NEUP Funded Projects
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 | |
|---|---|---|---|---|---|---|
| Understanding PM-HIP Interparticle Evolution and its Influence on Fracture Toughness in Alumina-Forming Steels | Purdue University | $1,100,000 | This project aims to understand how interparticle evolution during hot isostatic pressing (HIP) influences fracture toughness of Al-bearing steels. The team will use a series of interrupted HIP experiments with phase field models to understand the formation mechanisms of interparticle defects during HIP of alumina-forming austenitic (AFA) stainless steels and FeCrAl steels, and the influence of these defects on fracture behavior. | Document | Advanced Manufacturing Technologies | FY2024 |
| Multiscale high-throughput experiment/modeling approach to understanding creep behavior in Additively Manufactured reactor steels | University of Minnesota, Twin Cities | $1,043,271 | This project proposes to develop a predictive capability for processing-microstructure-property correlations in additive manufactured microstructures utilizing a multiscale approach encompassing bulk creep tests, miniaturized tensile testing, and a high-throughput, indentation based, cost-effective method for elevated temperature mechanical mapping of additively manufactured 316H Stainless Steel, Grade 91, and Titanium-Zirconium-Molybdenum (TZM) alloys. | Document | Advanced Manufacturing Technologies | FY2024 |
| Hi-fidelity characterization of molten salt-graphite pore interactions through experiments and embedded modeling | North Carolina State University | $1,100,000 | We propose a suite of fuel salt (FLiBe + U) infiltration experiments (University of Michigan-UM) followed by X-ray computed tomography, XCT (NCSU), in-situ mechanical property evaluation with scanning electron microscopy (NCSU) and high fidelity data analytics and modeling (NCSU/Leeds) along with complimentary porosimetry measurements (ORNL) and XPS analysis at University of Manchester (UoM). Three graphite grades are selected in this project: NBG-18, IG-110 and POCO: ZXF-5Q. | Document | Advanced Nuclear Materials | FY2024 |
| Assessing molten salt corrosion resistance of stainless steel 316H in nuclear reactor environments | North Carolina State University | $1,100,000 | The proposed goal is to leverage a blend of innovative molten salt corrosion experiments and cutting-edge characterization techniques to advance our understanding of molten salt corrosion in both commercial and additively manufactured (AM) stainless steel (SS) 316H, particularly under radiation or stress environments. | Document | Advanced Nuclear Materials | FY2024 |
| Polymer-Derived C-SiC Coatings on Kernel Particles for Advanced Nuclear Reactors | University of Alabama at Birmingham | $1,100,000 | This program is to use a polymer-derived ceramic approach to develop C-SiC/ZrC coatings on ZrO2 kernel substitute particles. We aim to create new fuel encapsulation materials in replacement of the coatings on fuel kernel particles, including the TRISO layers, for advanced reactors, conduct ion irradiation testing of the new materials for nuclear performance evaluation, and carry out detailed microstructure and composition characterization to assess the C-SiC/ZrC coated fuel particle behaviors. | Document | Advanced Nuclear Materials | FY2024 |
| Sorbent regeneration, recycling, and transformation: A transformative approach to iodine capture and immobilization | University of Nevada, Reno | $1,000,000 | The project will focus on the development of materials and processes for regeneration and recycling of sorbents, and the transformation of iodine-loaded sorbents into waste forms. A combination of computational and experimental studies will be conducted to understand (a) how the components in a primary off-gas stream interact with the sorbent, (b) how this off-gas stream affects the regeneration lifetime, and (c) low-temperature binders and processing paths that leads to durable waste forms. | Document | Advanced Nuclear Materials | FY2024 |
| Developing place-based understandings of respectful community engagement for consent-based siting | University of Michigan | $1,100,000 | Through this project we seek to develop (1) guiding principles for respectful community engagement-to support consent-based siting-empirically rooted in the lived experiences of Native Communities; (2) metrics and indicators of consent; and (3) a generative AI tool to facilitate community-based storytelling of the past and imagining of the future to visualize how nuclear infrastructures have and could in the future alter community landscapes. | Document | Consent-based Siting for SNF Management | FY2024 |
