,163		Document	GEN IV	FY2010
Investigation of Laser Shock Peening for Enhancing Fatigue and Stress Corrosion Cracking Resistance of Nuclear Energy Materials	University of Cincinnati	$1,242,019		Document	MRIIR	FY2010
Failure Predictions for VHTR Core Components using a Probabilistic Continuum Damage Mechanics Model	University of Minnesota	$854,542		Document	GEN IV	FY2010
Irradiation Accelerated Corrosion of Reactor Core Materials	University of Michigan	$798,943		Document	MRIIR	FY2010
Development of a Scanning Microscale Fast Neutron Irradiation Platform for Examining the Correlation Between Local Neutron Damage and Graphite Microstructure	University of Missouri-Columbia	$703,064		Document	GEN IV	FY2010
Study of Interfacial Interactions using Thin Film Surface Modification: Radiation and Oxidation Effects in Materials	University of Wisconsin-Madison	$538,032		Document	MRIIR	FY2010
Development of Thermal Transient Flow Rate Sensors for High Temperature, Irradiation, Corrosive Environment	University of Nevada-Las Vegas	$451,269		Document	GEN IV	FY2010
Novel Engineered Refractory Materials for Advanced Reactor Applications	North Carolina State University	$1,129,304		Document	MRIIR	FY2010
Novel Methods of Tritium Sequestration: High Temperature Gettering and Separation Membrane Materials Discovery for Nuclear Energy Systems	University of South Carolina	$1,366,626		Document	GEN IV	FY2010
Heat Transfer Salts for Nuclear Reactor Systems - Chemistry Control, Corrosion Mitigation, and Modeling	University of Wisconsin-Madison	$1,352,040		Document	GEN IV	FY2010
Pulsed Magnetic Welding for Advanced Core and Cladding Steels	University of Wisconsin-Madison	$525,206		Document	GEN IV	FY2010
Corrosion in Supercritical Carbon Dioxide: Materials, Environmental Purity, Surface Treatments, and Flow Issues	University of Wisconsin-Madison	$651,447		Document	GEN IV	FY2010
Quantification of Cation Sorption to Engineered Barrier Materials Under Extreme Conditions	Clemson University	$1,171,380		Document	FCR&D	FY2011
In-Pile Instrumentation Multi-Parameter System Utilizing Photonic Fibers and Nanovision	Idaho State University	$1,199,990		Document	FCR&D	FY2011
Development of Plasmonically Cloaked Nanoparticles	Idaho State University	$800,000		Document	FCR&D	FY2011
Fission Product Transmutation in Mixed Radiation Fields	Idaho State University	$800,000		Document	FCR&D	FY2011
Life Prediction of Spent Fuel Storage Canister Material	Massachusetts Institute of Technology	$899,826		Document	FCR&D	FY2011
Active Interrogation using Photofission Technique for Nuclear Materials Control and Accountability	Oregon State University	$900,000		Document	FCR&D	FY2011
Anisotropic Azimuthal Power and Temperature Distribution on Fuel Rod: Impact of Hydride Distribution	Pennsylvania State University	$631,956		Document	FCR&D	FY2011
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$1,000,000		Document	FCR&D	FY2011
Recovery of Uranium from Seawater: Preparation and Development of Polymer-Supported Extractants	City College of New York, Hunter	$363,716		Document	MSTR	FY2011
Microemulsions and Aggregation Formation in Extraction Processes for Used Nuclear Fuel: Thermodynamics and Structural Studies	University of California, Irvine	$1,000,000		Document	FCR&D	FY2011
One-Dimensional Nanostructures for Neutron Detection	North Carolina State University	$455,629		Document	MSTR	FY2011
Optimized Processing Fabrication Paths for Larger Heats of Nanostructured Ferritic Alloys	University of California, Santa Barbara	$1,000,000		Document	FCR&D	FY2011
Feasibility and Safety Assessment for Advanced Reactor Concepts Using Vented Fuel	Oregon State University	$600,000		Document	MSTR	FY2011
Basic Physics Data: Measurement of Neutron Multiplicity from Induced Fission	University of Michigan	$973,364		Document	FCR&D	FY2011
Development of an Efficient Meso-Scale Multi-Phase Flow Solver in Nuclear Applications	City College of New York	$505,858		Document	NEAMS	FY2011
High Temperature Transducers for Online Monitoring of Microstructure Evolution	Pennsylvania State University	$455,628		Document	MSTR	FY2011
Radionuclide Incorporation and Long Term Performance of Apatite Waste Forms	University of Michigan	$862,500		Document	FCR&D	FY2011
Multiscale Modeling and Uncertainty Quantification for Nuclear Fuel Performance	Colorado State University	$1,098,250		Document	NEAMS	FY2011
Laser-Arc Hybrid Welding of Thick Section Ni-base Alloys- Advanced Modeling and Experiments	Pennsylvania State University	$536,117		Document	MSTR	FY2011
Actinide Foil Production for MPACT Research	University of Nevada-Las Vegas	$156,897		Document	FCR&D	FY2011
Fundamental Studies of the Role of Grain Boundaries on Uniform Corrosion of Advanced Nuclear Reactor Materials	Drexel University	$1,098,250		Document	NEAMS	FY2011
Correlates of Sensitive Technologies	Texas A&M University	$509,467		Document	MSTR	FY2011
Enriched Boron-Doped Amorphous Selenium Based Position-Sensitive Solid-State Thermal Neutron Detector for MPACT Applications	University of South Carolina	$1,000,000		Document	FCR&D	FY2011
Phenomena-based Uncertainty Quantification in Predictive Coupled-Physics Reactor Simulations	Texas A&M University	$1,098,250		Document	NEAMS	FY2011
Improved Safety Margin Characterization of Risk from Loss of Offsite Power	Texas A&M University	$600,000		Document	MSTR	FY2011
Development of Advanced High Uranium Density Fuels for Light Water Reactors	University of Wisconsin-Madison	$1,000,000		Document	FCR&D	FY2011
Characterization of Modeling of Grain Boundary Chemistry Evolution in Ferritic Steels Under Irradiation	University of Michigan	$1,098,250		Document	NEAMS	FY2011
Diffusion, Thermal Properties and chemical Compatibilities of Select MAX Phases with Materials for Advanced Nuclear Systems	Drexel University	$535,927		Document	NEET	FY2011
A High Temperature-Tolerant and Radiation-Resistant In-Core Neutron Sensor for Advanced Reactors	The Ohio State University	$455,629		Document	MSTR	FY2011
Developing the User Experience for a Next Generation Nuclear Fuel Cycle Simulator	University of Wisconsin-Madison	$1,200,000		Document	FCR&D	FY2011
Development of Multiscale Materials Modeling Techniques and Coarse-Graining Strategies for Predicting Materials Degradation in Extreme Irradiation Environments	University of Tennessee, Knoxville	$750,000		Document	NEAMS	FY2011
A New Light Weight Structural Material for Nuclear Structures	North Carolina State University	$399,490		Document	NEET	FY2011
Pathway Aggregation in the Risk Assessment of Proliferation Resistance and Physical Protection (PR&PP) of Nuclear Energy Systems	The Ohio State University	$534,471		Document	MSTR	FY2011
Experimental Investigation of Convection and Heat Transfer in the Reactor Core for a VHTR	City College of New York	$1,118,856		Document	RCRD&D	FY2011
Preparation of High Purity, High Molecular-Weight Chitin from Ionic Liquids for Use as an Adsorbate for the Extraction of Uranium from Seawater	University of Alabama	$338,260		Document	MSTR	FY2011
Graphite Microstructural Characterization Using Time-Domain and Correlation-Based Ultrasonics	Johns Hopkins University	$1,199,997		Document	RCRD&D	FY2011
Selectivity in Ligand Binding to Uranyl Compounds: A Synthetic, Structural, Thermodynamic and Computational Study	University of California-Berkeley	$500,000		Document	MSTR	FY2011
Methodology Development for Passive Component Reliability Modeling in a Multi-Physics Simulation Environment	The Ohio State University	$533,457		Document	RCRD&D	FY2011
Development of Seismic Isolation Systems Using Periodic Materials	University of Houston	$538,154		Document	MSTR	FY2011
Pebble Fuel Handling and Reactivity Control for Salt-Cooled High Temperature Reactors	University of California, Berkeley	$612,721		Document	RCRD&D	FY2011
Innovative Elution Processes for Recovering Uranium from Seawater	University of Idaho	$400,000		Document	MSTR	FY2011
Self-Sustaining Thorium Boiling Water Reactors	University of California, Berkeley	$1,145,932		Document	RCRD&D	FY2011
Development of Austenitic ODS Strengthened Alloys for Very High Temperature Applications	University of Illinois-Urbana Champaign	$538,154		Document	MSTR	FY2011
High Fluency Low Flux Embrittlement Models of LWR Reactor Pressure Vessel Embrittlement and a Supporting Database from the UCSB ATR-2 Irradiation Experiment	University of California, Santa Barbara	$1,199,607		Document	RCRD&D	FY2011
Enhancement of the Extraction of the Uranium from Seawater	University of Maryland	$400,000		Document	MSTR	FY2011
A Research Program for Fission Product/Dust Transport in HTGR's	University of Missouri-Columbia	$1,157,367		Document	RCRD&D	FY2011
Transient Safety Analysis of Fast Spectrum TRU Burning LWR with Internal Blankets	University of Michigan	$599,475		Document	MSTR	FY2011
Development and Validation of a Lifecycle-based Prognostics Architecture with Test Bed Validation	University of Tennessee, Knoxville	$846,315		Document	RCRD&D	FY2011
Development of Novel Sorbents for Uranium Extraction from Seawater	University of North Carolina, Chapel Hill	$400,000		Document	MSTR	FY2011
In-situ Condition Monitoring of Components in Small Modular Reactors Using Process and Electrical Signature Analysis	University of Tennessee, Knoxville	$650,000		Document	RCRD&D	FY2011
Radiation Behavior of High-Entropy Alloys for Advanced Reactors	University of Tennessee, Knoxville	$538,159		Document	MSTR	FY2011
Technical Development for S-CO2 Advanced Energy Conversion	University of Wisconsin	$815,000		Document	RCRD&D	FY2011
Rapid Computer Aided Ligand Design and Screening of Precious Metal Extractants from TRUEX Raffinate with Experimental Validation	Washington State University	$500,000		Document	MSTR	FY2011
Ag Transport Through Non-Irradiated and Irradiated SiC	University of Wisconsin-Madison	$1,055,456		Document	RCRD&D	FY2011
Critical Heat Flux Phenomena at High Pressure and Low Mass Fluxes: Tests and Models	University of Wisconsin-Madison	$1,199,781		Document	RCRD&D	FY2011
Modeling and Test Validation of a Reactor Cavity Cooling System with Air	University of Wisconsin-Madison	$1,199,988		Document	RCRD&D	FY2011
Transient Mixed Convection Validation for NGNP	Utah State University	$635,860		Document	RCRD&D	FY2011
Alternative High-Performance Ceramic Waste Forms	Alfred University	$840,000	This project aims to advance fundamental understanding of the kinetics of structural evolution of crystalline ceramic waste forms. The structure/property relationships will be identified and will reveal new formulations, improved processing routes, and strategies for improved performance or ceramic waste forms.	Document	FCR&D	FY2012
Surface Layer Bulk Glass Interface Evolution with Aqueous Corrosion	Alfred University	$880,000	This project will investigate the links between the morphology, structure and chemistry of surface layer-bulk glass interface and the long-term corrosion-reaction kinetics using in-situ and ex-situ experiments. The understanding will result in improved models for long-term predictive behavior of high-level-waste (HLW) glasses under repository conditions.	Document	FCR&D	FY2012
Improved Accident Tolerance of Austenitic Stainless Steel Cladding through Colossal Supersaturation with Interstitial Solutes	Case Western Reserve University	$850,000	This project aims to develop new case-hardened austenitic stainless steels by saturating them with materials that improve their mechanical properties, corrosion resistance and radiation resistance. This project, if successful, will result in safer, longer-lasting, and more accident tolerant fuel claddings.	Document	FCR&D	FY2012
Optimization of Deep Borehole Systems for HLW Disposal	Massachusetts Institute of Technology	$850,000	Researchers aim to carry out a comprehensive evaluation of the deep borehole option for disposal of used nuclear fuel and high livel waste. The models developed will predict potential movement of water through natural and engineered barriers and release of radionuclides to the biosphere which will aide in site selection.	Document	FCR&D	FY2012
Scholarship for Nuclear Communications and Methods for Evaluation of Nuclear Project Acceptability	Massachusetts Institute of Technology	$800,000	Researchers will work to develop a model to characterize the factors affecting social acceptance of nuclear projects with potential stakeholders. The resultant model will strengthen the ability to design and implement large projects more efficiently, leading to higher rates of success of future nuclear projects.	Document	FCR&D	FY2012
Accurate Holdup Calculations with Predictive Modeling and Data Integration	North Carolina State University	$875,000	Researchers will develop and use state-of-the-art radiation transport codes to account accurately for the fissile material in a nuclear materials processing facility. An accurate estimation of the materials will allow for ensured radiological safety, security, waste management and efficient plant operation.	Document	FCR&D	FY2012
Novel Metal Sulfides to Achieve Effective Capture and Durable Consolidation of Radionuclides	Northwestern University	$760,000	Researchers will evaluate the effectiveness of chalcogenide based materials design novel metal sulfides to effectively capture and store of radioisotopes released during reprocessing of used nuclear fuel. This project will focus on understanding structure-property relationships to enable refined and direct synthesis approaches for improved and cost-efficient nuclear waste forms.	Document	FCR&D	FY2012
Nonlinear Ultrasonic Diagnosis and Prognosis of ASR Damage in Dry Cask Storage	Northwestern University	$885,000	Researchers aim to use nondestructive damage characterization methods to detect, manage and mitigate the degradation/damage mechanisms of dry cask storage systems for nuclear fuels. This project, if successful, will provide tools that will allow the prediction of the reliability and the safety of concrete structures in dry cask storage systems.	Document	FCR&D	FY2012
Prototype Demonstration of Gamma-Blind Tensioned Metastable Fluid Neutron/Multiplicity/Alpha Detector- Real Time Methods for Advanced Fuel Cycle Applications	Texas A&M University	$875,000	This project aims to create a prototype demonstration of a novel neutron/alpha detector based on a technology that is blind to gamma field used fuel. The prototype, if successful, will enhance instrumentation for monitoring real-time material balance during various stages of the nuclear cycle.	Document	FCR&D	FY2012
Testing of Sapphire Optical Fiber and Sensors in Intense Radiation Fields, when Subjected to Very High Temperatures	The Ohio State University	$885,000	The researchers on this project will investigate the performance of sapphire optical fibers and sensors in reactor environments. The project, if successful, will result in improved instrumentation to understand the behavior and predict performance of nuclear fuel systems at the microstructural level.	Document	FCR&D	FY2012
Concrete Materials with Ultra-High Damage Resistance and Self-Sensing Capacity for Extended Nuclear Fuel Storage Systems	University of California, Irvine	$800,000	Researchers aim to design a new class of multifunctional concrete materials. This project, if successful, will result in a novel multifunctional concrete material that possesses inherent degradation monitoring capability and is suitable for an extended storage system for the used nuclear fuel.	Document	FCR&D	FY2012
Development of Innovative Accident Tolerant High Thermal Conductivity UO2 Fuel Pellets with a Diamond Dopant	University of Florida	$800,000	Researchers will evaluate the use of diamond nanoparticles composite material in innovative accident tolerant fuel pellets. This could significantly improve both the thermal conductivity of fuel pellets and light water reactors' efficiency safety.	Document	FCR&D	FY2012
Probabilistic Multi-Hazard Assessment of Dry Cask Structures	University of Houston	$865,000	This project aims to investigate the performance of dry cask storage systems under multiple hazard systems (earthquake, tornados, combined with aging effects) using a probabilistic multi-hazard framework. This framework will be validated based on experimental research and will provide improved models for safety and reliability of spent nuclear fuels during storage and transportation.	Document	FCR&D	FY2012
Measurement of Irradiated Pyroprocessing Samples via Laser Induced Breakdown Spectroscopy	University of Idaho	$820,000	This project aims to use advanced characterization techniques to investigate microstructural changes and the micromechanisms related to irradiation induced damage in used nuclear fuels and waste forms. This project, if successful, will result in enhanced models to predict the structural and chemical response of used fuel and waster forms during interim storage and permanent disposal.	Document	FCR&D	FY2012
Elastic/Inelastic Measurement Project	University of Kentucky	$880,523	Researchers will measure nuclear data for elastic/inelastic scattered neutrons on coolants and structural materials. The data generated, will be useful for future R&D programs that will study innovative next generation LWR and future fast systems.	Document	FCR&D	FY2012
Electrochemical Corrosion Studies for Modeling Metallic Waste Form Release Rates	University of Nevada- Las Vegas	$790,000	This project aims to use advanced electrochemical methods to investigate the corrosion related degradation of metal alloys used for housing fission products. The data obtained from this study will allow for the prediction of the long-term behavior of the metallic host phase materials over geological time-scales.	Document	FCR&D	FY2012
Thermodynamic and Microstructural Mechanisms in the Corrosion of Advanced Ceramic Tc-bearing Waste Forms and Thermophysical Properties	University of Nevada- Las Vegas	$795,000	This project team will harvest thermodynamic and microstructural data on the evolution of ceramic based waste forms. The data will be used to advance the current state-of-the-art methodology used for isolation and stabilization of fission products and improve on nuclear fuel recycling processes.	Document	FCR&D	FY2012
Development and Experimental Benchmark of Simulations to Predict Used Nuclear Fuel Cladding Temperatures during Drying and Transfer Operations	University of Nevada- Reno	$745,000	Researchers will conduct experiments to investigate and develop advanced computational models of heat transfer in post-pool-storage drying operations. This project, if successful, will result in tools that can be used to design efficient drying processes to as to ensure suitability for dry-cask systems for long-term storage and transport.	Document	FCR&D	FY2012
Better Radiation Response and Accident Tolerance of Nanostructured Ceramic Fuel Materials?	University of Tennessee	$815,000	Researchers will use novel experimental methods to investigate the links between microstructure, phase stability and damage evolution in nanostructured ceramic fuel materials. The project will study fuel materials at temperatures and irradiation conditions relevant to operation and accidental scenarios.	Document	FCR&D	FY2012
Radiation and Thermal Effects on Used Nuclear Fuel and Nuclear Waste Forms	University of Tennesssee	$770,000	This project aims to investigate the structural and chemical response of used nuclear fuel and waste forms during interim storage and permanent disposal. If successful, this project will generate models that will allow the prediction of structural evolution and hence the radiological safety and security of nuclear fuel and waste forms.	Document	FCR&D	FY2012
Seismic Performance of Dry Casks Storage for Long-Term Exposure	University of Utah	$873,319	Researchers will evaluate the mechanical performance of dry-cask storage under seismic loading for mid-term operational periods. Simulations will include scenarios for freestanding, anchored, and vaulted casks. The experimental tests will also evaluate the dynamic seismic response of freestanding and anchored dry-cask storage prototypes, providing recommendations for optimal Interim Spent Fuel Storage Installations (ISFSIs) design.	Document	FCR&D	FY2012
Validation Experiments for Spent-Fuel Dry-Cask In-Basket Convection	Utah State University	$690,000	Researchers in this project aim to conduct experiments that generate data on natural convection through a fuel assembly. The data will be used to validate the computational models being developed for nuclear safety and design.	Document	FCR&D	FY2012
Re-Branding the Nuclear Fuel Cycle	Virginia Commonwealth University	$850,000	This project will create a comprehensive framework for the evaluation of alternative fuel cycle systems that will be used to identify and analyze key elements related to long-term management of nuclear fuels , with the ultimate goal to develop a communications strategy to reach stakeholders.	Document	FCR&D	FY2012
Advanced Characterization of Molecular Interactions in TALSPEAK-like Separations Systems	Washington State University	$875,000	Researchers will use advanced characterization techniques (experimental and computational) to improve understanding of the molecular level processes/interactions during separation processes for advanced fuel cycles. The understanding of these interactions will be used to develop more robust and streamlined separation processes for advanced fuel cycles.	Document	FCR&D	FY2012
Coupling of Nuclear Waste Form Corrosion and Radionuclide Transport in Presence of Relevant Repository Sediments	Washington State University	$885,000	Researchers will conduct experiments to understand the mechanisms responsible for the corrosion of nuclear waste forms in realistic chemical environments. The data generated from these experiments will enable increased reliability of the models used to predict the waste form performance in repository environments.	Document	FCR&D	FY2012
Stationary Liquid Fuel Fast Reactor (SLFFR) Concept for TRU Burning	Purdue University	$450,000	Reasearchers will investigate a new type of molten metallic fuel reactor concept that will consume hazardous transuranic waste. The liquid fuel alloy has several advantages over solid fuel fast reactors that are used for the same purpose.	Document	MSTR	FY2012
ABR for TRU Transmutation with Breed & Burn Thorium Blanket for Improved Economics and Resource Utilization	University of California- Berkeley	$450,000	The research team will use detailed neutronic analysis for a new Advanced Burner Reactor concept with low conversion ratio. The concept will use a new core shape to improve the utilization of neutrons to perform breed and burn.	Document	MSTR	FY2012
New Materials for High Temperature Thermoelecric Power Generation	University of California, Davis	$450,000	Reasearchers will work to develop nanostructured and other new materials to support the development of higher efficiency thermoelectric devices. These devices convert thermal energy to electricity with no moving parts. The new materials will operate at higher efficiencies and over a wider temperature range than those currently available--an important quality for future nuclear-powered deep space exploration.	Document	MSTR	FY2012
Microscopic Fuel Particles Produced by Self-Assembly of Actinide Nanoclusters on Carbon Nanomaterials	University of Notre Dame	$440,000	Reasearchers will develop the mechanisms, conditions and protocols to prepare uranium-carbon nanocomposite materials to make them more flexible. This could result in the generation of wholesale electricity, providing process heat, and providing power for households.	Document	MSTR	FY2012
High Hydrogen Content Graphene Hydride Compounds & High Cross-Section Cladding Coatings for Fast Neutron Detection	University of South Carolina	$430,000	This project will exploit recent breakthroughs to grow epitaxial graphene on commercial SiC wafers. This will allow researchers to develop a new detection method for fast neutrons. In addition, it will lead to better and more compact neutron detection system.	Document	MSTR	FY2012
Reducing Actinide Production Using Inert Matrix Fuels	University of Texas- Austin	$435,000	Reasearchers will perform a neutronic analysis, a thermal-hydraulic analysis and a simulation of fuel decay heat as a functionof fuel burnup, to determine if inert matrix fuel in coventional reactors will continue to be licensable. If successful, the inert matrix fuel mixtures will reduce harmful transuranic components in the fuel discharge streams at a level comparable to a fast reactcor burner.	Document	MSTR	FY2012
