Advanced Fuel Cycle Initiative (AFCI)
- NEUP Project 09-779: Development of Diffusion Barrier Coatings and Deposition Technologies for Mitigating Fuel Cladding Chemical Interactions (FCCI)
K. Sridharan, University of Wisconsin-Madison
- NEUP Project 09-780: Thermal Properties of LiCl-KCl Molten Salt for Nuclear Waste Separation
K. Sridharan, University of Wisconsin-Madison
- NEUP Project 09-782: Computational Design of Advanced Nuclear Fuels
S. Savrasov, University of California, Davis
- NEUP Project 09-783: Improvements to Nuclear Data and Its Uncertainties by Theoretical Modeling
Y. Danon, Rensselaer Polytechnic Institute
- NEUP Project 09-786: Advanced Mesh-Enabled Monte Carlo Capability for Multi-Physics Reactor Analysis
P. Wilson, University of Wisconsin, Madison
- NEUP Project 09-787: Ab Initio Enhanced Calphad Modeling of Actinide Rich Nuclear Fuels
D. Morgan, University of Wisconsin, Madison
- NEUP Project 09-791: Sharp Interface Tracking in Rotating Microflows of Solvent Extraction
J. Glimm, Stony Brook University
- NEUP Project 09-795: High-Fidelity Space-Time Adaptive Multiphysics Simulations in Nuclear Engineering
P. Solin, University of Nevada, Reno
- NEUP Project 09-800: Thermodynamic Development of Corrosion Rate Modeling in Iron Phosphate Glasses
M.E. Schlesinger and R.K. Brow, Missouri University of Science and Technology
- NEUP Project 09-804: Development of Subspace-Based Hybrid Monte Carlo-Deterministic Algorithms for Reactor Physics Calculations
H. Abdel-Khalik, North Carolina State University
- NEUP Project 09-806: Fundamental Understanding of Ambient and High-Temperature Plasticity Phenomena in Structural Materials in Advanced Reactors
C. Deo, Georgia Institute of Technology
- NEUP Project 09-809: Simulations of the Thermodynamic and Diffusion Properties of Actinide Oxide Fuel Materials
U. Becker, University of Michigan
- NEUP Project 09-811: Heterogeneous Recycling in Fast Reactors
B. Forget, Massachusetts Institute of Technology
- NEUP Project 09-814: Bulk Nanostructured FCC Steels with Enhanced Radiation Tolerance
X. Zhang, Texas A&M University
- NEUP Project 09-816: Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels
S. McDeavitt, Texas A&M University
- NEUP Project 09-818: Simulations of Failure via Three-Dimensional Cracking in Fuel Cladding for Advanced Nuclear Fuels
H. Lu, University of Texas, Dallas
- NEUP Project 09-820: Quantification of UV-Visible and Laser Spectroscopic Techniques for Materials Accountability and Process Control
K. Czerwinski, University of Nevada, Las Vegas
- NEUP Project 09-821: Development of Alternative Technetium Waste Forms
K. Czerwinski, University of Nevada, Las Vegas
- NEUP Project 09-825: Adsorptive Separation and Sequestration of Krypton, I and C14 on Diamond Nanoparticles
T. Ghosh, University of Missouri-Columbia
- NEUP Project 09-828: Data Collection Methods for Validation of Advanced Multi-Resolution Fast Reactor Simulations
A. Tokuhiro, University of Idaho
- NEUP Project 09-829: Advanced Elastic/Inelastic Nuclear Data Development Project
F. Harmon, Idaho State University
- NEUP Project 09-842: SiC Schottky Diode Detectors for Measurement of Actinide Concentrations from Alpha Activities in Molten Salt Electrolyte
W. Windl, Ohio State University
Investigator Initiated Research (IIR)
- NEUP Project 09-766: Improved LWR Cladding Performance by EPD Surface Modification Technique
M. Corradini, University of Wisconsin, Madison
- NEUP Project 09-769: Maximum Fuel Utilization in Fast Reactors Without Chemical Reprocessing
E. Greenspan, University of California, Berkeley
- NEUP Project 09-773: Developing a High Thermal Conductivity Fuel with Silicon Carbide Additives