| Informing Consent-Based Siting of a Consolidated Interim Storage Facility (CISF): Examining Public Engagement Through History and Evaluation of Prior & Current Outreach Results | Vanderbilt University | $1,000,000 | We will use two phases of research to assist NE in understanding factors that influence the quality and extent of public engagement needed to address different people and communities seeking to make decisions regarding the siting of a CISF. Supporting NE's the consent-based siting process we have developed an accelerated 2-year schedule, focusing on three geographic areas of the US: IL, TX & NM and the area served by the TVA/Duke Power Ñeach contain multiple SNF storage facilities. | Document | Consent-based Siting for SNF Management | FY2024 |
| Accident Tolerant Fuels to Support Power Uprates in LWRs | University of Wisconsin-Madison | $1,100,000 | This project will demonstrate that power uprates higher than the current state of operation can be reached using accident tolerant fuels in light water reactors while not exceeding reactor safety margins during normal operation and accidents. We will analyze it considering fuel enriched up to 10% and peak rod average burnup up to 75GWd/tU concerning reactor physics, thermal-hydraulics, reactor safety, and economics. Considerations will be made in consultation with the named industry advisory board. | Document | Existing Plant Optimization | FY2024 |
| Comparative study of three-dimensional microstructural imaging and thermal conductivity evolution of irradiated solid and annular U-Zr fuels | Massachusetts Institute of Technology | $1,000,000 | Uranium-zirconium (U-Zr) annular metallic fuel holds the promise to simultaneously increase sodium fast reactor (SFR) core uranium loading and reduce peak cladding temperatures, thus greatly improving fuel performance. However, key convolved fuel degradation mechanisms during irradiation at temperature threaten to hold back its real-world applicability, requiring more detailed understanding to both predict U-Zr fuel performance and suggest improvements. | Document | Fuels | FY2024 |
| Mechanistic study and modeling of fission gas release in UO2 and doped UO2 | Oregon State University | $1,000,000 | The objective of this project is to enhance the safety and performance of light water reactors and other advanced reactor designs by gaining a fundamental understanding of fast gas reactor mechanisms and developing mechanistic models for UO2 and doped UO2 fuels under HBU and transient conditions. | Document | Fuels | FY2024 |
| Anisotropic Thermal Properties of SiC-SiC Cladding: Method Development & Characterization | University of Pittsburgh | $1,000,000 | We propose to develop a high-temperature nondestructive thermal conductivity (k) measurement system coupled with validated multiscale models to accurately determine the anisotropic thermal conductivity of SiC-SiC composite cladding tubes. The multiscale measurement and modeling results benefit both DOE ATF programs as well as providing a fundamental understanding of how the microstructure of the composite leads to its anisotropic properties. | Document | Fuels | FY2024 |
| Understanding the Performance of SiC-SiCf Composite Cladding Architectures with Cr Coating in Normal Operating and Accident Conditions in LWRs and Advanced Reactors | University of Wisconsin-Madison | $1,000,000 | The project will focus on investigating the impact of Cr-coating on the SiC-SiCf composite cladding of various architectures under normal operating and accident conditions in light water reactors and advanced reactors for the safe and economic deployment of SiC cladding. Cr-coating will provide protection from high-temperature corrosion and better hermeticity under accident conditions. The performance of the claddings will be evaluated through the corrosion test, reflood test, burst test, and non-destructive evaluation(NDE). | Document | Fuels | FY2024 |
| Developing critical insights on the effects of Mo on a' precipitation and dislocation loop formation in FeCrAl alloys | University of Wisconsin-Madison | $1,000,000 | This project aims at developing a mechanistic understanding on the effects of Mo on a' precipitation and dislocation loop formation in FeCrAl alloys in thermal and irradiation conditions and turns it into a set of design principles guiding further optimization, by integrating atomistic simulations, CALPHAD modeling, thermal aging, proton irradiation, and advanced characterization. The material discoveries will be generalized to other solutes other than Mo. | Document | Fuels | FY2024 |