An Integrated Fuel Depletion Calculator for Fuel Cycle Options Analysis	University of Texas- Austin	$395,000	Reasearchers use new analysis techniques to better predict nuclear fuel behavior. The new model will allow improved fuel cycle for a larger number of users.	Document	MSTR	FY2012
Atomic-Scale to Meso-Scale Simulation Studies of Thermal Ageing and Irradiation Effects in Fe-Cr Alloys	Boston University	$874,997	Reasearchers will develop predictive, multi-scale simulation tools for iron-chromium alloys, which are expected to be key components of advanced steels envisioned as fuel cladding and structural components for Generation IV reactors. Such modeling is necessary to avoid resource intensive and costly thermal and neutron irradiation experiments to obtain required performance data.	Document	NEAMS	FY2012
Validation Data and Model Development for Fuel Assembly Response to Seismic Loads	George Washington University	$862,435	Reasearchers will conduct experiments that will provide comprehensive data characterizing the dynamics of the fluid and the structure in Pressurized Water Reactors (PWR) fuel assemblies under seismic loads (earthquakes and loss of coolant accidents). Completion of their project will greatly benefit the safety of existing and future nuclear reactors.	Document	NEAMS	FY2012
Uncertainty Quantification and Management for Multiscale Nuclear Materials Modeling	Georgia Institute of Technology	$743,444	Reasearchers will address the question of uncertainty propogation and error estimates associated with model prediction of material behavior under irradiation. Their work will facilitate a better understanding of the connection of various unit processes to collective responses in a multiscale model chain enabling the development of high strength and high ductility materials.	Document	NEAMS	FY2012
Fuel and Core Design Options to Overcome the Heavy Metal Loading Limit and Improve Performance and Safety of Liquid Salt Cooled Reactors	Georgia Insitute of Technology	$784,689	Reasearchers will examine new options for fuel and core designs in liquid salt cooled reactors where the current standard of TRISO type fuel has limitations due to loading characteristics. The research could enable new, more feasible fuel-core-reload options that will improve safety and performance parameters.	Document	RCRD&D	FY2012
Nonlinear Ultrasonic Techniques to Monitor Radiation Damage in RPV and Internal Components	Georgia Institute of Technology	$877,000	Reasearchers will explore new nondestructive materials evaluation and monitoring techniques utilizing nonlinear ultrasonic measurements . This technique will allow researchers to assess remaining useful life of select reactor components. Breakthroughs in this area will lead to the ability to characterize radiation damage in reactor pressure vessels and other components-leading to a clearer definition of reactor safety margins.	Document	RCRD&D	FY2012
Intergral Reactor Containment Condensation Model and Experimental Validation	Oregon State University	$871,119	Reasearchers will conduct experiments to enhance the safety and efficiency of small modular reactors (SMRs). This project will assess the impact of high-pressure steam condensation on steel containment vessels to be used for SMR deigns.	Document	RCRD&D	FY2012
Investigation of Natural Circulation Instability and Transients in Passively Safe Small Modular Reactors	Purdue University	$871,100	Reasearchers will perform scaled experiments to study the thermal-hydraulic instabilities that can occur in Small Modular Reactors (SMR) which rely on natural circulation cooling during normal operation and accident conditions. Their work will not only improve our understanding of general natural circulation instability but also lead to the development of stability criteria and predictability in the operation of SMRÃs.	Document	RCRD&D	FY2012
Thermoelectric-Driven Sustainable Sensing and Actuation Systems for Fault-Tolerant Nuclear Incidents	State University of New York, Stony Brook	$599,802	Reasearchers will examine the use of solid-state thermoelectric generators to produce electricity to sense and opeate during both normal and abnormal situations. This will provide indefinite monitoring of key components during power outages or station blackouts.	Document	RCRD&D	FY2012
Experimental and CFD Studies of Coolant Flow Mixing within Scaled Models of the Upper and Lower Plenums of NGNP Gas-Cooled Reactors	Texas A&M University	$713,051	Reasearchers will model the internal coolant flow of a prismatic core very high temperature reactor (VHTR) by using large eddy simulation tools. This method will enable more accurate prediction of flow field characteristics and better evaluation of VHTR behavior under operational and accidental conditions.	Document	RCRD&D	FY2012
Demonstrating Hybrid Heat Transport and Energy Conversion System Performance Characterization Using Intelligent Control Systems	University of Idaho	$877,000	Reasearchers will demonstrate an intelligent control systems in a hybrid energy conversion loop for a next generation nuclear power plant. Hybrid energy systems are a method of optimizing the use of natural resources for energy production. Hybrid systems present an opportunity to develop domestic energy sources to improve energy security.	Document	RCRD&D	FY2012
Advanced Reactor-Intermediate Heat Exchanger (IHX) Coupling: Theoretical Modeling and Experimental Validation	University of Idaho	$869,997	Reasearchers will model the behavior of the Advanced Reactor Intermediate Heat Exchanger Chemical Process system and develop advanced control techniques that take into account abnormal scenarios. The data and information obtained will assist in the development of intelligent control systems for next generation nuclear reactor systems.	Document	RCRD&D	FY2012
Irradiation Performance of Fe-Cr Base Alloys	University of Illinois- Urbana Champaign	$876,332	Reasearchers will perform post-radiation analysis and develop tools for future development and application of the Fe-Cr class of alloys. The results of this research will lead to better modeling of performance and development of an alloy designated as the primary choice for reactor fuel cladding and structural applications in advanced systems.	Document	RCRD&D	FY2012
Accelerated Irradiations for High Dose Microstructures in Fast Reactor Alloys	University of Michigan	$831,876	Reasearchers will determine the extent to which high dose rate irradiation can be used as an irradiation damage tool to understand microstructure evolution at high doses and temperatures relevant to advanced fast reactors. The project will provide fundamental understanding of the effectiveness of this process and thus of microstructure development in irradiated materials.	Document	RCRD&D	FY2012
Mitigating IASCC of Reactor Core Internals by Post-Irradiation Annealing Advanced Mitigation Strategies	University of Michigan	$876,985	Reasearchers will determine the optimum Post-irradiation annealing (PIA)-driven mitigation strategy to extend the potential lifetime of light water reactors. Samples that have already been irradiated in a light water reactor will be used to test PIA treatments to understand IASCC initiation and propoagation, annealing kinetics, the role of microstructure features in irradation hardening and localized deformation, and the optimum mitigation strategy based on PIA.	Document	RCRD&D	FY2012
Experimentally Validated Numerical Models for Effects of Non-Isothermal Turbulent Mixing on Wall Stresses in High Temperature Reactors	University of Pittsburgh	$876,422	Reasearchers will develop a comprehensive experimentally validated computational framework for the turbulent mixing in the lower plenum of a very high temperature reactor (VHTR). Through CFD modeling and experimental validation, the results from this project will lay the groundwork for future stress analysis, failure and fatigue studies, and uncertainty quantification for the VHTR system.	Document	RCRD&D	FY2012
Role of Defects in Swelling and Creep of Irradiated SiC	University of Wisconsin- Madison	$875,350	Reasearchers will study mechanisms controlling both radiation swelling and radiation creep in silicon carbide. These two effects are crucial to understanding the issues associated with the brittle silicon carbide composite. Success in this project will ground progress in the adoption of silicon carbide for reactor solutions, particularly as fuel cladding.	Document	RCRD&D	FY2012
Advanced Supercritical Carbon Dioxide Brayton Cycle Development	University of Wisconsin, Madison	$877,000	Reasearchers will investigate the benefits of utilizing advanced Brayton cycles with supercritical carbon dioxide in new reactor systems and components. Benefits of this research include improvement of analysis and performance of components currently utilizing these cycles as well as the potential for a large scale advanced CO2 power system.	Document	RCRD&D	FY2012
Mechanical Behavior of UO2 at Sub-grain Length Scales: Quantification of Elastic, Plastic and Creep Properties via Microscale Testing	Arizona State University	$800,000	Reasearchers will develop techniques to measure properties at sub-grain scales using depleted Uranium Oxide samples. The project will provide a framework to measure sub-grain scale mechanical properties, as well as provide experimental data to improve the understanding of advanced oxide fuels.	Document	FCR&D	FY2013
The Impacts of Pore-Scale Physical and Chemical Heterogeneities on the Transport of Radionuclide-Carrying Colloids	Colorado School of Mines	$800,000	Reasearchers will identify the dominant transport mechanisms to develop models that predict radionuclide distribution in porous materials. Experimental and computational models will be created that couple pore-scale geometric and interfacial structures. Simulators such as these are a necessary step towards fully predictive models for field-scale applications in the future.	Document	FCR&D	FY2013
Recovery of Uranium from Seawater: Polymer-Supported Aminophosphinates as Selective Extractants	Hunter College, CUNY	$399,999	Reasearchers will prepare a polymer-supported extractant for the recovery of uranium from seawater. The project will focus on primary amines that could provide a 3-fold increase in uranium capture capacity than current methods.	Document	FCR&D	FY2013
In-pile Thermal Conductivity Characterization with Single-laser Heating/Time Resolved Raman	Iowa State University	$800,000	Reasearchers will develop a time-resolved Raman-based thermal conductivity measurement system to improve remote in-pile thermal conductivity measurement. These measurements will provide new insights into the behavior of materials exposed to extreme radiation and temperature environments. Understanding the behavior of materials at the microstructural level will support optimized fuel designs.	Document	FCR&D	FY2013
Organic Speciation and Interactions in ALSEP - One Step Partitioning Process of Minor Actinides, Lanthanides, and Fission Products	Oregon State University	$600,000	Reasearchers will investigate the Actinide-Lanthanide Separation (ALSEP) process organic phase prior to aqueous phase separation and after aqueous separation phases of bare and metal-loaded acids. Quantifying these effects can be used to determine how an engineering scale process will perform and generate an accurate chemical model for the system.	Document	FCR&D	FY2013
Glass Composition and Solution Speciation Effects on Stage III Dissolution	Pennsylvania State University	$700,000	Reasearchers will study the chemical and structural triggers of long-term vitrified nuclear waste form behavior. They will study a range of waste glass compositions in corrosive environments. The study will improve understanding of the long-term residual rate and may provide new options for environmental control of glass dissolution rates.	Document	FCR&D	FY2013
Correlating Thermal, Mechanical, and Electrical Coupling Based Multiphysics Behavior of Nuclear Materials Through In-Situ Measurements	Purdue University	$800,000	Reasearchers will use in-situ experimental techniques to monitor the influence of extreme conditions on fuel cladding. The project will establish an in-situ experimental setup that can predict change in thermal properties and their correlation with mechanical properties and correlate such changes to changes in microstructural and chemical features.	Document	FCR&D	FY2013
Creation of a Geant4 Muon Tomography Package for Imaging of Nuclear Fuel in Dry Cask Storage	Purdue University	$440,000	Reasearchers will develop a simulation and analysis package to aid in the non-destructive assessment of sealed used nuclear fuel dry casks using cosmic ray muons. Cosmic ray muon tomography allows for non-destructive assessment that can independently verify and identify weapons grade material sealed within dense dry casks.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Two-stage Fast Reactor Fuel Cycle Options for Optimum Resource Utilization and Waste Management	Purdue University	$400,000	Reasearchers will evaluate the two different two-stage fast reactor fuel cycle options that will offer efficient use of uranium resources and the ability to burn actinides and long-live fission products. Evaluation of these fast fuel cycle options will serve as a useful complement to the options currently being considered in the Fuel Cycle Options Campaign.	Document	FCR&D	FY2013
Mixed Metal Phosphonate-Phosphate Resins for Separation of Lanthanides from Actinides	Texas A&M University	$650,000	Reasearchers will use ion exchangers to cleanly separate lanthanides and curium from reusable actinides. The study will assist in the development of an inexpensive, simple way in which to separate lanthanides from actinides found in used nuclear fuel rods and to recover a large portion of the usable fuel.	Document	FCR&D	FY2013
Safeguards in Pyroprocessing: an Integrated Model Development and Measurement Data Analysis	The Ohio State University	$626,151	Reasearchers will develop a comprehensive and effective safeguards approach for a pyroprocessing facility to support safeguards for future fuel cycles in the United States. The new approach and design will focus directly on the special nuclear materials in the electrorefiner where actinides are separated from fission products through electrochemical process.	Document	FCR&D	FY2013
Using Ionic Liquids for the Development of Renewable Biopolymer-Based Adsorbents for the Extraction of Uranium from Seawater and Testing Under Marine Conditions	University of Alabama	$400,000	Reasearchers will explore the fundamental engineering parameters for a renewable high-performance adsorbent for the extraction of uranium from sweater based on a recently proven ionic liquid (IL)-chitin platform. The project will use the platform to develop a versatile, modifiable adsorbent and characterize its performance and degradation in marine conditions.	Document	FCR&D	FY2013
Developing Ultra-Small Scale Mechanical Testing Methods and Microstructural Investigation Procedures for Irradiated Materials.	University of California, Berkeley	$800,000	Reasearchers will develop new small-scale mechanical testing techniques to allow for the estimation or direct measurement of bulk properties. The combined experiments and modeling will significantly enhance the statistics and information that can be obtained on small radioactive archived samples, as well as new ion beam irradiated specimens.	Document	FCR&D	FY2013
Improved Delayed-Neutron Spectroscopy Using Trapped Ions	University of California, Berkeley	$400,000	Reasearchers will develop innovative spectroscopy techniques to measure the decay of fission fragments. The resulting data from these new techniques will be used to better understand reactor kinetics under accident conditions and failure scenarios.	Document	FCR&D	FY2013
Thermally and Chemically Responsive Nanoporous Materials for Efficient Capture of Fission Product Gases	University of California, Davis	$750,000	Reasearchers will create new nanoporous materials that will be highly effective at capturing fission product gases. These materials would be relevant to both reactor fuels applications and reprocessing operations. Tests will be performed in carbon based and nitride based nanostructures, with the most promising materials from the modeling perspective undergoing further testing.	Document	FCR&D	FY2013
Multiphase Nanocrystalline Ceramic Concept for Nuclear Fuel	University of California, Irvine	$800,000	Researchers will study the use of nanoparticles and nanostructured ceramics to create new materials that can extend the service life and increase efficiency for nuclear fuel. Multiphase nanocrystalline ceramics will be used to design simulated nuclear fuel that can provide added plasticity, better radiation tolerance and improved thermal conductivity.	Document	FCR&D	FY2013
Development of Novel Porous Sorbents for Extraction of Uranium from Seawater	University of Chicago	$400,000	Reasearchers will develop a highly porous sorbent for the extraction of uranium from seawater. Previous research has established sorbent performance. This project will use past foundational studies to design and investigate a new nanocomposites that will be processed into tacks or braids for field tests in seawater tests. The technology may also be used for other metals.	Document	FCR&D	FY2013
Microwave Readout Techniques for Very Large Arrays of Nuclear Sensors	University of Colorado, Boulder	$799,937	Reasearchers will develop a powerful readout technique based on microwave transmission and reflection. The technique will enable very large arrays of diverse sensor types for nuclear materials quantification and tracking. It will provide more accurate data on material composition and quantity.	Document	FCR&D	FY2013
BiI3 Gamma-Ray Spectrometers for Reliable Room-Temperature Nuclear Materials Safeguarding	University of Florida	$799,999	Reasearchers will develop gamma-ray spectrometers based on BiI3 single crystals for MPACT applications such as burnup validation quantification, improved assay of plutonium, determination of uranium enrichment and overall monitoring spent fuel within the fuel cycle. The project will improve energy resolution, efficiency and environmental performance with this new gamma-ray detector.	Document	FCR&D	FY2013
Innovative Coating of Nanostructured Vanadium Carbide on the F/M Cladding Tube Inner Surface for Mitigating the Fuel Cladding Chemical Interactions	University of Florida	$760,276	Researchers will develop barrier coatings on the inner surface of fuel cladding tubes to improve performance of materials at elevated temperatures and high neutron exposures in fast reactors. The project will develop and test a low temperature coating process of nanostructured vanadium carbide that will provide a benchmark for use in future studies.	Document	FCR&D	FY2013
Doubling the Life of Concrete Structures	University of Idaho	$800,000	Reasearchers will use nanoscale techniques to develop methods for doubling the service life of concrete structures. They will study the effect of temperature load and temperature cycling (freezing and thawing) on the durability of concrete with nanoscale viscosity modifiers. The project will benefit from non-destructive evaluation of concrete performance through electrochemical techniques.	Document	FCR&D	FY2013
Off-Gas Treatment: Evaluation of Nano-structured Sorbents for Selective Removal of Contaminants	University of Idaho	$785,910	Reasearchers will evaluate nanostructured sorbent materials for their effectiveness in removing and immobilizing radionuclides for the off-gas treatment from used nuclear fuel recycling operations. The project aims at achieving near-zero emissions of radionuclides by capturing them from the off-gas of recycling operations, allowing for the development of advanced fuel cycles.	Document	FCR&D	FY2013
Innovative Elution Processes for Recovering Uranium and Transition Metals from Amidoxime-Based Sorbents	University of Idaho	$399,864	Reasearchers will develop a new two-step elution process to achieve total recovery of uranium and effective recycling of the sorbent. The extraction process would selectively remove uranium from the sorbent with little or no damage. The process would then remove transition metals and regenerate the sorbent for repeated use, making uranium extraction from seawater economically viable.	Document	FCR&D	FY2013
Performance of a Steel/Oxide Composite Waste Form for Combined Waste Streams from Advanced Electrochemical Processes over Geologic Time Scales	University of Illinois at Chicago	$700,000	Reasearchers will develop and validate a mechanistically-based corrosion model for cermet-type waste forms, creating a testing protocol and modeling approach for predicting long-term performance. The study will apply novel electrochemical testing and modeling methods to the behavior of metal/oxide phase boundaries to evaluate waste form performance.	Document	FCR&D	FY2013
Enhancement of the Extraction of Uranium from Seawater	University of Maryland, College Park	$400,000	Reasearchers will develop and optimize novel adsorbents for uranium recovery from seawater. The team will use radiation-induced grafting of organic phosphates onto polymers. The experiments will use ocean water, with mechanistic analysis, to provide a solid basis for large-scale demonstration of the performance of the new adsorbents in ocean environments.	Document	FCR&D	FY2013
Improving the Understanding of the Coupled Thermal-Mechanical-Hydrologic Behavior of Consolidating Granular Salt	University of New Mexico	$800,000	Reasearchers will increase the understanding of granular salt seal materials for shafts, drifts and boreholes. By coupling thermal, mechanical and hydrological responses, the study will result in greater confidence in granular salt consolidation as a principal strategy for closure and isolation of long-term waste repositories.	Document	FCR&D	FY2013
Fission Fragment Yield Data in Support of Advanced Reactor Technology	University of New Mexico	$399,816	Reasearchers will produce a highly accurate data set for thermal fission. These precision data are necessary for high-accuracy simulations of nuclear criticality, transmutation rates, radiation effects and heating as well as for nuclear fuel, material accounting and identification needs.	Document	FCR&D	FY2013
Molecular dynamics-based simulations of bulk/interfacial structures and diffusion behaviors in nuclear waste glasses	University of North Texas	$700,000	Reasearchers will generate accurate atomic structural models for use in Monte Carlo simulations of the dissolution of nuclear waste glasses. Large-scale molecular dynamics-based computer simulations will be used to investigate self-diffusion behaviors, interfacial structure, and other structures formed during dissolution of these glasses.	Document	FCR&D	FY2013
U3Si2 Fabrication and Testing for Implementation into the BISON Fuel Performance Code	University of South Carolina	$800,000	Reasearchers will fabricate, test and model a high uranium density, advanced nuclear fuel that operates at a much lower temperature and stores less energy. The work will deliver key research data on creep and grain growth, improving economics, through possible power uprates, and advancing accident tolerant fuels research.	Document	FCR&D	FY2013
Structural Health Monitoring of Nuclear Spent Fuel Storage Facilities	University of South Carolina	$738,618	Reasearchers will develop a nuclear structural health monitoring system based on a sensing technology that monitors material degradation and aging for dry cask storage systems. The low-cost, low-profile sensors will perform on-demand monitoring of the structural integrity of individual components as well as the entire system.	Document	FCR&D	FY2013