R. Baney, University of Florida
- NEUP Project 09-775: Fabrication of Tungsten-Rhenium Cladding Materials via Spark Plasma Sintering for Ultra High Temperature Reactor Applications
I. Charit, University of Idaho
- NEUP Project 09-790: Neutron Damage and MAX Phase Ternary Compounds
M. Barsoum, Drexel University
- NEUP Project 09-802: Improved Fission Neutron Data Base for Active Interrogation of Actinides
S. Pozzi, University of Michigan
- NEUP Project 09-805: Ionic Liquid and Supercritical Fluid Hyphenated Techniques for Dissolution and Separation of Lanthanides, Actinides, and Fission Products
C. Wai, University of Idaho
- NEUP Project 09-823: Atomistic Calculations of the Effect of Minor Actinides on Thermodynamic and Kinetic Properties of UO2±x
C. Deo, Georgia Institute of Technology
- NEUP Project 09-824: Utilization of Methacrylates and Polymer Matrices for the Synthesis of Ion Specific Resins
K. Czerwinski, University of Nevada, Las Vegas
Light Water Reactor Sustainability (LWRS)
- NEUP Project 09-834: Advanced Models of LWR Pressure Vessel Embrittlement for Low Flux-High Fluence Conditions
G.R. Odette, University of California, Santa Barbara
Next Generation Nuclear Plant (NGNP)/Generation IV Nuclear Systems
- NEUP Project 09-764: An Innovative and Advanced Coupled Neutron Transport and Thermal Hydraulic Method (Tool) for the Design, Analysis and Optimization of VHTR/NGNP Prismatic Reactors
F. Rahnema, Georgia Institute of Technology
- NEUP Project 09-765: ALD Coatings on Gd2O3 Burnable Poison Nanoparticles and Carbonaceous TRISO Coating Layers
A. Weimer, University of Colorado, Boulder
- NEUP Project 09-768: Corrosion and Creep of Candidate Alloys in High Temperature Helium and Steam Environments for the NGNP
G. Was, University of Michigan
- NEUP Project 09-770: Accurate Development of Thermal Neutron Scattering Cross Section Libraries
A. Hawari, North Carolina State University
- NEUP Project 09-771: Creation of Full-Core HTR Benchmark with the Fort St. Vrain Initial Core and Assessment of Uncertainties in the FSV Fuel Composition and Geometry
W.R. Martin, University of Michigan
- NEUP Project 09-776: Mechanisms Governing the Creep Behavior of High Temperature Alloys for Generation IV Nuclear Energy Systems
V. Vasudevan, University of Cincinnati
- NEUP Project 09-777: Liquid Salt Heat Exchanger Technology for VHTR Based Applications
M. Anderson, University of Wisonsin, Madison
- NEUP Project 09-778: Materials, Turbomachinery and Heat Exchangers for Supercritical CO2 Systems
M. Anderson, University of Wisonsin, Madison
- NEUP Project 09-781: Experimental Studies of NGNP Reactor Cavity Cooling Systems with Water
M. Corradini, University of Wisconsin-Madison
- NEUP Project 09-784: Investigation of Countercurrent Helium-Air Flows in Air-Ingress Accidents for VHTRs
X. Sun, The Ohio State University
- NEUP Project 09-785: Assessment of Embrittlement of VHTR Structural Alloys in Impure Helium Environments
W. Crone, University of Wisconsin, Madison
- NEUP Project 09-788: Modeling Fission Product Sorption in Graphite Structures
I. Szlufarska, University of Wisconsin, Madison
- NEUP Project 09-789: Integral and Separate Effects Tests for Thermal Hydraulics Code Validation for Liquid-Salt Cooled Nuclear Reactors
P. Peterson, University of California, Berkeley
- NEUP Project 09-794: Irradiation Creep in Graphite
R. Ubic, Boise State University
- NEUP Project 09-796: Understanding Creep Mechanisms in Graphite with Experiments, Multiscale Simulations, and Modeling
J. Eapen, North Carolina State University