| Inference of flow conditions from in-core detector measurements for accelerating SMR licensing | Massachusetts Institute of Technology | $1,000,000 | Reactor modelling relies on the detailed description of reactor systems but often lacks the true as-built characteristics of a system. This proposal seeks to fill these geometrical data gaps using available detector data, predictive models and machine learning in order to provide better information to analysis tools and thus better prediction of future performance. | Document | Licensing, Safety, and Security | FY2024 |
| Taggants in Future Nuclear Fuels by Design as an Enabling Technology to Track Nuclear Materials | Rensselaer Polytechnic Institute | $1,000,000 | The overarching goal of this project is to develop an innovative materials accounting and control technology by adopting an approach of "safeguard by design" during fuel fabrication to fill nuclear control technology gaps in tracing and tracking nuclear fuels for advanced nuclear reactors. The project is based on a concept of "taggants in fuels" that can greatly increase forensic attributes, and enhance intrinsic proliferation resistance and MPACT effectiveness for advanced nuclear fuel cycles. | Document | Licensing, Safety, and Security | FY2024 |
| Non-Destructive Plutonium Assay in Pyroprocessing Bulk Materials with a 3D Boron-Coated-Straw Detector Array | University of Illinois at Urbana-Champaign | $1,100,000 | The objective of the proposed project is to develop and demonstrate a 3D boron-coated-straw detector array (3D-BCSDA) with high efficiency and spatial resolution. This detection system will be specifically designed to accurately assess the fissile mass in bulk nuclear material during pyroprocessing operations, thereby improving the precision and reliability of accountability measurements during separation. | Document | Licensing, Safety, and Security | FY2024 |
| Improving the computational efficiency and usability of dynamic PRA with reinforcement learning | University of Maryland, College Park | $1,064,400 | The overall objective of the proposed research is to improve the efficiency and usability of dynamic probabilistic risk assessment (PRA). Specifically, the first objective is to develop a new algorithm for dynamic PRA analysis that can significantly increase the computational efficiency. The second objective is to develop a question-answering system to streamline the process of risk-informed decision-making based on results obtained from the dynamic PRA analysis using the new algorithm. | Document | Licensing, Safety, and Security | FY2024 |
| Development of a Benchmark Model for the Near Real-Time Radionuclide Composition Measurement System using Microcalorimetry for Advanced Reactors | Virginia Commonwealth University | $1,100,000 | The primary goal of this proposed project is to develop high fidelity Monte Carlo radiation transport models of a microcalorimetry detector informed by fuel depletion models of a molten salt reactor and a pebble bed reactor to quantify the current and future capabilities of this detector technology to characterize and assay used fuel from these reactors in near real-time. | Document | Licensing, Safety, and Security | FY2024 |
| Concurrent Surrogate Model Development with Uncertainty Quantification in the MOOSE Framework Using Physics-Informed Gaussian-Process Machine Learning | University of Florida | $999,999 | The objective of this project is to develop a general capability for concurrent generation and use of physics-informed Gaussian process (GP)-based surrogate models to facilitate multiscale and multiphysics modeling. We will implement this new capability as part of the Multiphysics Object-Oriented Simulation Environment (MOOSE) so that every application based on the MOOSE framework will have access to it. | Document | Modeling and Simulation | FY2024 |
| Unstructured Adaptive Mesh Algorithms for Monte Carlo Transport | University of Illinois at Urbana-Champaign | $1,098,000 | We propose to develop the fundamental methods and techniques for unstructured adaptive mesh refinement with Monte Carlo tallies. This work enables a transformative leap forward in speed, accuracy, and robustness to enhance the contribution of high-fidelity radiation transport to advanced simulation. Adaptive refinement is deployed on a challenging multiphysics simulation, cascading heat pipe failure, to study acceleration and stabilization properties. | Document | Modeling and Simulation | FY2024 |
| Feasibility Study of Micro-Nuclear Reactor Thermal Output for Air Rotary Kilns in the High-Temperature Manufacturing of Portland Cement Clinker | Pennsylvania State University | $998,793 | This project aims to design and test a micro-nuclear reactor for high-temperature portland cement clinker production, a process responsible for 6%-8% of global CO2 emissions. Leveraging advanced reactors' heat output, the project explores TRISO-based nuclear microreactor core modifications and new working fluids for heat pipes. The research addresses uncertainties in micro-nuclear reactor deployment for clinker production and investigates high-efficiency heat exchanger designs. | Document | Non-Traditional and Non-electric Applications | FY2024 |