ORIGEN-based Nuclear Fuel Depletion Module for Fuel Cycle Assessment	University of Tennessee at Knoxville	$755,181	Reasearchers will develop a flexible reactor analysis module for the CYCLUS fuel cycle simulator based on established tools for reactor fuel depletion and decay. They will use ORIGEN, a mature and experimentally validated code, affording greater flexibility and allowing for accurate evaluations of impacts of both present and future fuel cycle options.	Document	FCR&D	FY2013
Cost and System Analysis of Innovative Fuel Resources Concepts	University of Texas at Austin	$295,960	_This project will develop and test braided polymer fiber adsorbents that surpass the sorption capacity, selectivity and durability of the best existing technology to recover uranium from seawater.	Document	FCR&D	FY2013
Risk Assessment of Structural Integrity of Transportation Casks	University of Utah	$789,296	Reasearchers will assess the loss of structural integrity of transportation casks and fuel cladding after extended storage. This risk assessment will conduct experimental tests and simulations to evaluate the structural performance of fuel, fuel assemblies and cask components when subjected to vibration and impact loads during transport.	Document	FCR&D	FY2013
Market-Based and System-Wide Fuel Cycle Optimization	University of Wisconsin, Madison	$612,731	Reasearchers will create market and economic optimizers to improve calculations for the CYCLUS fuel cycle simulator. The team will leverage existing optimization software frameworks within the simulator to resolve top level policy questions. The optimizations will allow CYCLUS to move beyond static material compositions, providing a holistic view of the fuel cycle system.		FCR&D	FY2013
Optical Fiber Based System for Multiple Thermophysical Properties for Glove Box, Hot Cell and In-Pile Applications	Utah State University	$799,975	Reasearchers will use a small pressure vessel to develop a robust technique for the measurement of multiple thermophysical properties at very high temperatures. The technique will lead to a system design moving toward the eventual measurement of irradiated fuels in a glovebox and/or hot cell with all sensors and electronics outside of the glovebox and/or hot cell.	Document	FCR&D	FY2013
Development of a Nano-Modified Concrete for Next Generation of Storage Systems	Vanderbilt University	$796,268	Reasearchers will use nano-sized and nano-structured particles based on enhanced reactivity to develop a superior concrete for the long-term storage of used nuclear fuel. The project will use state-of-the-art experimental chemical and mechanical characterizations and computation analysis to assess the performance of nano-modified concretes.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Thorium Fuel Cycle Options	Vanderbilt University	$797,995	Reasearchers will develop six fuel cycle data packages for multi-stage, thermal fuel cycles which incorporate thorium. These new fuel cycle data packages will provide the opportunity to examine fuel cycle options beyond those which have traditionally been considered. A thorium fuel cycle database will also be assembled as a basis for thorium literature for future evaluations of the thorium fuel cycle.	Document	FCR&D	FY2013
Enhanced Shielding Performance of HLW Storage Packages via Multi-Component Coatings	Virginia Polytechnic Institute and State University	$796,947	Reasearchers will develop a multi-layer composite that will enhance long-term storage and facilitate safe transport of storage packages. This novel multi-layer, multi-component coating would create an outer shield material that is resistant to the corrosion, radiation, diffusion and thermal cycling processes that affect fuel packages during long term storage.	Document	FCR&D	FY2013
Managing Zirconium Chemistry and Phase Compatibility in Combined Process Separations for Minor Actinide Partitioning	Washington State University	$700,000	Reasearchers will address unique challenges for combining TRUEX and TALSPEAK processes for partitioning of lanthanides and minor actinides. The project will develop improved information on the thermodynamics of fission product zirconium and develop a framework for an organic phase solvation model. Combined process development could streamline separations processes.	Document	FCR&D	FY2013
Advances in the Recovery of Uranium from Seawater: Studies Under Real Ocean Conditions	Woods Hole Oceanographic Institution	$398,882	Reasearchers will provide infrastructure and expertise for marine testing of currently available adsorbents in real ocean conditions. The team will move adsorbent research from the lab to field testing in order to quantify sorptive properties and uranium uptake. The project will provide valuable field data that will show the potential of large scale applications of these technologies.	Document	FCR&D	FY2013
NEUP Project 20-19172: Irradiation of Sensors and Adhesive Couplants for Application in LWR Primary Loop Piping and Components		$497,881	Reasearchers paln to attach ultrasonic transducers to substrates using various adhesive couplants that will be irradiated at elevated temperature to simulate LWR primary loop conditions at the PULSTAR reactor at North Carolina State University. Ultrasonic data will be taken in-situ. Subsequently, the sensors and couplant interfaces will be characterized using the LAMDA facility at ORNL. The results will be used to benefit a parallel EPRI project on online monitoring of cracks in LWR primary loop piping._	Document	R&D NSUF	FY2013
NEUP Project 20-19404: Extension of MSTDB to Provide a High-Quality, Validated Thermochemical Database for Predicting/Simulating Corrosion in Molten Salt Reactor SystemsUniversity of South Carolina		$600,000	Reasearchers will generate a validated, consistent database of initial fuel compositions and potential corrossion products of fluoride and chloride salts, allowing for important phenomena predictions in molten salt reactors to guide confident decisions. The database will be integral to the currently being developed Molten Salt Thermochemical Database (MSTDB), structured to allow use by commercial and open source codes._	Document	NEAMS	FY2013
Lower Length Scale Characterization and Validation of Formation and Stability of Helium Bubbles in Nano-structured Ferritic Alloys under Irradiation	Clemson University	$399,870	Reasearchers will provide a fundamental knowledge about the formation and stability of ultra-fine helium bubbles within 14YWT after neutron/ion irradiation for further design of new advanced structural materials with a characteristic high density nanoparticles feature which can increase the mechanical strength, hardness, irradiation resistance and the operational temperature range of materials.	Document	NEAMS	FY2013
Three-Dimensional Fuel Pin Model Validation by Prediction of Hydrogen Distribution in Cladding and Comparison with Experiment	Pennsylvania State University	$800,000	Reasearchers will validate important three-dimensional aspects of the fuel pin modeling by using specialized numerical modeling techniques coupled with laboratory experiments to validate existing models for predicting fuel performance in light water reactors.	Document	NEAMS	FY2013
Collocation-Based Surrogate Models for Uncertainty Quantification and Validation of Coupled, Multiphysics Fuel Performance Simulation Tools	University of Michigan	$596,835	Reasearchers will provide the necessary high fidelity, coupled, multiphysics fuel performance simulator for computational modeling and develop surrogates which will accelerate and focus the validation of the coupled codes. This will be achieved by utilizing the high fidelity coupled fuel performance, thermal-hydraulics and neutronics codes BISON/STAR-CCM+/MPACT and an innovative collocation-based surrogate methodology.	Document	NEAMS	FY2013
Multi-Resolution In-Situ Testing and Mutliscale Simulation for Creep Damage Fatigue Damage Analysis of Alloy 617	Arizona State University	$800,000	This project will develop novel testing and experimentally validated prediction methodologies for micro-structural damage mechanisms of structural materials for advanced reactor systems. The investigations will focus on the characterization and testing of specific metal alloys, but the proposed testing and life-prediction methodologies are applicable to other structural materials as well.	Document	RCRD&D	FY2013
Novel High Temperature and Radiation Resistant Infrared Glasses and Optical Fibers for Sensing in Advanced Small Modular Reactors	Clemson University	$800,000	Clemson University, in partnership with the Iowa State University and the Pacific Northwest National Laboratory, will develop novel optical materials with improved heat and radiation exposure resistance in order to enable in-vessel fiber optic sensing for advanced Small Modular Reactors.	Document	RCRD&D	FY2013
Validation Data Acquisition in HTTF during PCC Events	George Washington University	$800,000	Reasearchers at the George Washington University and Oregon State University will collaborate with NASA Langley Research Center to measure flow velocities in a high temperature test facility. This work supports the development of very-high temperature reactors with passive safety systems.	Document	RCRD&D	FY2013
Advanced High Temperature Inspection Capabilities for Small Modular Reactors	Iowa State University	$790,822	The objective of this project is to develop non-destructive evaluation techniques for advanced small modular reactors. The research will provide key enabling inspection technologies needed to support the design and the reactor component performance validation process for advanced small modular reactors.	Document	RCRD&D	FY2013
Experimental and Computational Investigations of Plenum-to-Plenum Heat Transfer under Natural Circulation in a Prismatic Very High Temperature Reactor	Missouri University of Science and Technology	$799,999	Reasearchers will perform experimental and computational investigations to study heat transfer and natural circulation phenomena in very-high temperature reactors. The study will assist in the ability to predict and analyze passive safety systems.	Document	RCRD&D	FY2013
New Mechanistic Models of Creep-Fatigue Crack Growth Interactions for Advanced High Temperature Reactor Components	Oregon State University	$790,790	Reasearchers will create and validate a robust, multi-scale, numerical model to predict material degradation in nickel-based reactor alloys. If successful, this project will provide better numerical tools for reactor designers and greatly improve their capability to design against material failures for reactor alloys in the long term.	Document	RCRD&D	FY2013
Self-Powered Wireless Dual-mode Langasite Sensor for Pressure/Temperature Monitoring of Nuclear Reactors	State University of New York, Stony Brook	$800,000	This research will develop a novel self-powered wireless hybrid sensor that can accurately monitor both pressure and temperature using a single device without requiring external electricity, even in extreme harsh environments.	Document	RCRD&D	FY2013
Compact Heat Exchanger Design and Testing for Advanced Nuclear Reactors and Advanced Power Cycles	The Ohio State University	$800,000	The goal of this project is to investigate optimal heat exchanger designs for advanced reactors. The research will study the optimization of printed circuit heat exchangers for specific fluids under a variety of conditions as well as perform numerical modeling. Experiments will focus on thermal performance and heat stress during extreme conditions.	Document	RCRD&D	FY2013
Fundamental Understanding of Creep-Fatigue Interactions in 9Cr-1MoV Steel Welds	The Ohio State University	$798,000	This project will advance the state of knowledge and fundamental understanding of deforming materials and welds under loading conditions. Specifically, new integrated testing procedures will be evaluated and applied for conditions that are most detrimental to material stability leading to improved predictions of life expectancy for reactor steels and welds.	Document	RCRD&D	FY2013
Advanced Mechanistic 3D Spatial Modeling and Analysis Methods to Accurately Represent Nuclear Facility External Event Scenarios	The Ohio State University	$800,000	Reasearchers will develop three-dimensional characterization uncertainty analysis for commercial power plants. The project will involve combining experts from the fields of seismic structural modeling and advanced methods of risk assessment. This effort is expected to result in next generation tools that can be used for assessment of seismic risks.	Document	RCRD&D	FY2013
Tritium Mitigation/Control for Advanced Reactor Systems	The Ohio State University	$400,000	Reasearchers will develop a fluoride salt cooled high-temperature reactor featuring a specialized system to control tritium production. If successful, this will result in a significant reduction in size and cost in comparison to other reactor designs.	Document	RCRD&D	FY2013
A Pebble-Bed Breed and Burn Reactor	University of California, Berkeley	$400,000	Reasearchers will assess the feasibility of designing a type of metal cooled reactor able to establish and maintain operation when fueled with depleted uranium. If successful, this reactor will offer at least a 30-fold increase in the uranium ore utilization versus that achieved in contemporary light water reactors without the need for fuel reprocessing and recycling.	Document	RCRD&D	FY2013
Investigation of Thermal Aging Effects on the Evolution of Microstructure and Mechanical Properties of Cast Duplex Stainless Steels	University of Maryland, College Park	$799,966	This research will provide a better understanding of the microstructural evolution and simultaneous change in mechanical response during aging. The results of the research will provide data that can be used to estimate degraded mechanical properties for an 80-year service life of light water reactors.	Document	RCRD&D	FY2013
Model validation using CFD-grade experimental database for NGNP Reactor Cavity Cooling Systems with water and air	University of Michigan	$799,348	Reasearchers will use advanced innovative instrumentation to build a high-resolution experimental database and to use the novel experimental data to assess and further develop the predictive capabilities of computer codes for thermal hydraulics and computational fluid dynamics. The improved models developed by this project will also have the direct benefit of improving the predictive capability of the passive systems of third generation light water reactors and small modular reactor systems.	Document	RCRD&D	FY2013
Long-Term Prediction of Emissivity of Structural Material for High Temperature Reactor Systems	University of Missouri	$799,117	Reasearchers will study specific types of emissivity driven cooling from a variety of materials that are relevant to nuclear reactors. The research will provide a basis for numerical modeling to support reactor development.	Document	RCRD&D	FY2013
Advanced I&C for Fault-Tolerant Supervisory Control of Small Modular Reactors	University of Pittsburgh	$800,000	The purpose of this research is to develop advanced instrumentation and control techniques for supervisory control of advanced small modular reactors. This research supports the operational goals of small modular reactor concepts through the development of improved oversight and surveillance techniques.	Document	RCRD&D	FY2013
Corrosion of Structural Materials for Advanced Supercritical Carbon-Dioxide Brayton Cycle	University of Wisconsin-Madison	$798,672	Reasearchers will study a variety of materials for corrosion resistance under conditions that improve power conversion. In addition to studying the corrosion resistance of the materials, researchers will study the effect of additives to mitigate corrosion. Development of corrosion theories and modeling aimed at prediction of long-term corrosion will be the underlying theme throughout the project.	Document	RCRD&D	FY2013
Component and Technology Development for Advanced Liquid Metal Reactors	University of Wisconsin-Madison	$798,920	In support of liquid metal cooled reactors, the University of Wisconsin, Madison will evaluate advanced alloys and ceramics that come in contact with liquid metals. Additionally, a robust oxygen sensor and for use in liquid metals will be developed in order to better evaluate corrosion profiles in support of diagnostic testing.	Document	RCRD&D	FY2013
A New Paradigm for Understanding Multi-phase Ceramic Waste Form Performance	Clemson University	$800,000	Researchers will use advanced characterization tools to develop 3-D microstructural data that can be incorporated into computer-based simulations in order to predict the performance of waste forms. Materials system modeling will incorporate elemental release and the interconnected microstructural network of phases to better understand performance and degradation, which will accelerate waste form acceptance in repository settings.	Document	FCR&D	FY2014
Controlling Hexavalent Americium: A Centerpiece to a Compact Nuclear Fuel Cycle	Colorado School of Mines	$800,000	Researchers will develop and exploit the fundamental chemistry of Americium to enable an industrially viable means to co-recover the major and minor actinide elements from used nuclear fuel. The results would be a significant step forward in the development of aqueous separations approaches designed to recover the U-Am actinides based on the availability of the hexavalent oxidation state.	Document	FCR&D	FY2014
Zeolite Membranes for Krypton/Xenon Separation from Spent Nuclear Fuel Reprocessing Off-Gas	Georgia Institute of Technology	$400,000	Researchers will develop a high-performance, lower-cost zeolitic membrane process for Kr/Xe separations during spent nuclear fuel processing. Current separation methods are not considered economical and a membrane process would have relatively lower cost, equipment size, and ambient operating temperature. The process would form a sound basis for further development of this transformative separation technology for the nuclear fuel cycle.	Document	FCR&D	FY2014
Optimizing Polymer-Grafted Amidoxime-based Adsorbents for Uranium Uptake from Seawater	Georgia Institute of Technology	$399,999	Researchers will work to increase the adsorbent capacity and selectivity toward uranium by optimizing the adsorbent morphology, synthesis variables, and conditioning parameters and by investigating the rate-limiting variables through transport and reaction modeling. A novel adsorption/partition concept that has the potential to substantially increase the adsorbent capacity will be tested, making uranium from seawater extraction more economically viable.	Document	FCR&D	FY2014
Extraction of Uranium from Seawater: Design and Testing of a Symbiotic System	Massachusetts Institute of Technology	$400,000	Researchers will develop a seawater uranium extraction system that will work symbiotically with an offshore windmill by utilizing the structure, mooring and power of the windmill, while increasing the energy harvested by the installation. Uranium will be extracted by an adsorbent polymer belt, which will be cycled through the seawater and an elution plant located at the base of the windmill tower. Increasing the frequency of harvesting could overcome current economic barriers to seawater uranium extraction.	Document	FCR&D	FY2014
Imaging a Dry Storage Cask with Cosmic Ray Muons	Oregon State University	$799,871	Researchers will develop an imaging system to monitor the content of a dry storage cask with cosmic ray muons. A very large amount of plutonium under nuclear safeguards is contained in used fuel assemblies stored in dry storage casks. Muon imaging will allow a cost effective and reliable way to evaluate dry storage cask content and integrity before transport.	Document	FCR&D	FY2014
Apatite and sodalite based glass-bonded waste forms for immobilization of 129I and mixed halide radioactive wastes	Rutgers University	$800,000	Researchers will develop advanced and chemically durable waste forms for immobilizing 129I (aqueous based reprocessing of fuel) and mixed-halide wastes (molten-salt processing of fuel) by low temperature synthesis. Halide-containing sodalite and calcium phosphate-based apatite minerals will be synthesized, consolidated and tested for chemical durability. The project will provide needed baseline data for the development of advanced waste forms for immobilization of iodine and mixed-halide wastes.	Document	FCR&D	FY2014
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$350,000	Researchers will develop modeling tools supported by experiments for off-gas capture from future nuclear-fuel recycling facilities. Target species include tritium, iodine, krypton, and xenon. The models are intended to provide path forward recommendations to develop off-gas treatment adsorption processes. The project will contribute to the evaluation of options for environmentally acceptable recycle systems.	Document	FCR&D	FY2014
Development of high performance ODS alloys	Texas A&M University	$800,000	Researchers will study swelling, radiation hardening and changes in mechanical properties of ODS alloys to develop two sets of advanced ODS alloys. Two sets of first-round candidate alloys that have already undergone extensive development and testing will evaluate irradiation performance. The study will meet the need for high strength, radiation-tolerant cladding and core components that have enhanced resistance to void swelling.	Document	FCR&D	FY2014
Rare Earth Electrochemical Property Measurements and Phase Diagram Development in a Complex Molten Salt Mixture for Molten Salt Recycle	The Ohio State University	$800,000	Researchers will investigate rare earth (RE) properties in complex molten salt mixtures. In a molten salt recycle approach, the RE drawdown by electrolysis is a key step in which REs are separated from salt containing other fission products. Investigation of RE electrolysis must consider the electrochemical properties of the REs. We propose to conduct studies of detailed experiments and corresponding models to provide the physical properties and phase diagrams required to predict the performance of RE drawdown for processing complex molten salts.	Document	FCR&D	FY2014
Studies of Lanthanide Transport in Metallic Nuclear Fuels	The Ohio State University	$800,000	Researchers will study the redistribution of lanthanides and migration of lanthanides to the fuel surface. The mechanisms of lanthanide transport in metallic fuel based on the novel discovery of a Ôliquid-likeÕ transport mechanism will be studied analytically and experimentally. The project will develop a fundamental understanding of lanthanide fission product migration and redistribution in advanced metallic nuclear fuels, and theory and data to mitigate fuel-cladding chemical interactions.	Document	FCR&D	FY2014
Computational and Experimental Studies of Microstructure-Scale Porosity in Metallic Fuels for Improved Gas Swelling Behavior	University of Arkansas	$796,823	Researchers will study the microstructure of metallic uranium alloy fuels, and their resistance to densification, to minimize in-pile irradiation swelling through bimodal pore size distribution. The project will develop a predictive approach to design metallic fuel microstructures for optimal swelling resistance and fission gas retention.	Document	FCR&D	FY2014
Improved Hybrid Modeling of Spent Fuel Storage Facilities	University of California, Berkeley	$645,393	Researchers will develop a variance reduction method for computational transport that will improve the ability to design and operate monitoring systems for interim used fuel installations through enhanced modeling and simulation. This new tool will demonstrate that modeling calculations can be done more accurately in less time than with current tools and will perform studies characterizing how changes in material, cask configurations, and number of casks could impact monitoring systems.	Document	FCR&D	FY2014
Selective ligands for uranyl via combinatorial peptoid libraries: A synthetic, structural, thermodynamic and computational study	University of California, Berkeley	$400,000	Researchers will study how donor ligands bind to the uranyl ion, UO22+, with the longer-term goal of using this information to tackle selective recognition of uranyl in aqueous solution. The study will impact underlying approaches to controlling the behavior of uranium in these systems. The actinide separation technology could be used in several areas including uranium extraction from seawater, nuclear waste remediation and nuclear materials.	Document	FCR&D	FY2014