- NEUP Project 09-798: Verification & Validation of High-Order Short-Characteristics-Based Deterministic Transport Methodology on Unstructured Grids
Y. Azmy, North Carolina State University
- NEUP Project 09-799: Effect of Post-Weld Heat Treatment on Creep Rupture Properties of Grade 91 Steel Heavy Section Welds
L. Li, Utah State University
- NEUP Project 09-801: Tritium Sequestration in Gen IV NGNP Gas Stream via Proton Conducting Ceramic Pumps
F. Chen, University of South Carolina
- NEUP Project 09-803: Identifying and Understanding Environment-Induced Crack Propagation Behavior in Solid Strengthened Ni-Based Superalloys
L. Ma, University of Nevada, Las Vegas
- NEUP Project 09-807: Verification of the CENTRM Module for Adaptation of the SCALE Code to NGNP Prismatic and PBR Core Designs
B. Ganapol, University of Arizona
- NEUP Project 09-808: A Distributed Fiber Optic Sensor Network for Online 3-D Temperature and Neutron Fluence Mapping in a VHTR Environment
P. Tsvetkov, Texas A&M University
- NEUP Project 09-810: Experimental Study and Computational Simulations of Key Pebble Bed Thermomechanics Issues for Design and Safety
A. Tokuhiro, University of Idaho
- NEUP Project 09-812: Multi-Scale Multi-Physics Methods Development for the Calculation of Hot-Spots in the NGNP
T. Downar, University of Michigan
- NEUP Project 09-813: TRISO-Coated Fuel Durability Under Extreme Conditions
I. Reimanis, Colorado School of Mines
- NEUP Project 09-817: CFD Model Development and Validation for High Temperature Gas Cooled Reactor Cavity Cooling System (RCCS) Applications
Y. Hassan, Texas A&M University
- NEUP Project 09-819: Testing of Performance of Optical Fibers Under Irradiation in Intense Radiation Fields When Subjected to High Temperature
T. Blue, The Ohio State University
- NEUP Project 09-822: Optimizing Neutron Thermal Scattering Effects in Very High Temperature Reactors
A. Hawari, North Carolina State University
- NEUP Project 09-826: Understanding Fundamental Material Degradation Processes in High Temperature Aggressive Chemomechanical Environments
J. Stubbins, University of Illinois at Urbana-Champaign
- NEUP Project 09-827: Fission Product Sorptivity in Graphite
R. Tompson, University of Missouri
- NEUP Project 09-830: Graphite Oxidation Simulation in HTR Accident Conditions
M. El-Genk, University of New Mexico
- NEUP Project 09-831: 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
X. Zhang, University of Rochester
- NEUP Project 09-832: Multiaxial Creep-Fatigue and Creep-Ratcheting Failures of Grade 91 and Haynes 230 Alloys Toward Addressing Design Issues of Gen IV Nuclear Power Plants
T. Hassan, North Carolina State University
- NEUP Project 09-833: Millimeter-Wave Thermal Analysis Development and Application to GEN IV Reactor Materials
P. Woskov, Massachusetts Institute of Technology
- NEUP Project 09-835: Prediction and Monitoring Systems of Creep-Fracture Behavior of 9Cr-1Mo Steels for Reactor Pressure Vessels
G. Potirniche, University of Idaho
- NEUP Project 09-838: Modeling Stress Strain Relationships and Predicting Failure Probabilities for Graphite Core Components
S. Duffy, Cleveland State University
- NEUP Project 09-840: Investigation on the Core Bypass Flow in a Very High Temperature Reactor
Y. Hassan, Texas A&M University
- NEUP Project 09-841: Study of Air Ingress Across the Duct During the Accident Conditions
Y. Hassan, Texas A&M University
- NEUP Project 09-843: Microscale Heat Conduction Models and Doppler Feedback
A. Hawari, North Carolina State University
- NEUP Project 09-844: Removal of 14C from Irradiated Graphite for Graphite Recycle and Waste Volume Reduction
M.L. Dunzik-Gougar, Idaho State University