| Redox potential, ionic speciation, and separation and recovery challenges from molten salts containing actinides and fission products | Massachusetts Institute of Technology | $999,999 | Establishing an efficient, safe, secure, and economical Molten-Salt Reactor (MSR) fuel cycle is imperative for MSR implementation. Molten salt fuel recycling technology requires predictive knowledge of the chemical and physical behavior of lanthanide and actinide ions with different oxidation states dissolved in solvent salts. A combination of off-gas and X-ray measurements with machine-learning simulations will be used to produce predictive modeling of separation and recovery conditions. | Document | Nuclear Fuel Recycle Technologies | FY2024 |
| Pre-Treatment and Bulk Separation of Used Fuels with Carbonate-Peroxide Solutions | Pennsylvania State University | $1,000,000 | To use carbonate-peroxide chemistries to develop a pre-processing method for used uranium-based fuels that enables the subsequent use and optimization of current solvent extraction reprocessing schemes. Using simple precipitation, this innovative method provides an initial, bulk separation of uranium from fission products and actinides. | Document | Nuclear Fuel Recycle Technologies | FY2024 |
| Optimization of Fueling Strategies and Material Surveillance through Real-time Pebble Tracking in Pebble Bed Reactors | University of Illinois at Urbana-Champaign | $1,100,000 | Flexible operation of the energy grid of the future introduces uncertainty in determining the optimal operating conditions of Pebble Bed Reactors. The proposed work will help to address these challenges and enable more economical operation by providing the tools to determine of optimal fuel reloading strategy through pebble identification and tracking. | Document | Reactor Development and Plant Optimization | FY2024 |
| Effects of Tritium-Graphite Interactions on Safety Transients in Graphite-Moderated Nuclear Reactors. | University of Illinois at Urbana-Champaign | $1,000,000 | MSRs, FHRs, and HTGRs have tritium production rates 10 to 10,000 times larger than LWRs. Objective of this project is to:-Quantify the concentration of tritium in graphite in new generation FHRs and HTGRs as a function of time and operational conditions-Assess the impact of the tritium content in graphite on reactor physics during normal operations and safety transients-Quantify tritium release rates and release kinetics during reactor transients inducing temperature increases | Document | Reactor Development and Plant Optimization | FY2024 |
| Experimental Study and Computational Modeling of P-LOFC and D-LOFC Accidents in the Fast Modular Reactor Consisting of Silicon Carbide Composite Rods | University of Michigan | $1,100,000 | The primary objectives of this proposed research are to better understand NC flow phenomena and heat transfer under both D-LOFC and P-LOFC accidents in the FMR, produce experimental data in a well-scaled integral-effects test facility for the two accidents, and develop and validate predictive CFD models for NC flow phenomena in both accidents. | Document | Reactor Development and Plant Optimization | FY2024 |
| Sodium heat pipes; design and failure mode assessment for micro-reactor applications | University of Wisconsin-Madison | $1,000,000 | The present proposal aims to experimentally investigate the thermal-hydraulics performance of liquid sodium heat pipes applied to microreactors, with a focus on exploring different design parameters, effects of different parameters on operating performance and understanding the evolution and impact of different failure modes. | Document | Reactor Development and Plant Optimization | FY2024 |
| Interfacial Interactions between Graphite and Molten Fluoride Fuel Salt | Virginia Polytechnic Institute and State University | $1,000,000 | NaF-KF-UF4 fuel salt will be selected to study graphite-salt interactions and impact of the existence of fission products (FPs) and corrosion products on the interactions at different temperatures and pressures. Fundamental mechanisms of graphite-salt interaction and degradation will be understood. | Document | Reactor Development and Plant Optimization | FY2024 |