Combining Experiments and Simulations of Extraction Kinetics and Thermodynamics in Advanced Separation Processes for Used Nuclear Fuel	University of California, Irvine	$799,938	Researchers will study how the kinetics and thermodynamics of metal ion extraction in advanced separation processes for used nuclear fuel can be described by molecular dynamic (MD) simulations and how the simulations can be validated by experimental data. The project would have broad impacts on several separations processes including advanced TALSPEAK, ALSEP and GANEX by increasing the confidence and accuracy of computer modeling of metal ion extraction._	Document	FCR&D	FY2014
Effect of Metallic Li on the Behavior of Metals in Molten Salts	University of Nevada, Reno	$458,250	Researchers will identify the effect of metallic lithium on materials that are used in molten salt recycling. The study will try to understand how the presence of Li(0) in molten salts affects the degradation of alloys. Studying these changes will help accurately predict container material behavior and longevity.	Document	FCR&D	FY2014
Assessment of Corrosion Resistance of Promising Accident Tolerant Fuel Cladding under Reactor Conditions	University of Notre Dame	$800,000	Researchers will assess the corrosion behavior of accident tolerant fuel candidate iron-based alloys under normal LWR operating conditions consisting of high temperature, relevant water chemistry and irradiation. The assessment will produce data about possible irradiation-accelerated corrosion rates of iron-based alloys, and the mechanisms by which such corrosion rates are accelerated. The project will advance the selection of appropriate replacements for Zircaloy cladding.	Document	FCR&D	FY2014
Functionalized Porous Organic Polymers as Uranium Nano-Traps for Efficient Recovery of Uranium from Seawaterr	University of South Florida	$399,000	Researchers will develop functionalized porous organic polymers, or Ônano-trapsÕ for extraction of uranium from seawater. This technique allows for increased surface area and custom-designed pore size and chemistry to fit specific parameters. The adsorbent materials have high efficiency and effectiveness for uranium recovery from seawater, providing a potential supply for nuclear fuel.	Document	FCR&D	FY2014
Enhanced Accident-Tolerant Fuel Performance and Reliability for Aggressive iPWR/SMR Operation	University of Tennessee	$799,967	To develop a process that evaluates operational and safety performance of reactor-and-fuel combinations by integrating whole-core 3D neutronics with MOOSE/BISON fuel performance assessments via explicit time and space dependent fuel rod operational power histories. The project will be valuable in analyzing and evaluating accident tolerant fuel concepts and furthering the understanding of reactor physics and fuel performance aspects of key accident tolerant fuel concepts.	Document	FCR&D	FY2014
Nuclear Technology R&D Strategies in an Era of Energy Price Uncertainty	University of Texas, Austin	$799,112	Researchers will identify nuclear technology options that are competitive over a wide range of plausible future business environments. No single nuclear technology or business practice will be the best choice across all or even most future conditions. The study will focus on hybrid nuclear-fossil technologies, energy storage and conversion, which will result in an identification of nuclear strategies that can succeed under future market conditions.	Document	FCR&D	FY2014
Development and Optimization of Voltammetric Methods for Real Time Analysis of Electrorefiner Salt with High Concentrations of Actinides and Fission Products	University of Utah	$621,612	Researchers will develop an advanced voltammetry method to pursue the objective of real time monitoring of actinide concentrations in electrorefiner salt. This will include experimental measurement of key parameters such as activity coefficients and exchange current density. It will also involve simulation of voltammetry processes based on first principles. The project will allow for real time measurements that could support the commercialization of pyroprocessing.	Document	FCR&D	FY2014
Development of Self-Healing Zirconium-Silicide Coatings for Improved Performance of Zirconium-Alloy Fuel Cladding	University of Wisconsin, Madison	$798,621	Researchers will study the deposition of self-healing zirconium-silicide coatings on zirconium-alloy fuel cladding material to improve corrosion resistance under normal and accident conditions. Under these conditions, Zr-Si coating evolves into a highly protective functionally-graded multilayered system. The study will lead to improved performance of zirconium-alloy fuels._	Document	FCR&D	FY2014
Thermal Conductivity in Metallic Fuels	Virginia Polytechnic Institute and State University	$799,837	Researchers will calculate the thermal conductivity of metallic uranium and neptunium alloys, including the effects of noble gasses, using density functional theory. The experiments will validate the calculated effective thermal conductivity using the MARMOT code and by helping determine DFT simulation parameters. The study works to improve fuel lifetime by understanding its thermal behavior.	Document	FCR&D	FY2014
SiC-ODS Alloy Gradient Nanocomposites as Novel Cladding Materials	Virginia Polytechnic Institute and State University	$799,998	Researchers will combine nuclear nanomaterial design, processing, testing, and characterization efforts to develop revolutionary materials that can withstand neutron irradiation for long period of time using nanostructured SiC and oxide dispersion strengthened steel. The ultimate objective is to offer new cladding materials with increased corrosion resistance, strength, and creep resistance in both steady state and accident conditions.	Document	FCR&D	FY2014
Experimental Breeder Reactor II Benchmark Evaluation	Idaho State University	$400,000	Researchers will develop a benchmark evaluation of the Experimental Breeder Reactor II (EBR-II). During nearly 30 years of operation numerous experiments were conducted at EBR-II. The most significant of these experiments were conducted in 1986 demonstrating inherent safety features in loss of flow without reactor scram and loss of heat sink without reactor scram. Benchmark evaluation will be valuable for the reactor design efforts in the United States and South Korea.	Document	MSNE	FY2014
Integral full core multi-physics PWR benchmark with measured data	Massachusetts Institute of Technology	$400,000	Researchers will introduce BEAVRS, a new multi-cycle full-core Pressurized Water Reactor (PWR) depletion benchmark based on two operational cycles of a commercial nuclear power plant. This project aims at addressing the uncertainty quantification of the measured data and on making this benchmark a true non-proprietary international benchmark for the validation of high-fidelity multi-physics computational tools.	Document	MSNE	FY2014
Benchmark Evaluation of PROTEUS Gas-Cooled Reactor Experiments	University of Florida	$400,000	Researchers will create International Reactor Physics Experiment Evaluation Project (IRPhEP) benchmarks using data from 1970s experiments of the neutronics of gas-cooled fast reactor (GCFR) designs investigated in the PROTEUS reactor. The GCFR-PROTEUS experiments fill a gap in current integral benchmark data. These experiments can provide validation of computational models and nuclear data for next generation reactors.	Document	MSNE	FY2014
An Investigation To Establish Multiphysical Property Dataset Of Nuclear Materials Based On In-Situ Observations And Measurements	Purdue University	$800,000	Researchers will create an in-situ measurement based experimental approach to develop experimental validation dataset for NEAMS based code validation. Particular emphasis is on supplying data set for multiphysics simulations in extreme conditions as a function of material microstructure.	Document	NEAMS	FY2014
Experimental Validation of UO2 Microstructural Evolutions for NEAMS tool MARMOT	University of Florida	$798,000	Researchers will experimentally validate MARMOT for predicting the microstructural evolutions of UO2 oxide fuel under the driving forces of high temperatures and large temperature gradient in reactors. By performing the experiments and simulations simultaneously using precisely defined initial conditions, the experiment data will provide direct benchmarking of the MARMOT code.	Document	NEAMS	FY2014
High-resolution time-resolved experiments on mixing and entrainment of buoyant jets in stratified environments	University of Michigan	$799,983	Researchers will study high spatial and time-resolution experimental data of the fluid dynamics phenomena of flow jets interacting with a stratified layer. The issue plays an important role in the safety of several reactor designs, including sodium-cooled reactors. The data addresses the NEAMS needs for the validation of high fidelity computational fluid dynamics methodologies.	Document	NEAMS	FY2014
Fundamental study of key issues related to advanced S-CO2 Brayton Cycle: prototypic HX development and Cavitation	Georgia Institute of Technology	$799,000	Researchers will study scientific and operational issues pertinent to compact heat exchanger systems and turbo-machinery. The project will work to resolve issues with the fabrication of diffusion bonded compact heat exchangers, alternate heat exchange technology for recuperators, and resolution of issues with cavitation and fluid instabilities.	Document	RCRD&D	FY2014
Advanced Models for Nondestructive Evaluation of Aging Nuclear Power Plant Cables	Iowa State University	$787,291	Researchers will develop advanced models that relate environmentally induced microstructural and chemical changes in cable insulation polymers to their macroscopic electrical parameters. These parameters will be measured and modeled over a wide range of the electromagnetic spectrum, covering several potential nondestructive evaluation techniques, enabling identification of the most sensitive techniques for future development.	Document	RCRD&D	FY2014
Development of Novel Functionally Graded Transition Joints for Improving the Creep Strength of Dissimilar Metal Welds in Nuclear Applications	Lehigh University	$800,000	Researchers will develop graded transition joints and improved creep life models for increasing the life of dissimilar metal welds (DMWs) in nuclear reactors. The research represents the first application of functionally graded material concepts for solving the problem of DMW failures through an integrated approach of additive manufacturing, modeling, microstructural characterization, and advanced strain-sensing techniques.	Document	RCRD&D	FY2014
Feasibility Assessment of a Micro Modular Reactor (MMR)	North Carolina State University	$400,000	Researchers will develop an innovative compact reactor concept that integrates power production, power conversion and electricity generation in a single unit: the Micro Modular Reactor (MMR). It is designed to be absolutely melt-down proof (MDP) under all circumstances including complete loss of coolant scenarios with no possible release of radioactive material, to have a cycle length of greater than 10 years, and to be highly proliferation resistant.	Document	RCRD&D	FY2014
Scaling Studies for Advanced Gas Reactor Concepts	Oregon State University	$681,834	Researchers will expand the utilization of the Oregon State University High Temperature Test Facility (HTTF) to validate a broader range of advanced high temperature reactors and events. The facility will be revised to add a detailed scaling analysis of additional gas reactor concepts including advanced gas-cooled, molten salt, and sodium cooled reactors.	Document	RCRD&D	FY2014
Fluid Stratification Separate Effects Analysis, Testing and Benchmarking	Oregon State University	$800,000	Researchers will study fluid stratification in high temperature gas reactors. Coolant stratification is the result of incomplete mixing of one or more fluids, leading to a density gradient, which may or may not dissipate under diffusive or convective effects. This combined analytical and experimental project seeks to investigate stratification driven by diffusive and convective mechanisms and is expected to yield insight into this phenomenon.	Document	RCRD&D	FY2014
Probabilistic Economic Valuation of Safety Margin Management Analysis	Oregon State University	$795,364	Researchers will use RAVEN and develop a companion software package to facilitate economic analysis of safety margins. The project is a proof of concept that will use techniques to examine the cost of improving safety margins vs. the risk of accidents from not improving safety margins. This analysis can be used to evaluate the economic viability of various plant upgrades.	Document	RCRD&D	FY2014
Novel Dissimilar Joints Between Alloy 800H and 2.25%Cr and 1%Mo Steel	Pennsylvania State University	$800,000	Researchers will fabricate and test dissimilar metal joints between a nickel base alloy and a steel with gradual variations of chemical composition, microstructure and properties in a manner that reduces abrupt thermal expansion mismatch and the resulting residual stresses. Data on structure and properties will serve as valuable inputs for the initiation of an ASME code case.	Document	RCRD&D	FY2014
Multi-Phase Model Development to Assess RCIC System Capabilities under Severe Accident Conditions	Texas A&M University	$564,246	Researchers will develop physics-based models of the Reactor Core Isolation Cooling (RCIC) System and incorporating them into a multi-phase code for validation. The project will tackle the current major challenges in RCIC System analysis and enable evaluation of two-phase thermodynamic aspects.	Document	RCRD&D	FY2014
Experimental Investigation and CFD Analysis of Steam Ingress Accidents in HTGRs	The Ohio State University	$800,000	Researchers will study the steam ingress scenario for HTGRs. The study will investigate thermal-hydraulic behavior and graphite oxidation of stream ingress phenomena to validate predictive CFD models. This work will resolve concerns about possible steam generator tube ruptures in a HTGR He-Steam Rankine cycle.	Document	RCRD&D	FY2014
Coiled Tube Gas Heaters For Nuclear Gas-Brayton Power Conversion	University of California, Berkeley	$800,000	Researchers will develop heat exchangers for Brayton-cycle power conversion in reactors using sodium, NaK, or salt as intermediate coolants. The proposed coiled tube gas heaters (CTGHs) are expected to have excellent power density, thermal shock/creep, in-service inspection, and reparability characteristics.	Document	RCRD&D	FY2014
Fundamental Studies of Irradiation-Induced Modifications in Microstructural Evolution and Mechanical Properties of Advanced Alloys	University of Illinois, Urbana-Champaign	$800,000	Researchers will develop and test a mechanism for predicting neutron irradiation performance for optimized Grade 92 and Alloy 709 for applications in advanced reactor systems. The work will employ ion irradiations and available information from neutron irradiations of related alloys to develop a basis for predicting the neutron irradiation performance of the optimized alloys.	Document	RCRD&D	FY2014
Integrated Computational and Experimental Study of Radiation Damage Effects in Grade 92 Steel and Alloy 709	University of Tennessee	$800,000	Researchers will develop a mechanistic understanding and predictive models of irradiation-induced microstructural evolution and resulting mechanical properties in optimized ferritic-martensitic Grade 92 steel and austenitic alloy 709 using multiscale simulations coupled with rigorous experimental validation. The project will provide insights into the correlation between ion irradiation and fast neutron damage.	Document	RCRD&D	FY2014
Meta-Level Design Guidance and Operator Performance Measures for Hybrid Control Rooms	Vanderbilt University	$799,869	Researchers will apply human factors engineering methods and relevant expertise from non-nuclear high-risk high-consequence domains toward the measurement of operator performance in analog, digital, and hybrid main control rooms. Performance measures will be developed for evaluating the situation awareness and decision-making proficiencies to support the transition to digital or hybrid control room displays.	Document	RCRD&D	FY2014

FY 2009 Research and Development Awards

A complete list of R&D projects with their associated abstracts is available below.

Title	Institution	Estimated Funding*	Project Description	Abstract	Project Type	Fiscal Year
Neutron Damage and MAX Phase Ternary Compounds	Drexel University			Document	IIR	FY2009
Atomistic Calculations of the Effect of Minor Actinides on Thermodynamic and Kinetic Properties of UO2+x	Georgia Institute of Technology			Document	IIR	FY2009
Maximum Fuel Utilization in Fast Reactors without Chemical Reprocessing	University of California, Berkeley			Document	IIR	FY2009
Developing a High Thermal Conductivity Fuel with Silicon Carbide Additives	University of Florida			Document	IIR	FY2009
Fabrication of Tungsten-Rhenium Cladding Materials via Spark Plasma Sintering for Ultra High Temperature Reactor Applications	University of Idaho			Document	IIR	FY2009
Ionic Liquid and Supercritical Fluid Hyphenated Techniques for Dissolution and Separation of Lanthanides, Actinides, and Fission Products	University of Idaho			Document	IIR	FY2009
Improved Fission Neutron Data Base for Active Interrogation of Actinides	University of Michigan			Document	IIR	FY2009
Utilization of Methacrylates and Polymer Matrices for the Synthesis of Ion Specific Resins	University of Nevada, Las Vegas			Document	IIR	FY2009
Improved LWR Cladding Performance by EPD Surface Modification Technique	University of Wisconsin, Madison			Document	IIR	FY2009
Advanced Models of LWR Pressure Vessel Embrittlement for Low Flux-High Fluence Conditions	University of California, Santa Barbara			Document	LWRS	FY2009
Irradiation Creep in Graphite	Boise State University			Document	NGNP	FY2009
Modeling the Stress Strain Relationships and Predicting Failure Probabilities For Graphite Core Components	Cleveland State University			Document	NGNP	FY2009
TRISO-Coated Fuel Durability Under Extreme Conditions	Colorado School of Mines			Document	NGNP	FY2009
An Innovative and Advanced Coupled Neutron Transport and Thermal Hydraulic Method (Tool) for the Design, Analysis and Optimization of VHTR/NGNP Prismatic Reactors	Georgia Institute of Technology			Document	NGNP	FY2009
Removal of 14C from Irradiated Graphite for Graphite Recycle and Waste Volume Reduction	Idaho State University			Document	NGNP	FY2009
Millimeter-Wave Thermal Analysis Development and Application to Gen IV Reactor Materials	Massachusetts Institute of Technology			Document	NGNP	FY2009
Accurate Development of Thermal Neutron Scattering Cross Section Libraries	North Carolina State University			Document	NGNP	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
Understanding Creep Mechanisms in Graphite with Experiments, Multiscale Simulations, and Modeling	North Carolina State University			Document	NGNP	FY2009
Simulations of the Thermodynamic and Diffusion Properties of Actinide Oxide Fuel Materials	University of Michigan			Document	AFCI	FY2009
Verification & Validation of High-Order Short-Characteristics-Based Deterministic Transport Methodology on Unstructured Grids	North Carolina State University			Document	NGNP	FY2009
Adsorptive Separation and Sequestration of Krypton, I and C14 on Diamond Nanoparticles	University of Missouri, Columbia			Document	AFCI	FY2009
Microscale Heat Conduction Models and Doppler Feedback	North Carolina State University			Document	NGNP	FY2009
Fundamental Understanding of Ambient and High-Temperature Plasticity Phenomena in Structural Materials in Advanced Reactors	Georgia Institute of Technology			Document	AFCI	FY2009
Development of Alternative Technetium Waste Forms	University of Nevada, Las Vegas			Document	AFCI	FY2009
Optimizing Neutron Thermal Scattering Effects in Very High Temperature Reactors	North Carolina State University			Document	NGNP	FY2009
Advanced Elastic/Inelastic Nuclear Data Development Project	Idaho State University			Document	AFCI	FY2009
Heterogeneous Recycling in Fast Reactors	Massachusetts Institute of Technology			Document	AFCI	FY2009
Quantification of UV-Visible and Laser Spectroscopic Techniques for Materials Accountability and Process Control	University of Nevada, Las Vegas			Document	AFCI	FY2009
Multiaxial Creep-Fatigue and CreepRatcheting Failures of Grade 91 and Haynes 230 Alloys Toward Addressing Design Issues of Gen IV Nuclear Power Plants	North Carolina State University			Document	NGNP	FY2009
Thermodynamic Development of Corrosion Rate Modeling in Iron Phosphate Glasses	Missouri University of Science and Technology			Document	AFCI	FY2009
Development of Subspace-Based Hybrid Monte Carlo-Deterministic Algorithms for Reactor Physics Calculations	North Carolina State University			Document	AFCI	FY2009
High-Fidelity Space-Time Adaptive Multiphysics Simulations in Nuclear Engineering	University of Nevada, Reno			Document	AFCI	FY2009
Improvements to Nuclear Data and Its Uncertainties by Theoretical Modeling	Rensselaer Polytechnic Institute			Document	AFCI	FY2009
Investigation of Countercurrent Helium-air Flows in Air-ingress Accidents for VHTRs	Ohio State University			Document	NGNP	FY2009
Sharp Interface Tracking in Rotating Microflows of Solvent Extraction	State University of New York at Stony Brook			Document	AFCI	FY2009
Bulk Nanostructured FCC Steels with Enhanced Radiation Tolerance	Texas A&M University			Document	AFCI	FY2009
Simulations of Failure via Three-Dimensional Cracking in Fuel Cladding for Advanced Nuclear Fuels	University of Texas, Dallas			Document	AFCI	FY2009
Testing of Performance of Optical Fibers Under Irradiation in Intense Radiation Fields, When Subjected to Very High Temperatures	Ohio State University			Document	NGNP	FY2009
Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels	Texas A&M University			Document	AFCI	FY2009
SiC Schottky Diode Detectors for Measurement of Actinide Concentrations from Alpha Activities in Molten Salt Electrolyte	The Ohio State University			Document	AFCI	FY2009
Computational Design of Advanced Nuclear Fuels	University of California, Davis			Document	AFCI	FY2009
Advanced Mesh-Enabled Monte Carlo Capability for Multi-Physics Reactor Analysis	University of Wisconsin, Madison			Document	AFCI	FY2009
Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations	University of Idaho			Document	AFCI	FY2009
A Distributed Fiber Optic Sensor Network for Online 3-D Temperature and Neutron Fluence Mapping in a VHTR Environment	Texas A&M University			Document	NGNP	FY2009
Ab Initio Enhanced Calphad Modeling of Actinide Rich Nuclear Fuels	University of Wisconsin, Madison			Document	AFCI	FY2009
Investigation on the Core Bypass Flow in a Very High Temperature Reactor	Texas A&M University			Document	NGNP	FY2009
Development of Diffusion Barrier Coatings and Deposition Technologies for Mitigating Fuel Cladding Chemical Interactions (FCCI)	University of Wisconsin, Madison			Document	AFCI	FY2009
CFD Model Development and Validation for High Temperature Gas Cooled Reactor Cavity Cooling System (RCCS) Applications	Texas A&M University			Document	NGNP	FY2009
Thermal Properties of LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin, Madison			Document	AFCI	FY2009
Study of Air ingress across the duct during the accident conditions	Texas A&M University			Document	NGNP	FY2009
Verification of the CENTRM Module for Adaptation of the SCALE Code to NGNP Prismatic and PBR Core Designs	University of Arizona			Document	NGNP	FY2009
Integral and Separate Effects Tests for Thermal Hydraulics Code Validation for Liquid-Salt Cooled Nuclear Reactors	University of California, Berkeley			Document	NGNP	FY2009
Mechanisms Governing the Creep Behavior of High Temperature Alloys for Generation IV Nuclear Energy Systems	University of Cincinnati			Document	NGNP	FY2009