| AI to Guide Sorption Data Acquisition and Assimilation into Uncertainty Quantifications for the Nuclear Waste Disposal Performance Assessment | Massachusetts Institute of Technology | $800,000 | The objective of this project is to develop machine learning (ML) and AI toolsets to effectively expand the global sorption database-the datasets collected by multiple institutions around the world-and to assimilate these datasets into the uncertainty quantification (UQ) in the performance assessment (PA) of nuclear waste repositories. | Document | Spent Fuel, Waste Science & Technology and Integrated Waste Management System | FY2024 |
| Local resonance-based linear and nonlinear NDE techniques for repaired DSC wall structures | University of Illinois at Urbana-Champaign | $1,000,000 | The proposed work plan will develop nondestructive examination (NDE) methods that develop and evaluate linear and nonlinear resonant ultrasound spectroscopy methods (such as NRUS, NIRAS, etc.) to cold spray (CS) repaired dry shielded canister (DSC) wall structures. With the support of our partners from Pacific Northwest National Laboratory (PNNL) and Oak Ridge National Laboratory (ORNL), we will perform technology development and validation on plain and cold spray-repaired DSC wall specimens. | Document | Spent Fuel, Waste Science & Technology and Integrated Waste Management System | FY2024 |
| Thermodynamic Models for Multivalent Actinide Solubility and Speciation as a Function of Temperature and Ionic Strength | University of Notre Dame | $1,000,000 | This proposed project will quantify the solubility and speciation of Np and Pu under temperatures, ionic strengths, and pH values that are relevant to the generic repository concept. The major deliverable will be full thermodynamic descriptions of the studied systems, which will lead to improved radionuclide transport models and support the development of a sound technical basis for the geologic disposal of spent nuclear fuel and other actinide-bearing wastes. | Document | Spent Fuel, Waste Science & Technology and Integrated Waste Management System | FY2024 |
| Advancing Fundamental Molten Salt Modeling using Ultrafast Spectroscopy | North Carolina State University | $600,000 | The overarching goal of the proposed research is to advance our fundamental understanding of molten salts by combining ultrafast spectroscopic experiments with high fidelity atomistic simulations. The proposed research will introduce a new experimental technique to the study of molten salts that will directly measure ion kinetics, specifically, terahertz time-domain spectroscopy (THz-TDS), which will further validate AIMD as a predictive modeling tool. | Document | Strategic Needs Blue Sky | FY2024 |
| Hydrodynamics of Two-Phase Flow Under the Geometric Effects of Pipe Orientation and U-bends | Purdue University | $600,000 | Most two-phase flow analyses have been performed in straight vertical-upward pipes. However, nuclear reactor systems include piping with different geometric components, such as elbows or U-bends, as well as changes in flow orientations. The proposed work performs experiments in a scaled test facility existing at the institution's lab to investigate the effects of flow orientations and geometries relevant to nuclear reactor systems on the hydrodynamics of two-phase flow. | Document | Strategic Needs Blue Sky | FY2024 |
| Interface-Resolved Experimental and Numerical Studies of Two-Phase Flow for Nuclear Engineering Applications | Virginia Polytechnic Institute and State University | $500,000 | The project aims at advancing the interface-resolved simulation capabilities for the two-phase flows found in various nuclear engineering applications. We will develop a comprehensive, high-resolution, interface-resolved database emphasizing bubble dynamics and bubble interaction mechanisms. The data will be used to validate the sub-grid models implemented in an interface-resolved simulation tool to improve simulation accuracy by developing physics-based coalescence models. | Document | Strategic Needs Blue Sky | FY2024 |
| Mechanism Driven Evaluations of Sequential and Simultaneous Irradiation-Creep-Fatigue Testing | University of Michigan | $1,000,000 | This project addresses a critical need for irradiation and creep-fatigue testing by carrying out a systematic, mechanistic-driven benchmarking for irradiation creep, irradiation fatigue and creep-fatigue tests under various environments. | Document | Advanced Nuclear Materials | FY2023 |