ALD Produced B2O3, Al2O3 and TiO2 Coatings on Gd2O3 Burnable Poison Nanoparticles	University of Colorado, Boulder			Document	NGNP	FY2009
Experimental Study and Computational Simulations of Key Pebble Bed Thermomechanics Issues for Design and Safety	University of Idaho			Document	NGNP	FY2009
Prediction and Monitoring Systems of Creep-Fracture Behavior of 9Cr-1Mo Steels for Reactor Pressure Vessels	University of Idaho			Document	NGNP	FY2009
Understanding Fundamental Material Degradation Processes in High Temperature Aggressive Chemomechanical Environments	University of Illinois, Urbana-Champaign			Document	NGNP	FY2009
Multi-Scale Multi-physics Methods Development for the Calculation of Hot-Spots in the NGNP	University of Michigan			Document	NGNP	FY2009
Corrosion and Creep of Candidate Alloys in High Temperature Helium and Steam Environments for the NGNP	University of Michigan			Document	NGNP	FY2009
Creation of a Full-Core HTR Benchmark with the Fort St. Vrain Initial Core and Validation of the DHF Method with Helios for NGNP Configurations	University of Michigan			Document	NGNP	FY2009
Fission Product Sorptivity in Graphite	University of Missouri, Columbia			Document	NGNP	FY2009
Identifying and Understanding Environment-Induced Crack Propagation Behavior in Ni-Based Superalloy INCONEL 617	University of Nevada, Las Vegas			Document	NGNP	FY2009
Graphite Oxidation Simulation in HTR Accident Conditions	University of New Mexico			Document	NGNP	FY2009
Non Destructive Thermal Analysis and In Situ Investigation of Creep Mechanism of Graphite and Ceramic Composites using Phase-sensitive THz Imaging & Nonlinear Resonant Ultrasonic Spectroscopy	University of Rochester			Document	NGNP	FY2009
Tritium Sequestration in Gen IV NGNP Gas Stream via Proton Conducting Ceramic Pumps	University of South Carolina			Document	NGNP	FY2009
Materials, Turbomachinery and Heat Exchangers for Supercritical CO2 Systems	University of Wisconsin, Madison			Document	NGNP	FY2009
Experimental Studies of NGNP Reactor Cavity Cooling System with Water	University of Wisconsin, Madison			Document	NGNP	FY2009
Assessment of Embrittlement of VHTR Structural Alloys in Impure Helium Environments	University of Wisconsin, Madison			Document	NGNP	FY2009
Modeling Fission Product Sorption in Graphite Structures	University of Wisconsin, Madison			Document	NGNP	FY2009
Liquid Salt Heat Exchanger Technology for VHTR Based Applications	University of Wisconsin, Madison			Document	NGNP	FY2009
Effect of Post-Weld Heat Treatment on Creep Rupture Properties of Grade 91 Steel Heavy Section Welds	Utah State University			Document	NGNP	FY2009
Alpha Radiolysis of Nuclear Solvent Extraction Ligands used for An(III) and Ln(III) Separations	California State University, Long Beach	$1,390,252		Document	FCR&D	FY2010
Predictive Maturity of Multi-Scale Simulation Models for Fuel Performance	Clemson University	$614,690		Document	FCR&D	FY2010
Freeze-casting as a Novel Manufacturing Process for Fast Reactor Fuels	Drexel University	$1,149,327		Document	FCR&D	FY2010
Fuel Performance Experiments on the Atomistic Level, Studying Fuel Through Engineered Single Crystal UO2	Idaho State University	$650,000		Document	FCR&D	FY2010
Development of A Self Biased High Efficiency Solid-State Neutron Detector for MPACT Applications	Rensselaer Polytechnic Institute	$810,141		Document	FCR&D	FY2010
Development of a Innovative High Thermal Conductivity UO 2 Ceramic Composites Fuel Pellets with Carbon Nano-Tubes Using Spark Plasma Sintering	University of Florida	$894,042		Document	FCR&D	FY2010
Exploration and Modeling of Structural Changes in Waste Glass under Corrosion	Pennsylvania State University	$1,377,444		Document	FCR&D	FY2010
Evaluation of materials for interim storage of spent fuel for more than 100 years	University of Michigan	$931,603		Document	FCR&D	FY2010
Implementation of On-the-Fly Doppler Broadening in MCNP5 for Multiphysics Simulation of Nuclear Reactors	University of Michigan	$406,712		Document	FCR&D	FY2010
Methods and tools to allow molecular flow simulations to be coupled to higher level continuum descriptions of flows in porous/fractured media and aerosol/dust dynamics	University of Missouri-Columbi	$541,286		Document	FCR&D	FY2010
Characterization and Modeling of Materials for Kr-Xe Separations	University of Nevada-Las Vegas	$989,800		Document	FCR&D	FY2010
Modeling Solute Thermokinetics in LiCl-KCl Molten Salt for Nuclear Waste Separation	University of Wisconsin-Madison	$616,073		Document	FCR&D	FY2010
Advanced Aqueous Separation Systems for Actinide Partitioning: Develop Fundamental Understanding of An(III)/Ln(III) Separation	Washington State University	$1,451,784		Document	FCR&D	FY2010
Consistent Multigroup Theory Enabling Accurate Coarse-Group Simulation of GenIV Reactors	Georgia Institute of Technology	$1,046,277		Document	GEN IV	FY2010
Studies of Deteriorated Heat Transfer in Prismatic Cores Stemming from Irradiation-Induced Geometry Distortion	Idaho State University	$1,287,921		Document	GEN IV	FY2010
Carbide Coatings for Nickel Alloys, Graphite, and Carbon/Carbon Composites to be Used in Fluoride Salt Valves	Johns Hopkins University	$1,183,239		Document	GEN IV	FY2010
Design, Testing, and Modeling of the Direct Reactor Auxiliary Cooling System for AHTRs	Ohio State University	$1,366,627		Document	GEN IV	FY2010
Monitoring microstructural evolution of Alloy 617 with nonlinear acoustics for remaining useful life prediction; multiaxial creep-fatigue and creep-ratcheting	Pennsylvania State University	$1,000,000		Document	GEN IV	FY2010
Development and Validation of Multidimensional Models of Supercritical CO 2 Energy Conversion Systems for Nuclear Power Reactors	Rensselaer Polytechnic Institute	$475,005		Document	GEN IV	FY2010
Multiscale Concrete Modeling for Aging Degradation	Mississippi State University	$345,941		Document	LWRS	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term and Elevated Temperature Irradiation: Modeling and Experimental Investigation	University of California-Berkeley	$1,320,667		Document	GEN IV	FY2010
Development of an advanced computational fluid dynamics technology for the next-generation nuclear reactor system analysis and safety margin characterization code	North Carolina State University	$418,199		Document	LWRS	FY2010
Development of Barrier Layers for the Protection of Candidate Alloys in the VHTR	University of California-Santa Barbara	$995,232		Document	GEN IV	FY2010
Precursor Derived Nanostructured Si-C-X Materials for Nuclear Applications	University of Washington	$899,518		Document	MRIIR	FY2010
Investigation of a Novel NDE Method for Monitoring Thermo-Mechanical Damage and Microstructure Evolution in Ferritic-Martensitic Steels for Generation IV Nuclear Energy Systems	University of Cincinnati	$833,109		Document	GEN IV	FY2010
Development and Testing of an Open-Loop Oscillator for Small Reactivity Worth Samples	Idaho State University	$597,252		Document	MRIIR	FY2010
Fission Product Transport in TRISO Particle Layers under Operating and Off-Normal Conditions	University of Michigan	$966,581		Document	GEN IV	FY2010
Understanding the Irradiation Behavior of Zirconium Carbide	Pennsylvania State University	$870,613		Document	MRIIR	FY2010
Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term Irradiation at Elevated Temperature: Critical Experiments	University of Michigan	$1,181,379		Document	GEN IV	FY2010
Modeling investigation of the stability and irradiation-induced evolution of nanoscale precipitates in advanced structural materials	University of Tennessee-Knoxville	$380,653		Document	MRIIR	FY2010
Three-dimensional NDE of VHTR Core Components via Simulation-based Testing	University of Minnesota	$1,366,163		Document	GEN IV	FY2010
Investigation of Laser Shock Peening for Enhancing Fatigue and Stress Corrosion Cracking Resistance of Nuclear Energy Materials	University of Cincinnati	$1,242,019		Document	MRIIR	FY2010
Failure Predictions for VHTR Core Components using a Probabilistic Continuum Damage Mechanics Model	University of Minnesota	$854,542		Document	GEN IV	FY2010
Irradiation Accelerated Corrosion of Reactor Core Materials	University of Michigan	$798,943		Document	MRIIR	FY2010
Development of a Scanning Microscale Fast Neutron Irradiation Platform for Examining the Correlation Between Local Neutron Damage and Graphite Microstructure	University of Missouri-Columbia	$703,064		Document	GEN IV	FY2010
Study of Interfacial Interactions using Thin Film Surface Modification: Radiation and Oxidation Effects in Materials	University of Wisconsin-Madison	$538,032		Document	MRIIR	FY2010
Development of Thermal Transient Flow Rate Sensors for High Temperature, Irradiation, Corrosive Environment	University of Nevada-Las Vegas	$451,269		Document	GEN IV	FY2010
Novel Engineered Refractory Materials for Advanced Reactor Applications	North Carolina State University	$1,129,304		Document	MRIIR	FY2010
Novel Methods of Tritium Sequestration: High Temperature Gettering and Separation Membrane Materials Discovery for Nuclear Energy Systems	University of South Carolina	$1,366,626		Document	GEN IV	FY2010
Heat Transfer Salts for Nuclear Reactor Systems - Chemistry Control, Corrosion Mitigation, and Modeling	University of Wisconsin-Madison	$1,352,040		Document	GEN IV	FY2010
Pulsed Magnetic Welding for Advanced Core and Cladding Steels	University of Wisconsin-Madison	$525,206		Document	GEN IV	FY2010
Corrosion in Supercritical Carbon Dioxide: Materials, Environmental Purity, Surface Treatments, and Flow Issues	University of Wisconsin-Madison	$651,447		Document	GEN IV	FY2010
Quantification of Cation Sorption to Engineered Barrier Materials Under Extreme Conditions	Clemson University	$1,171,380		Document	FCR&D	FY2011
In-Pile Instrumentation Multi-Parameter System Utilizing Photonic Fibers and Nanovision	Idaho State University	$1,199,990		Document	FCR&D	FY2011
Development of Plasmonically Cloaked Nanoparticles	Idaho State University	$800,000		Document	FCR&D	FY2011
Fission Product Transmutation in Mixed Radiation Fields	Idaho State University	$800,000		Document	FCR&D	FY2011
Life Prediction of Spent Fuel Storage Canister Material	Massachusetts Institute of Technology	$899,826		Document	FCR&D	FY2011
Active Interrogation using Photofission Technique for Nuclear Materials Control and Accountability	Oregon State University	$900,000		Document	FCR&D	FY2011
Anisotropic Azimuthal Power and Temperature Distribution on Fuel Rod: Impact of Hydride Distribution	Pennsylvania State University	$631,956		Document	FCR&D	FY2011
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$1,000,000		Document	FCR&D	FY2011
Recovery of Uranium from Seawater: Preparation and Development of Polymer-Supported Extractants	City College of New York, Hunter	$363,716		Document	MSTR	FY2011
Microemulsions and Aggregation Formation in Extraction Processes for Used Nuclear Fuel: Thermodynamics and Structural Studies	University of California, Irvine	$1,000,000		Document	FCR&D	FY2011
One-Dimensional Nanostructures for Neutron Detection	North Carolina State University	$455,629		Document	MSTR	FY2011
Optimized Processing Fabrication Paths for Larger Heats of Nanostructured Ferritic Alloys	University of California, Santa Barbara	$1,000,000		Document	FCR&D	FY2011
Feasibility and Safety Assessment for Advanced Reactor Concepts Using Vented Fuel	Oregon State University	$600,000		Document	MSTR	FY2011
Basic Physics Data: Measurement of Neutron Multiplicity from Induced Fission	University of Michigan	$973,364		Document	FCR&D	FY2011
Development of an Efficient Meso-Scale Multi-Phase Flow Solver in Nuclear Applications	City College of New York	$505,858		Document	NEAMS	FY2011
High Temperature Transducers for Online Monitoring of Microstructure Evolution	Pennsylvania State University	$455,628		Document	MSTR	FY2011
Radionuclide Incorporation and Long Term Performance of Apatite Waste Forms	University of Michigan	$862,500		Document	FCR&D	FY2011
Multiscale Modeling and Uncertainty Quantification for Nuclear Fuel Performance	Colorado State University	$1,098,250		Document	NEAMS	FY2011
Laser-Arc Hybrid Welding of Thick Section Ni-base Alloys- Advanced Modeling and Experiments	Pennsylvania State University	$536,117		Document	MSTR	FY2011
Actinide Foil Production for MPACT Research	University of Nevada-Las Vegas	$156,897		Document	FCR&D	FY2011
Fundamental Studies of the Role of Grain Boundaries on Uniform Corrosion of Advanced Nuclear Reactor Materials	Drexel University	$1,098,250		Document	NEAMS	FY2011
Correlates of Sensitive Technologies	Texas A&M University	$509,467		Document	MSTR	FY2011
Enriched Boron-Doped Amorphous Selenium Based Position-Sensitive Solid-State Thermal Neutron Detector for MPACT Applications	University of South Carolina	$1,000,000		Document	FCR&D	FY2011
Phenomena-based Uncertainty Quantification in Predictive Coupled-Physics Reactor Simulations	Texas A&M University	$1,098,250		Document	NEAMS	FY2011
Improved Safety Margin Characterization of Risk from Loss of Offsite Power	Texas A&M University	$600,000		Document	MSTR	FY2011
Development of Advanced High Uranium Density Fuels for Light Water Reactors	University of Wisconsin-Madison	$1,000,000		Document	FCR&D	FY2011
Characterization of Modeling of Grain Boundary Chemistry Evolution in Ferritic Steels Under Irradiation	University of Michigan	$1,098,250		Document	NEAMS	FY2011
Diffusion, Thermal Properties and chemical Compatibilities of Select MAX Phases with Materials for Advanced Nuclear Systems	Drexel University	$535,927		Document	NEET	FY2011
A High Temperature-Tolerant and Radiation-Resistant In-Core Neutron Sensor for Advanced Reactors	The Ohio State University	$455,629		Document	MSTR	FY2011
Developing the User Experience for a Next Generation Nuclear Fuel Cycle Simulator	University of Wisconsin-Madison	$1,200,000		Document	FCR&D	FY2011
Development of Multiscale Materials Modeling Techniques and Coarse-Graining Strategies for Predicting Materials Degradation in Extreme Irradiation Environments	University of Tennessee, Knoxville	$750,000		Document	NEAMS	FY2011
A New Light Weight Structural Material for Nuclear Structures	North Carolina State University	$399,490		Document	NEET	FY2011
Pathway Aggregation in the Risk Assessment of Proliferation Resistance and Physical Protection (PR&PP) of Nuclear Energy Systems	The Ohio State University	$534,471		Document	MSTR	FY2011
Experimental Investigation of Convection and Heat Transfer in the Reactor Core for a VHTR	City College of New York	$1,118,856		Document	RCRD&D	FY2011
Preparation of High Purity, High Molecular-Weight Chitin from Ionic Liquids for Use as an Adsorbate for the Extraction of Uranium from Seawater	University of Alabama	$338,260		Document	MSTR	FY2011
Graphite Microstructural Characterization Using Time-Domain and Correlation-Based Ultrasonics	Johns Hopkins University	$1,199,997		Document	RCRD&D	FY2011
Selectivity in Ligand Binding to Uranyl Compounds: A Synthetic, Structural, Thermodynamic and Computational Study	University of California-Berkeley	$500,000		Document	MSTR	FY2011
Methodology Development for Passive Component Reliability Modeling in a Multi-Physics Simulation Environment	The Ohio State University	$533,457		Document	RCRD&D	FY2011
Development of Seismic Isolation Systems Using Periodic Materials	University of Houston	$538,154		Document	MSTR	FY2011
Pebble Fuel Handling and Reactivity Control for Salt-Cooled High Temperature Reactors	University of California, Berkeley	$612,721		Document	RCRD&D	FY2011
Innovative Elution Processes for Recovering Uranium from Seawater	University of Idaho	$400,000		Document	MSTR	FY2011
Self-Sustaining Thorium Boiling Water Reactors	University of California, Berkeley	$1,145,932		Document	RCRD&D	FY2011
Development of Austenitic ODS Strengthened Alloys for Very High Temperature Applications	University of Illinois-Urbana Champaign	$538,154		Document	MSTR	FY2011
High Fluency Low Flux Embrittlement Models of LWR Reactor Pressure Vessel Embrittlement and a Supporting Database from the UCSB ATR-2 Irradiation Experiment	University of California, Santa Barbara	$1,199,607		Document	RCRD&D	FY2011
Enhancement of the Extraction of the Uranium from Seawater	University of Maryland	$400,000		Document	MSTR	FY2011
A Research Program for Fission Product/Dust Transport in HTGR's	University of Missouri-Columbia	$1,157,367		Document	RCRD&D	FY2011
Transient Safety Analysis of Fast Spectrum TRU Burning LWR with Internal Blankets	University of Michigan	$599,475		Document	MSTR	FY2011
Development and Validation of a Lifecycle-based Prognostics Architecture with Test Bed Validation	University of Tennessee, Knoxville	$846,315		Document	RCRD&D	FY2011
Development of Novel Sorbents for Uranium Extraction from Seawater	University of North Carolina, Chapel Hill	$400,000		Document	MSTR	FY2011
In-situ Condition Monitoring of Components in Small Modular Reactors Using Process and Electrical Signature Analysis	University of Tennessee, Knoxville	$650,000		Document	RCRD&D	FY2011
Radiation Behavior of High-Entropy Alloys for Advanced Reactors	University of Tennessee, Knoxville	$538,159		Document	MSTR	FY2011
Technical Development for S-CO2 Advanced Energy Conversion	University of Wisconsin	$815,000		Document	RCRD&D	FY2011
Rapid Computer Aided Ligand Design and Screening of Precious Metal Extractants from TRUEX Raffinate with Experimental Validation	Washington State University	$500,000		Document	MSTR	FY2011
Ag Transport Through Non-Irradiated and Irradiated SiC	University of Wisconsin-Madison	$1,055,456		Document	RCRD&D	FY2011
Critical Heat Flux Phenomena at High Pressure and Low Mass Fluxes: Tests and Models	University of Wisconsin-Madison	$1,199,781		Document	RCRD&D	FY2011
Modeling and Test Validation of a Reactor Cavity Cooling System with Air	University of Wisconsin-Madison	$1,199,988		Document	RCRD&D	FY2011
Transient Mixed Convection Validation for NGNP	Utah State University	$635,860		Document	RCRD&D	FY2011
Alternative High-Performance Ceramic Waste Forms	Alfred University	$840,000	This project aims to advance fundamental understanding of the kinetics of structural evolution of crystalline ceramic waste forms. The structure/property relationships will be identified and will reveal new formulations, improved processing routes, and strategies for improved performance or ceramic waste forms.	Document	FCR&D	FY2012
Surface Layer Bulk Glass Interface Evolution with Aqueous Corrosion	Alfred University	$880,000	This project will investigate the links between the morphology, structure and chemistry of surface layer-bulk glass interface and the long-term corrosion-reaction kinetics using in-situ and ex-situ experiments. The understanding will result in improved models for long-term predictive behavior of high-level-waste (HLW) glasses under repository conditions.	Document	FCR&D	FY2012
Improved Accident Tolerance of Austenitic Stainless Steel Cladding through Colossal Supersaturation with Interstitial Solutes	Case Western Reserve University	$850,000	This project aims to develop new case-hardened austenitic stainless steels by saturating them with materials that improve their mechanical properties, corrosion resistance and radiation resistance. This project, if successful, will result in safer, longer-lasting, and more accident tolerant fuel claddings.	Document	FCR&D	FY2012
Optimization of Deep Borehole Systems for HLW Disposal	Massachusetts Institute of Technology	$850,000	Researchers aim to carry out a comprehensive evaluation of the deep borehole option for disposal of used nuclear fuel and high livel waste. The models developed will predict potential movement of water through natural and engineered barriers and release of radionuclides to the biosphere which will aide in site selection.	Document	FCR&D	FY2012
Scholarship for Nuclear Communications and Methods for Evaluation of Nuclear Project Acceptability	Massachusetts Institute of Technology	$800,000	Researchers will work to develop a model to characterize the factors affecting social acceptance of nuclear projects with potential stakeholders. The resultant model will strengthen the ability to design and implement large projects more efficiently, leading to higher rates of success of future nuclear projects.	Document	FCR&D	FY2012
Accurate Holdup Calculations with Predictive Modeling and Data Integration	North Carolina State University	$875,000	Researchers will develop and use state-of-the-art radiation transport codes to account accurately for the fissile material in a nuclear materials processing facility. An accurate estimation of the materials will allow for ensured radiological safety, security, waste management and efficient plant operation.	Document	FCR&D	FY2012
Novel Metal Sulfides to Achieve Effective Capture and Durable Consolidation of Radionuclides	Northwestern University	$760,000	Researchers will evaluate the effectiveness of chalcogenide based materials design novel metal sulfides to effectively capture and store of radioisotopes released during reprocessing of used nuclear fuel. This project will focus on understanding structure-property relationships to enable refined and direct synthesis approaches for improved and cost-efficient nuclear waste forms.	Document	FCR&D	FY2012
Nonlinear Ultrasonic Diagnosis and Prognosis of ASR Damage in Dry Cask Storage	Northwestern University	$885,000	Researchers aim to use nondestructive damage characterization methods to detect, manage and mitigate the degradation/damage mechanisms of dry cask storage systems for nuclear fuels. This project, if successful, will provide tools that will allow the prediction of the reliability and the safety of concrete structures in dry cask storage systems.	Document	FCR&D	FY2012
Prototype Demonstration of Gamma-Blind Tensioned Metastable Fluid Neutron/Multiplicity/Alpha Detector- Real Time Methods for Advanced Fuel Cycle Applications	Texas A&M University	$875,000	This project aims to create a prototype demonstration of a novel neutron/alpha detector based on a technology that is blind to gamma field used fuel. The prototype, if successful, will enhance instrumentation for monitoring real-time material balance during various stages of the nuclear cycle.	Document	FCR&D	FY2012
Testing of Sapphire Optical Fiber and Sensors in Intense Radiation Fields, when Subjected to Very High Temperatures	The Ohio State University	$885,000	The researchers on this project will investigate the performance of sapphire optical fibers and sensors in reactor environments. The project, if successful, will result in improved instrumentation to understand the behavior and predict performance of nuclear fuel systems at the microstructural level.	Document	FCR&D	FY2012
Concrete Materials with Ultra-High Damage Resistance and Self-Sensing Capacity for Extended Nuclear Fuel Storage Systems	University of California, Irvine	$800,000	Researchers aim to design a new class of multifunctional concrete materials. This project, if successful, will result in a novel multifunctional concrete material that possesses inherent degradation monitoring capability and is suitable for an extended storage system for the used nuclear fuel.	Document	FCR&D	FY2012
Development of Innovative Accident Tolerant High Thermal Conductivity UO2 Fuel Pellets with a Diamond Dopant	University of Florida	$800,000	Researchers will evaluate the use of diamond nanoparticles composite material in innovative accident tolerant fuel pellets. This could significantly improve both the thermal conductivity of fuel pellets and light water reactors' efficiency safety.	Document	FCR&D	FY2012
Probabilistic Multi-Hazard Assessment of Dry Cask Structures	University of Houston	$865,000	This project aims to investigate the performance of dry cask storage systems under multiple hazard systems (earthquake, tornados, combined with aging effects) using a probabilistic multi-hazard framework. This framework will be validated based on experimental research and will provide improved models for safety and reliability of spent nuclear fuels during storage and transportation.	Document	FCR&D	FY2012
Measurement of Irradiated Pyroprocessing Samples via Laser Induced Breakdown Spectroscopy	University of Idaho	$820,000	This project aims to use advanced characterization techniques to investigate microstructural changes and the micromechanisms related to irradiation induced damage in used nuclear fuels and waste forms. This project, if successful, will result in enhanced models to predict the structural and chemical response of used fuel and waster forms during interim storage and permanent disposal.	Document	FCR&D	FY2012
Elastic/Inelastic Measurement Project	University of Kentucky	$880,523	Researchers will measure nuclear data for elastic/inelastic scattered neutrons on coolants and structural materials. The data generated, will be useful for future R&D programs that will study innovative next generation LWR and future fast systems.	Document	FCR&D	FY2012
Electrochemical Corrosion Studies for Modeling Metallic Waste Form Release Rates	University of Nevada- Las Vegas	$790,000	This project aims to use advanced electrochemical methods to investigate the corrosion related degradation of metal alloys used for housing fission products. The data obtained from this study will allow for the prediction of the long-term behavior of the metallic host phase materials over geological time-scales.	Document	FCR&D	FY2012
Thermodynamic and Microstructural Mechanisms in the Corrosion of Advanced Ceramic Tc-bearing Waste Forms and Thermophysical Properties	University of Nevada- Las Vegas	$795,000	This project team will harvest thermodynamic and microstructural data on the evolution of ceramic based waste forms. The data will be used to advance the current state-of-the-art methodology used for isolation and stabilization of fission products and improve on nuclear fuel recycling processes.	Document	FCR&D	FY2012
Development and Experimental Benchmark of Simulations to Predict Used Nuclear Fuel Cladding Temperatures during Drying and Transfer Operations	University of Nevada- Reno	$745,000	Researchers will conduct experiments to investigate and develop advanced computational models of heat transfer in post-pool-storage drying operations. This project, if successful, will result in tools that can be used to design efficient drying processes to as to ensure suitability for dry-cask systems for long-term storage and transport.	Document	FCR&D	FY2012
Better Radiation Response and Accident Tolerance of Nanostructured Ceramic Fuel Materials?	University of Tennessee	$815,000	Researchers will use novel experimental methods to investigate the links between microstructure, phase stability and damage evolution in nanostructured ceramic fuel materials. The project will study fuel materials at temperatures and irradiation conditions relevant to operation and accidental scenarios.	Document	FCR&D	FY2012
Radiation and Thermal Effects on Used Nuclear Fuel and Nuclear Waste Forms	University of Tennesssee	$770,000	This project aims to investigate the structural and chemical response of used nuclear fuel and waste forms during interim storage and permanent disposal. If successful, this project will generate models that will allow the prediction of structural evolution and hence the radiological safety and security of nuclear fuel and waste forms.	Document	FCR&D	FY2012
Seismic Performance of Dry Casks Storage for Long-Term Exposure	University of Utah	$873,319	Researchers will evaluate the mechanical performance of dry-cask storage under seismic loading for mid-term operational periods. Simulations will include scenarios for freestanding, anchored, and vaulted casks. The experimental tests will also evaluate the dynamic seismic response of freestanding and anchored dry-cask storage prototypes, providing recommendations for optimal Interim Spent Fuel Storage Installations (ISFSIs) design.	Document	FCR&D	FY2012
Validation Experiments for Spent-Fuel Dry-Cask In-Basket Convection	Utah State University	$690,000	Researchers in this project aim to conduct experiments that generate data on natural convection through a fuel assembly. The data will be used to validate the computational models being developed for nuclear safety and design.	Document	FCR&D	FY2012
Re-Branding the Nuclear Fuel Cycle	Virginia Commonwealth University	$850,000	This project will create a comprehensive framework for the evaluation of alternative fuel cycle systems that will be used to identify and analyze key elements related to long-term management of nuclear fuels , with the ultimate goal to develop a communications strategy to reach stakeholders.	Document	FCR&D	FY2012
Advanced Characterization of Molecular Interactions in TALSPEAK-like Separations Systems	Washington State University	$875,000	Researchers will use advanced characterization techniques (experimental and computational) to improve understanding of the molecular level processes/interactions during separation processes for advanced fuel cycles. The understanding of these interactions will be used to develop more robust and streamlined separation processes for advanced fuel cycles.	Document	FCR&D	FY2012
Coupling of Nuclear Waste Form Corrosion and Radionuclide Transport in Presence of Relevant Repository Sediments	Washington State University	$885,000	Researchers will conduct experiments to understand the mechanisms responsible for the corrosion of nuclear waste forms in realistic chemical environments. The data generated from these experiments will enable increased reliability of the models used to predict the waste form performance in repository environments.	Document	FCR&D	FY2012
Stationary Liquid Fuel Fast Reactor (SLFFR) Concept for TRU Burning	Purdue University	$450,000	Reasearchers will investigate a new type of molten metallic fuel reactor concept that will consume hazardous transuranic waste. The liquid fuel alloy has several advantages over solid fuel fast reactors that are used for the same purpose.	Document	MSTR	FY2012
ABR for TRU Transmutation with Breed & Burn Thorium Blanket for Improved Economics and Resource Utilization	University of California- Berkeley	$450,000	The research team will use detailed neutronic analysis for a new Advanced Burner Reactor concept with low conversion ratio. The concept will use a new core shape to improve the utilization of neutrons to perform breed and burn.	Document	MSTR	FY2012
New Materials for High Temperature Thermoelecric Power Generation	University of California, Davis	$450,000	Reasearchers will work to develop nanostructured and other new materials to support the development of higher efficiency thermoelectric devices. These devices convert thermal energy to electricity with no moving parts. The new materials will operate at higher efficiencies and over a wider temperature range than those currently available--an important quality for future nuclear-powered deep space exploration.	Document	MSTR	FY2012
Microscopic Fuel Particles Produced by Self-Assembly of Actinide Nanoclusters on Carbon Nanomaterials	University of Notre Dame	$440,000	Reasearchers will develop the mechanisms, conditions and protocols to prepare uranium-carbon nanocomposite materials to make them more flexible. This could result in the generation of wholesale electricity, providing process heat, and providing power for households.	Document	MSTR	FY2012
High Hydrogen Content Graphene Hydride Compounds & High Cross-Section Cladding Coatings for Fast Neutron Detection	University of South Carolina	$430,000	This project will exploit recent breakthroughs to grow epitaxial graphene on commercial SiC wafers. This will allow researchers to develop a new detection method for fast neutrons. In addition, it will lead to better and more compact neutron detection system.	Document	MSTR	FY2012
Reducing Actinide Production Using Inert Matrix Fuels	University of Texas- Austin	$435,000	Reasearchers will perform a neutronic analysis, a thermal-hydraulic analysis and a simulation of fuel decay heat as a functionof fuel burnup, to determine if inert matrix fuel in coventional reactors will continue to be licensable. If successful, the inert matrix fuel mixtures will reduce harmful transuranic components in the fuel discharge streams at a level comparable to a fast reactcor burner.	Document	MSTR	FY2012
An Integrated Fuel Depletion Calculator for Fuel Cycle Options Analysis	University of Texas- Austin	$395,000	Reasearchers use new analysis techniques to better predict nuclear fuel behavior. The new model will allow improved fuel cycle for a larger number of users.	Document	MSTR	FY2012
Atomic-Scale to Meso-Scale Simulation Studies of Thermal Ageing and Irradiation Effects in Fe-Cr Alloys	Boston University	$874,997	Reasearchers will develop predictive, multi-scale simulation tools for iron-chromium alloys, which are expected to be key components of advanced steels envisioned as fuel cladding and structural components for Generation IV reactors. Such modeling is necessary to avoid resource intensive and costly thermal and neutron irradiation experiments to obtain required performance data.	Document	NEAMS	FY2012
Validation Data and Model Development for Fuel Assembly Response to Seismic Loads	George Washington University	$862,435	Reasearchers will conduct experiments that will provide comprehensive data characterizing the dynamics of the fluid and the structure in Pressurized Water Reactors (PWR) fuel assemblies under seismic loads (earthquakes and loss of coolant accidents). Completion of their project will greatly benefit the safety of existing and future nuclear reactors.	Document	NEAMS	FY2012
Uncertainty Quantification and Management for Multiscale Nuclear Materials Modeling	Georgia Institute of Technology	$743,444	Reasearchers will address the question of uncertainty propogation and error estimates associated with model prediction of material behavior under irradiation. Their work will facilitate a better understanding of the connection of various unit processes to collective responses in a multiscale model chain enabling the development of high strength and high ductility materials.	Document	NEAMS	FY2012
Fuel and Core Design Options to Overcome the Heavy Metal Loading Limit and Improve Performance and Safety of Liquid Salt Cooled Reactors	Georgia Insitute of Technology	$784,689	Reasearchers will examine new options for fuel and core designs in liquid salt cooled reactors where the current standard of TRISO type fuel has limitations due to loading characteristics. The research could enable new, more feasible fuel-core-reload options that will improve safety and performance parameters.	Document	RCRD&D	FY2012
Nonlinear Ultrasonic Techniques to Monitor Radiation Damage in RPV and Internal Components	Georgia Institute of Technology	$877,000	Reasearchers will explore new nondestructive materials evaluation and monitoring techniques utilizing nonlinear ultrasonic measurements . This technique will allow researchers to assess remaining useful life of select reactor components. Breakthroughs in this area will lead to the ability to characterize radiation damage in reactor pressure vessels and other components-leading to a clearer definition of reactor safety margins.	Document	RCRD&D	FY2012
Intergral Reactor Containment Condensation Model and Experimental Validation	Oregon State University	$871,119	Reasearchers will conduct experiments to enhance the safety and efficiency of small modular reactors (SMRs). This project will assess the impact of high-pressure steam condensation on steel containment vessels to be used for SMR deigns.	Document	RCRD&D	FY2012
Investigation of Natural Circulation Instability and Transients in Passively Safe Small Modular Reactors	Purdue University	$871,100	Reasearchers will perform scaled experiments to study the thermal-hydraulic instabilities that can occur in Small Modular Reactors (SMR) which rely on natural circulation cooling during normal operation and accident conditions. Their work will not only improve our understanding of general natural circulation instability but also lead to the development of stability criteria and predictability in the operation of SMRÃs.	Document	RCRD&D	FY2012
Thermoelectric-Driven Sustainable Sensing and Actuation Systems for Fault-Tolerant Nuclear Incidents	State University of New York, Stony Brook	$599,802	Reasearchers will examine the use of solid-state thermoelectric generators to produce electricity to sense and opeate during both normal and abnormal situations. This will provide indefinite monitoring of key components during power outages or station blackouts.	Document	RCRD&D	FY2012
Experimental and CFD Studies of Coolant Flow Mixing within Scaled Models of the Upper and Lower Plenums of NGNP Gas-Cooled Reactors	Texas A&M University	$713,051	Reasearchers will model the internal coolant flow of a prismatic core very high temperature reactor (VHTR) by using large eddy simulation tools. This method will enable more accurate prediction of flow field characteristics and better evaluation of VHTR behavior under operational and accidental conditions.	Document	RCRD&D	FY2012
Demonstrating Hybrid Heat Transport and Energy Conversion System Performance Characterization Using Intelligent Control Systems	University of Idaho	$877,000	Reasearchers will demonstrate an intelligent control systems in a hybrid energy conversion loop for a next generation nuclear power plant. Hybrid energy systems are a method of optimizing the use of natural resources for energy production. Hybrid systems present an opportunity to develop domestic energy sources to improve energy security.	Document	RCRD&D	FY2012
Advanced Reactor-Intermediate Heat Exchanger (IHX) Coupling: Theoretical Modeling and Experimental Validation	University of Idaho	$869,997	Reasearchers will model the behavior of the Advanced Reactor Intermediate Heat Exchanger Chemical Process system and develop advanced control techniques that take into account abnormal scenarios. The data and information obtained will assist in the development of intelligent control systems for next generation nuclear reactor systems.	Document	RCRD&D	FY2012
Irradiation Performance of Fe-Cr Base Alloys	University of Illinois- Urbana Champaign	$876,332	Reasearchers will perform post-radiation analysis and develop tools for future development and application of the Fe-Cr class of alloys. The results of this research will lead to better modeling of performance and development of an alloy designated as the primary choice for reactor fuel cladding and structural applications in advanced systems.	Document	RCRD&D	FY2012
Accelerated Irradiations for High Dose Microstructures in Fast Reactor Alloys	University of Michigan	$831,876	Reasearchers will determine the extent to which high dose rate irradiation can be used as an irradiation damage tool to understand microstructure evolution at high doses and temperatures relevant to advanced fast reactors. The project will provide fundamental understanding of the effectiveness of this process and thus of microstructure development in irradiated materials.	Document	RCRD&D	FY2012
Mitigating IASCC of Reactor Core Internals by Post-Irradiation Annealing Advanced Mitigation Strategies	University of Michigan	$876,985	Reasearchers will determine the optimum Post-irradiation annealing (PIA)-driven mitigation strategy to extend the potential lifetime of light water reactors. Samples that have already been irradiated in a light water reactor will be used to test PIA treatments to understand IASCC initiation and propoagation, annealing kinetics, the role of microstructure features in irradation hardening and localized deformation, and the optimum mitigation strategy based on PIA.	Document	RCRD&D	FY2012
Experimentally Validated Numerical Models for Effects of Non-Isothermal Turbulent Mixing on Wall Stresses in High Temperature Reactors	University of Pittsburgh	$876,422	Reasearchers will develop a comprehensive experimentally validated computational framework for the turbulent mixing in the lower plenum of a very high temperature reactor (VHTR). Through CFD modeling and experimental validation, the results from this project will lay the groundwork for future stress analysis, failure and fatigue studies, and uncertainty quantification for the VHTR system.	Document	RCRD&D	FY2012
Role of Defects in Swelling and Creep of Irradiated SiC	University of Wisconsin- Madison	$875,350	Reasearchers will study mechanisms controlling both radiation swelling and radiation creep in silicon carbide. These two effects are crucial to understanding the issues associated with the brittle silicon carbide composite. Success in this project will ground progress in the adoption of silicon carbide for reactor solutions, particularly as fuel cladding.	Document	RCRD&D	FY2012
Advanced Supercritical Carbon Dioxide Brayton Cycle Development	University of Wisconsin, Madison	$877,000	Reasearchers will investigate the benefits of utilizing advanced Brayton cycles with supercritical carbon dioxide in new reactor systems and components. Benefits of this research include improvement of analysis and performance of components currently utilizing these cycles as well as the potential for a large scale advanced CO2 power system.	Document	RCRD&D	FY2012
Mechanical Behavior of UO2 at Sub-grain Length Scales: Quantification of Elastic, Plastic and Creep Properties via Microscale Testing	Arizona State University	$800,000	Reasearchers will develop techniques to measure properties at sub-grain scales using depleted Uranium Oxide samples. The project will provide a framework to measure sub-grain scale mechanical properties, as well as provide experimental data to improve the understanding of advanced oxide fuels.	Document	FCR&D	FY2013
The Impacts of Pore-Scale Physical and Chemical Heterogeneities on the Transport of Radionuclide-Carrying Colloids	Colorado School of Mines	$800,000	Reasearchers will identify the dominant transport mechanisms to develop models that predict radionuclide distribution in porous materials. Experimental and computational models will be created that couple pore-scale geometric and interfacial structures. Simulators such as these are a necessary step towards fully predictive models for field-scale applications in the future.	Document	FCR&D	FY2013
Recovery of Uranium from Seawater: Polymer-Supported Aminophosphinates as Selective Extractants	Hunter College, CUNY	$399,999	Reasearchers will prepare a polymer-supported extractant for the recovery of uranium from seawater. The project will focus on primary amines that could provide a 3-fold increase in uranium capture capacity than current methods.	Document	FCR&D	FY2013
In-pile Thermal Conductivity Characterization with Single-laser Heating/Time Resolved Raman	Iowa State University	$800,000	Reasearchers will develop a time-resolved Raman-based thermal conductivity measurement system to improve remote in-pile thermal conductivity measurement. These measurements will provide new insights into the behavior of materials exposed to extreme radiation and temperature environments. Understanding the behavior of materials at the microstructural level will support optimized fuel designs.	Document	FCR&D	FY2013
Organic Speciation and Interactions in ALSEP - One Step Partitioning Process of Minor Actinides, Lanthanides, and Fission Products	Oregon State University	$600,000	Reasearchers will investigate the Actinide-Lanthanide Separation (ALSEP) process organic phase prior to aqueous phase separation and after aqueous separation phases of bare and metal-loaded acids. Quantifying these effects can be used to determine how an engineering scale process will perform and generate an accurate chemical model for the system.	Document	FCR&D	FY2013
Glass Composition and Solution Speciation Effects on Stage III Dissolution	Pennsylvania State University	$700,000	Reasearchers will study the chemical and structural triggers of long-term vitrified nuclear waste form behavior. They will study a range of waste glass compositions in corrosive environments. The study will improve understanding of the long-term residual rate and may provide new options for environmental control of glass dissolution rates.	Document	FCR&D	FY2013
Correlating Thermal, Mechanical, and Electrical Coupling Based Multiphysics Behavior of Nuclear Materials Through In-Situ Measurements	Purdue University	$800,000	Reasearchers will use in-situ experimental techniques to monitor the influence of extreme conditions on fuel cladding. The project will establish an in-situ experimental setup that can predict change in thermal properties and their correlation with mechanical properties and correlate such changes to changes in microstructural and chemical features.	Document	FCR&D	FY2013
Creation of a Geant4 Muon Tomography Package for Imaging of Nuclear Fuel in Dry Cask Storage	Purdue University	$440,000	Reasearchers will develop a simulation and analysis package to aid in the non-destructive assessment of sealed used nuclear fuel dry casks using cosmic ray muons. Cosmic ray muon tomography allows for non-destructive assessment that can independently verify and identify weapons grade material sealed within dense dry casks.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Two-stage Fast Reactor Fuel Cycle Options for Optimum Resource Utilization and Waste Management	Purdue University	$400,000	Reasearchers will evaluate the two different two-stage fast reactor fuel cycle options that will offer efficient use of uranium resources and the ability to burn actinides and long-live fission products. Evaluation of these fast fuel cycle options will serve as a useful complement to the options currently being considered in the Fuel Cycle Options Campaign.	Document	FCR&D	FY2013
Mixed Metal Phosphonate-Phosphate Resins for Separation of Lanthanides from Actinides	Texas A&M University	$650,000	Reasearchers will use ion exchangers to cleanly separate lanthanides and curium from reusable actinides. The study will assist in the development of an inexpensive, simple way in which to separate lanthanides from actinides found in used nuclear fuel rods and to recover a large portion of the usable fuel.	Document	FCR&D	FY2013
Safeguards in Pyroprocessing: an Integrated Model Development and Measurement Data Analysis	The Ohio State University	$626,151	Reasearchers will develop a comprehensive and effective safeguards approach for a pyroprocessing facility to support safeguards for future fuel cycles in the United States. The new approach and design will focus directly on the special nuclear materials in the electrorefiner where actinides are separated from fission products through electrochemical process.	Document	FCR&D	FY2013
Using Ionic Liquids for the Development of Renewable Biopolymer-Based Adsorbents for the Extraction of Uranium from Seawater and Testing Under Marine Conditions	University of Alabama	$400,000	Reasearchers will explore the fundamental engineering parameters for a renewable high-performance adsorbent for the extraction of uranium from sweater based on a recently proven ionic liquid (IL)-chitin platform. The project will use the platform to develop a versatile, modifiable adsorbent and characterize its performance and degradation in marine conditions.	Document	FCR&D	FY2013
Developing Ultra-Small Scale Mechanical Testing Methods and Microstructural Investigation Procedures for Irradiated Materials.	University of California, Berkeley	$800,000	Reasearchers will develop new small-scale mechanical testing techniques to allow for the estimation or direct measurement of bulk properties. The combined experiments and modeling will significantly enhance the statistics and information that can be obtained on small radioactive archived samples, as well as new ion beam irradiated specimens.	Document	FCR&D	FY2013
Improved Delayed-Neutron Spectroscopy Using Trapped Ions	University of California, Berkeley	$400,000	Reasearchers will develop innovative spectroscopy techniques to measure the decay of fission fragments. The resulting data from these new techniques will be used to better understand reactor kinetics under accident conditions and failure scenarios.	Document	FCR&D	FY2013
Thermally and Chemically Responsive Nanoporous Materials for Efficient Capture of Fission Product Gases	University of California, Davis	$750,000	Reasearchers will create new nanoporous materials that will be highly effective at capturing fission product gases. These materials would be relevant to both reactor fuels applications and reprocessing operations. Tests will be performed in carbon based and nitride based nanostructures, with the most promising materials from the modeling perspective undergoing further testing.	Document	FCR&D	FY2013