| Mechanisms-based Acceleration of Materials Qualifications for Creep-Fatigue Performance in Advanced Nuclear Systems | University of Illinois at Urbana-Champaign | $1,000,000 | The goal of this research is to fully understand, quantify and model creep-fatigue 'damage' as a function of loading patterns, temperature and microstructural evolution. Using this experimental information over a large range of relevant stress levels and temperatures, a mechanisms-based creep-fatigue analysis approach will be demonstrated which will properly qualify high temperature alloys for extended service in advanced nuclear systems where creep-fatigue is currently a major design limitation. | Document | Advanced Nuclear Materials | FY2023 |
| Subwavelength Ultrasonic Imaging for Rapid Qualification of Additively Manufactured Nuclear Structures and Components | University of Michigan | $1,000,000 | The objective of this project is to develop a transformational capability for rapid nondestructive quality assessment of actual nuclear additively manufactured structures and components through advanced ultrasonic imaging with subwavelength resolution. The resolution of conventional ultrasonic systems is limited by diffraction on the order of the wavelength. In this project, the goal is to break the diffraction limits of ultrasonic imaging by implementing a negative-index lens. | Document | Advanced Nuclear Materials | FY2023 |
| MXene as Sorbent Materials for Off-gas Radioiodine Capture and Immobilization | Clemson University | $1,000,000 | The overarching goal of this project is to develop efficient and stable new sorbent materials, for off-gas radioiodine capture and immobilization, that are based on MXenes with two-dimensional transition metal carbides/nitrides. The exploratory research will focus on three main objectives: 1) Design and synthesis of MXenes as radioiodine sorbent and support materials, 2) Quantification of iodine sorption capacity of MXenes in different forms, 3) Synthesis and characterization of consolidated waste forms. | Document | Advanced Nuclear Materials | FY2023 |
| Fundamental understanding of grain boundary cracking in LWR environments | University of California, Los Angeles | $1,000,000 | The objective of this project is to understand the details of stress corrosion cracking (SCC) and irradiation assisted stress corrosion cracking (IASCC) by targeted experiments and modeling efforts. A comprehensive model will be produced, which will predict the conditions under which these failure modes occur and when the materials may see onsets of the failure mode. This work will directly impact the nuclear industry by refining predictive models of component lifetime. | Document | Advanced Nuclear Materials | FY2023 |
| Facile manufacturing of fiber-reinforced-SiC/SiC composite using aerodynamic fiber deposition (AFD) and metal assisted polymer impregnation and pyrolysis processes (MAPIP) | University of Pittsburgh | $999,886 | SiC/SiC ceramic matrix composites (CMCs) are promising candidate materials for the cladding of accident tolerant fuels. Superior material properties of SiC/SiC CMC, however, come at a high manufacturing cost. The objective of the proposed research is to apply aerodynamic fiber deposition (AFD) and metal assisted polymer impregnation and pyrolysis (MAPIP) to develop a new facile manufacturing approach of SiC/SiC CMC. | Document | Advanced Nuclear Materials | FY2023 |
| High Concentration Monoamide Separations: Phase Modifiers and Transuranic Chemistry | Colorado School of Mines | $999,900 | Extraction of actinides from used nuclear fuel with high concentrations of monoamide extractants is a promising strategy to intensify separation processes; however key issues remain to be understood and resolved. This project will examine three questions: 1) Can phase modifiers mitigate issues with organic phase viscosity? 2) Can the chemistry of neptunium be controlled to ensure complete separation? 3) Do high concentrations of monoamides affect the oxidation states of important metals and can that be exploited? | Document | Fuel Cycle Technologies | FY2023 |
| Multiple Uranium Complexes in Chloride Fast Reactor Molten Salt Properties | University of Connecticut | $1,000,000 | Multivalent transition metal ions in a melt can exhibit multiple coordination states that affect molten salt properties. This project will use a new high-energy resolution fluorescence detection (HERFD) spectroscopy to overcome issues associated with measuring coordination numbers of multiple complexes, along with Raman spectroscopy and advanced simulations to accurately predict properties of molten salts with multiple uranium complexes. | Document | Fuel Cycle Technologies | FY2023 |
| Validation of Geochemical Reactive Transport Long-Term predictions Using Natural Cements and Ancient Cements Analogues | Vanderbilt University | $950,000 | This project will validate long-term performance predictions of rock/cement interfaces based on characterization of natural analogues, ancient cements and interfaces with rock formations, and demonstrate applicability of the established testing and simulation workflow with argillite rock (representative of potential U.S. repository systems). This project addresses the research gap of long-term validation and uncertainty assessment associated with cement barrier performance and multi-physics models. | Document | Fuel Cycle Technologies | FY2023 |