Multiphase Nanocrystalline Ceramic Concept for Nuclear Fuel	University of California, Irvine	$800,000	Researchers will study the use of nanoparticles and nanostructured ceramics to create new materials that can extend the service life and increase efficiency for nuclear fuel. Multiphase nanocrystalline ceramics will be used to design simulated nuclear fuel that can provide added plasticity, better radiation tolerance and improved thermal conductivity.	Document	FCR&D	FY2013
Development of Novel Porous Sorbents for Extraction of Uranium from Seawater	University of Chicago	$400,000	Reasearchers will develop a highly porous sorbent for the extraction of uranium from seawater. Previous research has established sorbent performance. This project will use past foundational studies to design and investigate a new nanocomposites that will be processed into tacks or braids for field tests in seawater tests. The technology may also be used for other metals.	Document	FCR&D	FY2013
Microwave Readout Techniques for Very Large Arrays of Nuclear Sensors	University of Colorado, Boulder	$799,937	Reasearchers will develop a powerful readout technique based on microwave transmission and reflection. The technique will enable very large arrays of diverse sensor types for nuclear materials quantification and tracking. It will provide more accurate data on material composition and quantity.	Document	FCR&D	FY2013
BiI3 Gamma-Ray Spectrometers for Reliable Room-Temperature Nuclear Materials Safeguarding	University of Florida	$799,999	Reasearchers will develop gamma-ray spectrometers based on BiI3 single crystals for MPACT applications such as burnup validation quantification, improved assay of plutonium, determination of uranium enrichment and overall monitoring spent fuel within the fuel cycle. The project will improve energy resolution, efficiency and environmental performance with this new gamma-ray detector.	Document	FCR&D	FY2013
Innovative Coating of Nanostructured Vanadium Carbide on the F/M Cladding Tube Inner Surface for Mitigating the Fuel Cladding Chemical Interactions	University of Florida	$760,276	Researchers will develop barrier coatings on the inner surface of fuel cladding tubes to improve performance of materials at elevated temperatures and high neutron exposures in fast reactors. The project will develop and test a low temperature coating process of nanostructured vanadium carbide that will provide a benchmark for use in future studies.	Document	FCR&D	FY2013
Doubling the Life of Concrete Structures	University of Idaho	$800,000	Reasearchers will use nanoscale techniques to develop methods for doubling the service life of concrete structures. They will study the effect of temperature load and temperature cycling (freezing and thawing) on the durability of concrete with nanoscale viscosity modifiers. The project will benefit from non-destructive evaluation of concrete performance through electrochemical techniques.	Document	FCR&D	FY2013
Off-Gas Treatment: Evaluation of Nano-structured Sorbents for Selective Removal of Contaminants	University of Idaho	$785,910	Reasearchers will evaluate nanostructured sorbent materials for their effectiveness in removing and immobilizing radionuclides for the off-gas treatment from used nuclear fuel recycling operations. The project aims at achieving near-zero emissions of radionuclides by capturing them from the off-gas of recycling operations, allowing for the development of advanced fuel cycles.	Document	FCR&D	FY2013
Innovative Elution Processes for Recovering Uranium and Transition Metals from Amidoxime-Based Sorbents	University of Idaho	$399,864	Reasearchers will develop a new two-step elution process to achieve total recovery of uranium and effective recycling of the sorbent. The extraction process would selectively remove uranium from the sorbent with little or no damage. The process would then remove transition metals and regenerate the sorbent for repeated use, making uranium extraction from seawater economically viable.	Document	FCR&D	FY2013
Performance of a Steel/Oxide Composite Waste Form for Combined Waste Streams from Advanced Electrochemical Processes over Geologic Time Scales	University of Illinois at Chicago	$700,000	Reasearchers will develop and validate a mechanistically-based corrosion model for cermet-type waste forms, creating a testing protocol and modeling approach for predicting long-term performance. The study will apply novel electrochemical testing and modeling methods to the behavior of metal/oxide phase boundaries to evaluate waste form performance.	Document	FCR&D	FY2013
Enhancement of the Extraction of Uranium from Seawater	University of Maryland, College Park	$400,000	Reasearchers will develop and optimize novel adsorbents for uranium recovery from seawater. The team will use radiation-induced grafting of organic phosphates onto polymers. The experiments will use ocean water, with mechanistic analysis, to provide a solid basis for large-scale demonstration of the performance of the new adsorbents in ocean environments.	Document	FCR&D	FY2013
Improving the Understanding of the Coupled Thermal-Mechanical-Hydrologic Behavior of Consolidating Granular Salt	University of New Mexico	$800,000	Reasearchers will increase the understanding of granular salt seal materials for shafts, drifts and boreholes. By coupling thermal, mechanical and hydrological responses, the study will result in greater confidence in granular salt consolidation as a principal strategy for closure and isolation of long-term waste repositories.	Document	FCR&D	FY2013
Fission Fragment Yield Data in Support of Advanced Reactor Technology	University of New Mexico	$399,816	Reasearchers will produce a highly accurate data set for thermal fission. These precision data are necessary for high-accuracy simulations of nuclear criticality, transmutation rates, radiation effects and heating as well as for nuclear fuel, material accounting and identification needs.	Document	FCR&D	FY2013
Molecular dynamics-based simulations of bulk/interfacial structures and diffusion behaviors in nuclear waste glasses	University of North Texas	$700,000	Reasearchers will generate accurate atomic structural models for use in Monte Carlo simulations of the dissolution of nuclear waste glasses. Large-scale molecular dynamics-based computer simulations will be used to investigate self-diffusion behaviors, interfacial structure, and other structures formed during dissolution of these glasses.	Document	FCR&D	FY2013
U3Si2 Fabrication and Testing for Implementation into the BISON Fuel Performance Code	University of South Carolina	$800,000	Reasearchers will fabricate, test and model a high uranium density, advanced nuclear fuel that operates at a much lower temperature and stores less energy. The work will deliver key research data on creep and grain growth, improving economics, through possible power uprates, and advancing accident tolerant fuels research.	Document	FCR&D	FY2013
Structural Health Monitoring of Nuclear Spent Fuel Storage Facilities	University of South Carolina	$738,618	Reasearchers will develop a nuclear structural health monitoring system based on a sensing technology that monitors material degradation and aging for dry cask storage systems. The low-cost, low-profile sensors will perform on-demand monitoring of the structural integrity of individual components as well as the entire system.	Document	FCR&D	FY2013
ORIGEN-based Nuclear Fuel Depletion Module for Fuel Cycle Assessment	University of Tennessee at Knoxville	$755,181	Reasearchers will develop a flexible reactor analysis module for the CYCLUS fuel cycle simulator based on established tools for reactor fuel depletion and decay. They will use ORIGEN, a mature and experimentally validated code, affording greater flexibility and allowing for accurate evaluations of impacts of both present and future fuel cycle options.	Document	FCR&D	FY2013
Cost and System Analysis of Innovative Fuel Resources Concepts	University of Texas at Austin	$295,960	_This project will develop and test braided polymer fiber adsorbents that surpass the sorption capacity, selectivity and durability of the best existing technology to recover uranium from seawater.	Document	FCR&D	FY2013
Risk Assessment of Structural Integrity of Transportation Casks	University of Utah	$789,296	Reasearchers will assess the loss of structural integrity of transportation casks and fuel cladding after extended storage. This risk assessment will conduct experimental tests and simulations to evaluate the structural performance of fuel, fuel assemblies and cask components when subjected to vibration and impact loads during transport.	Document	FCR&D	FY2013
Market-Based and System-Wide Fuel Cycle Optimization	University of Wisconsin, Madison	$612,731	Reasearchers will create market and economic optimizers to improve calculations for the CYCLUS fuel cycle simulator. The team will leverage existing optimization software frameworks within the simulator to resolve top level policy questions. The optimizations will allow CYCLUS to move beyond static material compositions, providing a holistic view of the fuel cycle system.		FCR&D	FY2013
Optical Fiber Based System for Multiple Thermophysical Properties for Glove Box, Hot Cell and In-Pile Applications	Utah State University	$799,975	Reasearchers will use a small pressure vessel to develop a robust technique for the measurement of multiple thermophysical properties at very high temperatures. The technique will lead to a system design moving toward the eventual measurement of irradiated fuels in a glovebox and/or hot cell with all sensors and electronics outside of the glovebox and/or hot cell.	Document	FCR&D	FY2013
Development of a Nano-Modified Concrete for Next Generation of Storage Systems	Vanderbilt University	$796,268	Reasearchers will use nano-sized and nano-structured particles based on enhanced reactivity to develop a superior concrete for the long-term storage of used nuclear fuel. The project will use state-of-the-art experimental chemical and mechanical characterizations and computation analysis to assess the performance of nano-modified concretes.	Document	FCR&D	FY2013
Development of Fuel Cycle Data Packages for Thorium Fuel Cycle Options	Vanderbilt University	$797,995	Reasearchers will develop six fuel cycle data packages for multi-stage, thermal fuel cycles which incorporate thorium. These new fuel cycle data packages will provide the opportunity to examine fuel cycle options beyond those which have traditionally been considered. A thorium fuel cycle database will also be assembled as a basis for thorium literature for future evaluations of the thorium fuel cycle.	Document	FCR&D	FY2013
Enhanced Shielding Performance of HLW Storage Packages via Multi-Component Coatings	Virginia Polytechnic Institute and State University	$796,947	Reasearchers will develop a multi-layer composite that will enhance long-term storage and facilitate safe transport of storage packages. This novel multi-layer, multi-component coating would create an outer shield material that is resistant to the corrosion, radiation, diffusion and thermal cycling processes that affect fuel packages during long term storage.	Document	FCR&D	FY2013
Managing Zirconium Chemistry and Phase Compatibility in Combined Process Separations for Minor Actinide Partitioning	Washington State University	$700,000	Reasearchers will address unique challenges for combining TRUEX and TALSPEAK processes for partitioning of lanthanides and minor actinides. The project will develop improved information on the thermodynamics of fission product zirconium and develop a framework for an organic phase solvation model. Combined process development could streamline separations processes.	Document	FCR&D	FY2013
Advances in the Recovery of Uranium from Seawater: Studies Under Real Ocean Conditions	Woods Hole Oceanographic Institution	$398,882	Reasearchers will provide infrastructure and expertise for marine testing of currently available adsorbents in real ocean conditions. The team will move adsorbent research from the lab to field testing in order to quantify sorptive properties and uranium uptake. The project will provide valuable field data that will show the potential of large scale applications of these technologies.	Document	FCR&D	FY2013
NEUP Project 20-19172: Irradiation of Sensors and Adhesive Couplants for Application in LWR Primary Loop Piping and Components		$497,881	Reasearchers paln to attach ultrasonic transducers to substrates using various adhesive couplants that will be irradiated at elevated temperature to simulate LWR primary loop conditions at the PULSTAR reactor at North Carolina State University. Ultrasonic data will be taken in-situ. Subsequently, the sensors and couplant interfaces will be characterized using the LAMDA facility at ORNL. The results will be used to benefit a parallel EPRI project on online monitoring of cracks in LWR primary loop piping._	Document	R&D NSUF	FY2013
NEUP Project 20-19404: Extension of MSTDB to Provide a High-Quality, Validated Thermochemical Database for Predicting/Simulating Corrosion in Molten Salt Reactor SystemsUniversity of South Carolina		$600,000	Reasearchers will generate a validated, consistent database of initial fuel compositions and potential corrossion products of fluoride and chloride salts, allowing for important phenomena predictions in molten salt reactors to guide confident decisions. The database will be integral to the currently being developed Molten Salt Thermochemical Database (MSTDB), structured to allow use by commercial and open source codes._	Document	NEAMS	FY2013
Lower Length Scale Characterization and Validation of Formation and Stability of Helium Bubbles in Nano-structured Ferritic Alloys under Irradiation	Clemson University	$399,870	Reasearchers will provide a fundamental knowledge about the formation and stability of ultra-fine helium bubbles within 14YWT after neutron/ion irradiation for further design of new advanced structural materials with a characteristic high density nanoparticles feature which can increase the mechanical strength, hardness, irradiation resistance and the operational temperature range of materials.	Document	NEAMS	FY2013
Three-Dimensional Fuel Pin Model Validation by Prediction of Hydrogen Distribution in Cladding and Comparison with Experiment	Pennsylvania State University	$800,000	Reasearchers will validate important three-dimensional aspects of the fuel pin modeling by using specialized numerical modeling techniques coupled with laboratory experiments to validate existing models for predicting fuel performance in light water reactors.	Document	NEAMS	FY2013
Collocation-Based Surrogate Models for Uncertainty Quantification and Validation of Coupled, Multiphysics Fuel Performance Simulation Tools	University of Michigan	$596,835	Reasearchers will provide the necessary high fidelity, coupled, multiphysics fuel performance simulator for computational modeling and develop surrogates which will accelerate and focus the validation of the coupled codes. This will be achieved by utilizing the high fidelity coupled fuel performance, thermal-hydraulics and neutronics codes BISON/STAR-CCM+/MPACT and an innovative collocation-based surrogate methodology.	Document	NEAMS	FY2013
Multi-Resolution In-Situ Testing and Mutliscale Simulation for Creep Damage Fatigue Damage Analysis of Alloy 617	Arizona State University	$800,000	This project will develop novel testing and experimentally validated prediction methodologies for micro-structural damage mechanisms of structural materials for advanced reactor systems. The investigations will focus on the characterization and testing of specific metal alloys, but the proposed testing and life-prediction methodologies are applicable to other structural materials as well.	Document	RCRD&D	FY2013
Novel High Temperature and Radiation Resistant Infrared Glasses and Optical Fibers for Sensing in Advanced Small Modular Reactors	Clemson University	$800,000	Clemson University, in partnership with the Iowa State University and the Pacific Northwest National Laboratory, will develop novel optical materials with improved heat and radiation exposure resistance in order to enable in-vessel fiber optic sensing for advanced Small Modular Reactors.	Document	RCRD&D	FY2013
Validation Data Acquisition in HTTF during PCC Events	George Washington University	$800,000	Reasearchers at the George Washington University and Oregon State University will collaborate with NASA Langley Research Center to measure flow velocities in a high temperature test facility. This work supports the development of very-high temperature reactors with passive safety systems.	Document	RCRD&D	FY2013
Advanced High Temperature Inspection Capabilities for Small Modular Reactors	Iowa State University	$790,822	The objective of this project is to develop non-destructive evaluation techniques for advanced small modular reactors. The research will provide key enabling inspection technologies needed to support the design and the reactor component performance validation process for advanced small modular reactors.	Document	RCRD&D	FY2013
Experimental and Computational Investigations of Plenum-to-Plenum Heat Transfer under Natural Circulation in a Prismatic Very High Temperature Reactor	Missouri University of Science and Technology	$799,999	Reasearchers will perform experimental and computational investigations to study heat transfer and natural circulation phenomena in very-high temperature reactors. The study will assist in the ability to predict and analyze passive safety systems.	Document	RCRD&D	FY2013
New Mechanistic Models of Creep-Fatigue Crack Growth Interactions for Advanced High Temperature Reactor Components	Oregon State University	$790,790	Reasearchers will create and validate a robust, multi-scale, numerical model to predict material degradation in nickel-based reactor alloys. If successful, this project will provide better numerical tools for reactor designers and greatly improve their capability to design against material failures for reactor alloys in the long term.	Document	RCRD&D	FY2013
Self-Powered Wireless Dual-mode Langasite Sensor for Pressure/Temperature Monitoring of Nuclear Reactors	State University of New York, Stony Brook	$800,000	This research will develop a novel self-powered wireless hybrid sensor that can accurately monitor both pressure and temperature using a single device without requiring external electricity, even in extreme harsh environments.	Document	RCRD&D	FY2013
Compact Heat Exchanger Design and Testing for Advanced Nuclear Reactors and Advanced Power Cycles	The Ohio State University	$800,000	The goal of this project is to investigate optimal heat exchanger designs for advanced reactors. The research will study the optimization of printed circuit heat exchangers for specific fluids under a variety of conditions as well as perform numerical modeling. Experiments will focus on thermal performance and heat stress during extreme conditions.	Document	RCRD&D	FY2013
Fundamental Understanding of Creep-Fatigue Interactions in 9Cr-1MoV Steel Welds	The Ohio State University	$798,000	This project will advance the state of knowledge and fundamental understanding of deforming materials and welds under loading conditions. Specifically, new integrated testing procedures will be evaluated and applied for conditions that are most detrimental to material stability leading to improved predictions of life expectancy for reactor steels and welds.	Document	RCRD&D	FY2013
Advanced Mechanistic 3D Spatial Modeling and Analysis Methods to Accurately Represent Nuclear Facility External Event Scenarios	The Ohio State University	$800,000	Reasearchers will develop three-dimensional characterization uncertainty analysis for commercial power plants. The project will involve combining experts from the fields of seismic structural modeling and advanced methods of risk assessment. This effort is expected to result in next generation tools that can be used for assessment of seismic risks.	Document	RCRD&D	FY2013
Tritium Mitigation/Control for Advanced Reactor Systems	The Ohio State University	$400,000	Reasearchers will develop a fluoride salt cooled high-temperature reactor featuring a specialized system to control tritium production. If successful, this will result in a significant reduction in size and cost in comparison to other reactor designs.	Document	RCRD&D	FY2013
A Pebble-Bed Breed and Burn Reactor	University of California, Berkeley	$400,000	Reasearchers will assess the feasibility of designing a type of metal cooled reactor able to establish and maintain operation when fueled with depleted uranium. If successful, this reactor will offer at least a 30-fold increase in the uranium ore utilization versus that achieved in contemporary light water reactors without the need for fuel reprocessing and recycling.	Document	RCRD&D	FY2013
Investigation of Thermal Aging Effects on the Evolution of Microstructure and Mechanical Properties of Cast Duplex Stainless Steels	University of Maryland, College Park	$799,966	This research will provide a better understanding of the microstructural evolution and simultaneous change in mechanical response during aging. The results of the research will provide data that can be used to estimate degraded mechanical properties for an 80-year service life of light water reactors.	Document	RCRD&D	FY2013
Model validation using CFD-grade experimental database for NGNP Reactor Cavity Cooling Systems with water and air	University of Michigan	$799,348	Reasearchers will use advanced innovative instrumentation to build a high-resolution experimental database and to use the novel experimental data to assess and further develop the predictive capabilities of computer codes for thermal hydraulics and computational fluid dynamics. The improved models developed by this project will also have the direct benefit of improving the predictive capability of the passive systems of third generation light water reactors and small modular reactor systems.	Document	RCRD&D	FY2013
Long-Term Prediction of Emissivity of Structural Material for High Temperature Reactor Systems	University of Missouri	$799,117	Reasearchers will study specific types of emissivity driven cooling from a variety of materials that are relevant to nuclear reactors. The research will provide a basis for numerical modeling to support reactor development.	Document	RCRD&D	FY2013
Advanced I&C for Fault-Tolerant Supervisory Control of Small Modular Reactors	University of Pittsburgh	$800,000	The purpose of this research is to develop advanced instrumentation and control techniques for supervisory control of advanced small modular reactors. This research supports the operational goals of small modular reactor concepts through the development of improved oversight and surveillance techniques.	Document	RCRD&D	FY2013
Corrosion of Structural Materials for Advanced Supercritical Carbon-Dioxide Brayton Cycle	University of Wisconsin-Madison	$798,672	Reasearchers will study a variety of materials for corrosion resistance under conditions that improve power conversion. In addition to studying the corrosion resistance of the materials, researchers will study the effect of additives to mitigate corrosion. Development of corrosion theories and modeling aimed at prediction of long-term corrosion will be the underlying theme throughout the project.	Document	RCRD&D	FY2013
Component and Technology Development for Advanced Liquid Metal Reactors	University of Wisconsin-Madison	$798,920	In support of liquid metal cooled reactors, the University of Wisconsin, Madison will evaluate advanced alloys and ceramics that come in contact with liquid metals. Additionally, a robust oxygen sensor and for use in liquid metals will be developed in order to better evaluate corrosion profiles in support of diagnostic testing.	Document	RCRD&D	FY2013
A New Paradigm for Understanding Multi-phase Ceramic Waste Form Performance	Clemson University	$800,000	Researchers will use advanced characterization tools to develop 3-D microstructural data that can be incorporated into computer-based simulations in order to predict the performance of waste forms. Materials system modeling will incorporate elemental release and the interconnected microstructural network of phases to better understand performance and degradation, which will accelerate waste form acceptance in repository settings.	Document	FCR&D	FY2014
Controlling Hexavalent Americium: A Centerpiece to a Compact Nuclear Fuel Cycle	Colorado School of Mines	$800,000	Researchers will develop and exploit the fundamental chemistry of Americium to enable an industrially viable means to co-recover the major and minor actinide elements from used nuclear fuel. The results would be a significant step forward in the development of aqueous separations approaches designed to recover the U-Am actinides based on the availability of the hexavalent oxidation state.	Document	FCR&D	FY2014
Zeolite Membranes for Krypton/Xenon Separation from Spent Nuclear Fuel Reprocessing Off-Gas	Georgia Institute of Technology	$400,000	Researchers will develop a high-performance, lower-cost zeolitic membrane process for Kr/Xe separations during spent nuclear fuel processing. Current separation methods are not considered economical and a membrane process would have relatively lower cost, equipment size, and ambient operating temperature. The process would form a sound basis for further development of this transformative separation technology for the nuclear fuel cycle.	Document	FCR&D	FY2014
Optimizing Polymer-Grafted Amidoxime-based Adsorbents for Uranium Uptake from Seawater	Georgia Institute of Technology	$399,999	Researchers will work to increase the adsorbent capacity and selectivity toward uranium by optimizing the adsorbent morphology, synthesis variables, and conditioning parameters and by investigating the rate-limiting variables through transport and reaction modeling. A novel adsorption/partition concept that has the potential to substantially increase the adsorbent capacity will be tested, making uranium from seawater extraction more economically viable.	Document	FCR&D	FY2014
Extraction of Uranium from Seawater: Design and Testing of a Symbiotic System	Massachusetts Institute of Technology	$400,000	Researchers will develop a seawater uranium extraction system that will work symbiotically with an offshore windmill by utilizing the structure, mooring and power of the windmill, while increasing the energy harvested by the installation. Uranium will be extracted by an adsorbent polymer belt, which will be cycled through the seawater and an elution plant located at the base of the windmill tower. Increasing the frequency of harvesting could overcome current economic barriers to seawater uranium extraction.	Document	FCR&D	FY2014
Imaging a Dry Storage Cask with Cosmic Ray Muons	Oregon State University	$799,871	Researchers will develop an imaging system to monitor the content of a dry storage cask with cosmic ray muons. A very large amount of plutonium under nuclear safeguards is contained in used fuel assemblies stored in dry storage casks. Muon imaging will allow a cost effective and reliable way to evaluate dry storage cask content and integrity before transport.	Document	FCR&D	FY2014
Apatite and sodalite based glass-bonded waste forms for immobilization of 129I and mixed halide radioactive wastes	Rutgers University	$800,000	Researchers will develop advanced and chemically durable waste forms for immobilizing 129I (aqueous based reprocessing of fuel) and mixed-halide wastes (molten-salt processing of fuel) by low temperature synthesis. Halide-containing sodalite and calcium phosphate-based apatite minerals will be synthesized, consolidated and tested for chemical durability. The project will provide needed baseline data for the development of advanced waste forms for immobilization of iodine and mixed-halide wastes.	Document	FCR&D	FY2014
Sorption Modeling and Verification for Off-Gas Treatment	Syracuse University	$350,000	Researchers will develop modeling tools supported by experiments for off-gas capture from future nuclear-fuel recycling facilities. Target species include tritium, iodine, krypton, and xenon. The models are intended to provide path forward recommendations to develop off-gas treatment adsorption processes. The project will contribute to the evaluation of options for environmentally acceptable recycle systems.	Document	FCR&D	FY2014
Development of high performance ODS alloys	Texas A&M University	$800,000	Researchers will study swelling, radiation hardening and changes in mechanical properties of ODS alloys to develop two sets of advanced ODS alloys. Two sets of first-round candidate alloys that have already undergone extensive development and testing will evaluate irradiation performance. The study will meet the need for high strength, radiation-tolerant cladding and core components that have enhanced resistance to void swelling.	Document	FCR&D	FY2014
Rare Earth Electrochemical Property Measurements and Phase Diagram Development in a Complex Molten Salt Mixture for Molten Salt Recycle	The Ohio State University	$800,000	Researchers will investigate rare earth (RE) properties in complex molten salt mixtures. In a molten salt recycle approach, the RE drawdown by electrolysis is a key step in which REs are separated from salt containing other fission products. Investigation of RE electrolysis must consider the electrochemical properties of the REs. We propose to conduct studies of detailed experiments and corresponding models to provide the physical properties and phase diagrams required to predict the performance of RE drawdown for processing complex molten salts.	Document	FCR&D	FY2014
Studies of Lanthanide Transport in Metallic Nuclear Fuels	The Ohio State University	$800,000	Researchers will study the redistribution of lanthanides and migration of lanthanides to the fuel surface. The mechanisms of lanthanide transport in metallic fuel based on the novel discovery of a Ôliquid-likeÕ transport mechanism will be studied analytically and experimentally. The project will develop a fundamental understanding of lanthanide fission product migration and redistribution in advanced metallic nuclear fuels, and theory and data to mitigate fuel-cladding chemical interactions.	Document	FCR&D	FY2014
Computational and Experimental Studies of Microstructure-Scale Porosity in Metallic Fuels for Improved Gas Swelling Behavior	University of Arkansas	$796,823	Researchers will study the microstructure of metallic uranium alloy fuels, and their resistance to densification, to minimize in-pile irradiation swelling through bimodal pore size distribution. The project will develop a predictive approach to design metallic fuel microstructures for optimal swelling resistance and fission gas retention.	Document	FCR&D	FY2014
Improved Hybrid Modeling of Spent Fuel Storage Facilities	University of California, Berkeley	$645,393	Researchers will develop a variance reduction method for computational transport that will improve the ability to design and operate monitoring systems for interim used fuel installations through enhanced modeling and simulation. This new tool will demonstrate that modeling calculations can be done more accurately in less time than with current tools and will perform studies characterizing how changes in material, cask configurations, and number of casks could impact monitoring systems.	Document	FCR&D	FY2014
Selective ligands for uranyl via combinatorial peptoid libraries: A synthetic, structural, thermodynamic and computational study	University of California, Berkeley	$400,000	Researchers will study how donor ligands bind to the uranyl ion, UO22+, with the longer-term goal of using this information to tackle selective recognition of uranyl in aqueous solution. The study will impact underlying approaches to controlling the behavior of uranium in these systems. The actinide separation technology could be used in several areas including uranium extraction from seawater, nuclear waste remediation and nuclear materials.	Document	FCR&D	FY2014
Combining Experiments and Simulations of Extraction Kinetics and Thermodynamics in Advanced Separation Processes for Used Nuclear Fuel	University of California, Irvine	$799,938	Researchers will study how the kinetics and thermodynamics of metal ion extraction in advanced separation processes for used nuclear fuel can be described by molecular dynamic (MD) simulations and how the simulations can be validated by experimental data. The project would have broad impacts on several separations processes including advanced TALSPEAK, ALSEP and GANEX by increasing the confidence and accuracy of computer modeling of metal ion extraction._	Document	FCR&D	FY2014
Effect of Metallic Li on the Behavior of Metals in Molten Salts	University of Nevada, Reno	$458,250	Researchers will identify the effect of metallic lithium on materials that are used in molten salt recycling. The study will try to understand how the presence of Li(0) in molten salts affects the degradation of alloys. Studying these changes will help accurately predict container material behavior and longevity.	Document	FCR&D	FY2014
Assessment of Corrosion Resistance of Promising Accident Tolerant Fuel Cladding under Reactor Conditions	University of Notre Dame	$800,000	Researchers will assess the corrosion behavior of accident tolerant fuel candidate iron-based alloys under normal LWR operating conditions consisting of high temperature, relevant water chemistry and irradiation. The assessment will produce data about possible irradiation-accelerated corrosion rates of iron-based alloys, and the mechanisms by which such corrosion rates are accelerated. The project will advance the selection of appropriate replacements for Zircaloy cladding.	Document	FCR&D	FY2014
Functionalized Porous Organic Polymers as Uranium Nano-Traps for Efficient Recovery of Uranium from Seawaterr	University of South Florida	$399,000	Researchers will develop functionalized porous organic polymers, or Ônano-trapsÕ for extraction of uranium from seawater. This technique allows for increased surface area and custom-designed pore size and chemistry to fit specific parameters. The adsorbent materials have high efficiency and effectiveness for uranium recovery from seawater, providing a potential supply for nuclear fuel.	Document	FCR&D	FY2014
Enhanced Accident-Tolerant Fuel Performance and Reliability for Aggressive iPWR/SMR Operation	University of Tennessee	$799,967	To develop a process that evaluates operational and safety performance of reactor-and-fuel combinations by integrating whole-core 3D neutronics with MOOSE/BISON fuel performance assessments via explicit time and space dependent fuel rod operational power histories. The project will be valuable in analyzing and evaluating accident tolerant fuel concepts and furthering the understanding of reactor physics and fuel performance aspects of key accident tolerant fuel concepts.	Document	FCR&D	FY2014
Nuclear Technology R&D Strategies in an Era of Energy Price Uncertainty	University of Texas, Austin	$799,112	Researchers will identify nuclear technology options that are competitive over a wide range of plausible future business environments. No single nuclear technology or business practice will be the best choice across all or even most future conditions. The study will focus on hybrid nuclear-fossil technologies, energy storage and conversion, which will result in an identification of nuclear strategies that can succeed under future market conditions.	Document	FCR&D	FY2014
Development and Optimization of Voltammetric Methods for Real Time Analysis of Electrorefiner Salt with High Concentrations of Actinides and Fission Products	University of Utah	$621,612	Researchers will develop an advanced voltammetry method to pursue the objective of real time monitoring of actinide concentrations in electrorefiner salt. This will include experimental measurement of key parameters such as activity coefficients and exchange current density. It will also involve simulation of voltammetry processes based on first principles. The project will allow for real time measurements that could support the commercialization of pyroprocessing.	Document	FCR&D	FY2014
Development of Self-Healing Zirconium-Silicide Coatings for Improved Performance of Zirconium-Alloy Fuel Cladding	University of Wisconsin, Madison	$798,621	Researchers will study the deposition of self-healing zirconium-silicide coatings on zirconium-alloy fuel cladding material to improve corrosion resistance under normal and accident conditions. Under these conditions, Zr-Si coating evolves into a highly protective functionally-graded multilayered system. The study will lead to improved performance of zirconium-alloy fuels._	Document	FCR&D	FY2014
Thermal Conductivity in Metallic Fuels	Virginia Polytechnic Institute and State University	$799,837	Researchers will calculate the thermal conductivity of metallic uranium and neptunium alloys, including the effects of noble gasses, using density functional theory. The experiments will validate the calculated effective thermal conductivity using the MARMOT code and by helping determine DFT simulation parameters. The study works to improve fuel lifetime by understanding its thermal behavior.	Document	FCR&D	FY2014
SiC-ODS Alloy Gradient Nanocomposites as Novel Cladding Materials	Virginia Polytechnic Institute and State University	$799,998	Researchers will combine nuclear nanomaterial design, processing, testing, and characterization efforts to develop revolutionary materials that can withstand neutron irradiation for long period of time using nanostructured SiC and oxide dispersion strengthened steel. The ultimate objective is to offer new cladding materials with increased corrosion resistance, strength, and creep resistance in both steady state and accident conditions.	Document	FCR&D	FY2014
Experimental Breeder Reactor II Benchmark Evaluation	Idaho State University	$400,000	Researchers will develop a benchmark evaluation of the Experimental Breeder Reactor II (EBR-II). During nearly 30 years of operation numerous experiments were conducted at EBR-II. The most significant of these experiments were conducted in 1986 demonstrating inherent safety features in loss of flow without reactor scram and loss of heat sink without reactor scram. Benchmark evaluation will be valuable for the reactor design efforts in the United States and South Korea.	Document	MSNE	FY2014
Integral full core multi-physics PWR benchmark with measured data	Massachusetts Institute of Technology	$400,000	Researchers will introduce BEAVRS, a new multi-cycle full-core Pressurized Water Reactor (PWR) depletion benchmark based on two operational cycles of a commercial nuclear power plant. This project aims at addressing the uncertainty quantification of the measured data and on making this benchmark a true non-proprietary international benchmark for the validation of high-fidelity multi-physics computational tools.	Document	MSNE	FY2014
Benchmark Evaluation of PROTEUS Gas-Cooled Reactor Experiments	University of Florida	$400,000	Researchers will create International Reactor Physics Experiment Evaluation Project (IRPhEP) benchmarks using data from 1970s experiments of the neutronics of gas-cooled fast reactor (GCFR) designs investigated in the PROTEUS reactor. The GCFR-PROTEUS experiments fill a gap in current integral benchmark data. These experiments can provide validation of computational models and nuclear data for next generation reactors.	Document	MSNE	FY2014
An Investigation To Establish Multiphysical Property Dataset Of Nuclear Materials Based On In-Situ Observations And Measurements	Purdue University	$800,000	Researchers will create an in-situ measurement based experimental approach to develop experimental validation dataset for NEAMS based code validation. Particular emphasis is on supplying data set for multiphysics simulations in extreme conditions as a function of material microstructure.	Document	NEAMS	FY2014
Experimental Validation of UO2 Microstructural Evolutions for NEAMS tool MARMOT	University of Florida	$798,000	Researchers will experimentally validate MARMOT for predicting the microstructural evolutions of UO2 oxide fuel under the driving forces of high temperatures and large temperature gradient in reactors. By performing the experiments and simulations simultaneously using precisely defined initial conditions, the experiment data will provide direct benchmarking of the MARMOT code.	Document	NEAMS	FY2014
High-resolution time-resolved experiments on mixing and entrainment of buoyant jets in stratified environments	University of Michigan	$799,983	Researchers will study high spatial and time-resolution experimental data of the fluid dynamics phenomena of flow jets interacting with a stratified layer. The issue plays an important role in the safety of several reactor designs, including sodium-cooled reactors. The data addresses the NEAMS needs for the validation of high fidelity computational fluid dynamics methodologies.	Document	NEAMS	FY2014
Fundamental study of key issues related to advanced S-CO2 Brayton Cycle: prototypic HX development and Cavitation	Georgia Institute of Technology	$799,000	Researchers will study scientific and operational issues pertinent to compact heat exchanger systems and turbo-machinery. The project will work to resolve issues with the fabrication of diffusion bonded compact heat exchangers, alternate heat exchange technology for recuperators, and resolution of issues with cavitation and fluid instabilities.	Document	RCRD&D	FY2014
Advanced Models for Nondestructive Evaluation of Aging Nuclear Power Plant Cables	Iowa State University	$787,291	Researchers will develop advanced models that relate environmentally induced microstructural and chemical changes in cable insulation polymers to their macroscopic electrical parameters. These parameters will be measured and modeled over a wide range of the electromagnetic spectrum, covering several potential nondestructive evaluation techniques, enabling identification of the most sensitive techniques for future development.	Document	RCRD&D	FY2014
Development of Novel Functionally Graded Transition Joints for Improving the Creep Strength of Dissimilar Metal Welds in Nuclear Applications	Lehigh University	$800,000	Researchers will develop graded transition joints and improved creep life models for increasing the life of dissimilar metal welds (DMWs) in nuclear reactors. The research represents the first application of functionally graded material concepts for solving the problem of DMW failures through an integrated approach of additive manufacturing, modeling, microstructural characterization, and advanced strain-sensing techniques.	Document	RCRD&D	FY2014
Feasibility Assessment of a Micro Modular Reactor (MMR)	North Carolina State University	$400,000	Researchers will develop an innovative compact reactor concept that integrates power production, power conversion and electricity generation in a single unit: the Micro Modular Reactor (MMR). It is designed to be absolutely melt-down proof (MDP) under all circumstances including complete loss of coolant scenarios with no possible release of radioactive material, to have a cycle length of greater than 10 years, and to be highly proliferation resistant.	Document	RCRD&D	FY2014
Scaling Studies for Advanced Gas Reactor Concepts	Oregon State University	$681,834	Researchers will expand the utilization of the Oregon State University High Temperature Test Facility (HTTF) to validate a broader range of advanced high temperature reactors and events. The facility will be revised to add a detailed scaling analysis of additional gas reactor concepts including advanced gas-cooled, molten salt, and sodium cooled reactors.	Document	RCRD&D	FY2014
Fluid Stratification Separate Effects Analysis, Testing and Benchmarking	Oregon State University	$800,000	Researchers will study fluid stratification in high temperature gas reactors. Coolant stratification is the result of incomplete mixing of one or more fluids, leading to a density gradient, which may or may not dissipate under diffusive or convective effects. This combined analytical and experimental project seeks to investigate stratification driven by diffusive and convective mechanisms and is expected to yield insight into this phenomenon.	Document	RCRD&D	FY2014
Probabilistic Economic Valuation of Safety Margin Management Analysis	Oregon State University	$795,364	Researchers will use RAVEN and develop a companion software package to facilitate economic analysis of safety margins. The project is a proof of concept that will use techniques to examine the cost of improving safety margins vs. the risk of accidents from not improving safety margins. This analysis can be used to evaluate the economic viability of various plant upgrades.	Document	RCRD&D	FY2014
Novel Dissimilar Joints Between Alloy 800H and 2.25%Cr and 1%Mo Steel	Pennsylvania State University	$800,000	Researchers will fabricate and test dissimilar metal joints between a nickel base alloy and a steel with gradual variations of chemical composition, microstructure and properties in a manner that reduces abrupt thermal expansion mismatch and the resulting residual stresses. Data on structure and properties will serve as valuable inputs for the initiation of an ASME code case.	Document	RCRD&D	FY2014
Multi-Phase Model Development to Assess RCIC System Capabilities under Severe Accident Conditions	Texas A&M University	$564,246	Researchers will develop physics-based models of the Reactor Core Isolation Cooling (RCIC) System and incorporating them into a multi-phase code for validation. The project will tackle the current major challenges in RCIC System analysis and enable evaluation of two-phase thermodynamic aspects.	Document	RCRD&D	FY2014
Experimental Investigation and CFD Analysis of Steam Ingress Accidents in HTGRs	The Ohio State University	$800,000	Researchers will study the steam ingress scenario for HTGRs. The study will investigate thermal-hydraulic behavior and graphite oxidation of stream ingress phenomena to validate predictive CFD models. This work will resolve concerns about possible steam generator tube ruptures in a HTGR He-Steam Rankine cycle.	Document	RCRD&D	FY2014
Coiled Tube Gas Heaters For Nuclear Gas-Brayton Power Conversion	University of California, Berkeley	$800,000	Researchers will develop heat exchangers for Brayton-cycle power conversion in reactors using sodium, NaK, or salt as intermediate coolants. The proposed coiled tube gas heaters (CTGHs) are expected to have excellent power density, thermal shock/creep, in-service inspection, and reparability characteristics.	Document	RCRD&D	FY2014
Fundamental Studies of Irradiation-Induced Modifications in Microstructural Evolution and Mechanical Properties of Advanced Alloys	University of Illinois, Urbana-Champaign	$800,000	Researchers will develop and test a mechanism for predicting neutron irradiation performance for optimized Grade 92 and Alloy 709 for applications in advanced reactor systems. The work will employ ion irradiations and available information from neutron irradiations of related alloys to develop a basis for predicting the neutron irradiation performance of the optimized alloys.	Document	RCRD&D	FY2014
Integrated Computational and Experimental Study of Radiation Damage Effects in Grade 92 Steel and Alloy 709	University of Tennessee	$800,000	Researchers will develop a mechanistic understanding and predictive models of irradiation-induced microstructural evolution and resulting mechanical properties in optimized ferritic-martensitic Grade 92 steel and austenitic alloy 709 using multiscale simulations coupled with rigorous experimental validation. The project will provide insights into the correlation between ion irradiation and fast neutron damage.	Document	RCRD&D	FY2014
Meta-Level Design Guidance and Operator Performance Measures for Hybrid Control Rooms	Vanderbilt University	$799,869	Researchers will apply human factors engineering methods and relevant expertise from non-nuclear high-risk high-consequence domains toward the measurement of operator performance in analog, digital, and hybrid main control rooms. Performance measures will be developed for evaluating the situation awareness and decision-making proficiencies to support the transition to digital or hybrid control room displays.	Document	RCRD&D	FY2014

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