| Predicting Pitting and Stress Corrosion Cracking of Dry Cask Storage Canisters via High Throughput Testing, Multiscale Characterization, and 3D Computer Vision based Machine Learning | The Ohio State University | $1,000,000 | This project consists of a US-UK collaborative research program focusing on the nucleation and growth of pits and stress corrosion cracking of stainless steel 304 (a canister material used for dry cask storage of spent nuclear fuels) by leveraging multi-scale characterization techniques, 2D/3D computer vision, and machine learning approaches. The study will enable the understanding and prediction of how and when pitting corrosion can nucleate, grow, and transition into stress corrosion cracking. | Document | Fuel Cycle Technologies | FY2023 |
| Multiscale Residual Stress Tailoring of Spent Fuel Canister CISCC Resistance | Purdue University | $1,000,000 | The objective of this project is to understand the role of residual stress in chloride-induced stress corrosion cracking (CISCC) of austenitic steel, then tailor CISCC initiation and propagation through engineered multiscale residual stress distributions. Microscopic and macroscopic residual stresses will be systematically varied, then a novel sequence of advanced, site-specific, correlative characterization techniques will be applied to directly link residual stress, pitting, and crack propagation. | Document | Fuel Cycle Technologies | FY2023 |
| Illuminating Emerging Supply Chain and Waste Management Challenges | University of Illinois at Urbana-Champaign | $1,000,000 | Regional constraints on domestic fuel supply and greater variation in demand from advanced reactors has led to a shift in the U.S. fuel cycle, and modeling tools must reflect this. In this work, Cyclus will be updated to better reflect new and emergent regional supply constraints, spatial and temporal fluctuations in material needs, and those impacts on the back-end of the fuel cycle will be quantified. This work will allow for flexible, reproducible analysis to inform stakeholder decision-making. | Document | Fuel Cycle Technologies | FY2023 |
| Determination of Local Structure and Phase Stability of Uranium Species in Molten Halide Salts: Linking Microscopic Structure with Macroscopic Thermodynamics | Arizona State University | $1,000,000 | The goal of this project is to determine the local structures (valence state, coordination configuration and medium-range structure) and thermodynamic stability of uranium species in molten chloride and fluoride salts at high temperatures using a combination of experimental and modeling methods. The obtained results will allow for revelation of the structure-stability relations of the studied systems and development of acid-base scales to determine the solubility of uranium in molten halide salts. | Document | Fuel Cycle Technologies | FY2023 |
| Thermal-Hydraulics Assessment of SiC Compared to Other ATF Cladding Materials and its Performance to Mitigate CRUD | University of Wisconsin-Madison | $1,000,000 | This project aims to experimentally investigate the thermal-hydraulics performance of SiC compared to the Cr-coated zircaloys and APMT ATF cladding materials under accident scenarios, including both DNB and dryout conditions. The project is divided into five tasks that will advance the understanding of the operation and optimization of heat pipes for advanced nuclear reactors. | Document | Fuels | FY2023 |
| Physics-Informed Artificial Intelligence for Non-Destructive Evaluation of Ceramic Composite Cladding by Creating Digital Fingerprints | University of Florida | $1,000,000 | The objective of this project is to spatially map the material composition, structure, and defect distribution of SiCf-SiCm composite tubes from ultrasonic wavefields measured from the materials and the defects within them. Specifically, this project will delve into the unique ultrasonic fingerprints (i.e., dispersion relations and mode shapes) of the SiCf-SiCm composites using physics-informed machine learning to assess the quality of the manufactured tubes based on their spatial-spectral ultrasonic characteristics. | Document | Fuels | FY2023 |
| Improving Reliability of Novel TRISO Fuel Forms for Advanced Reactors via Multiscale, High-Throughput Characterization and Modeling | Brigham Young University | $1,000,000 | This project will use a parallelized thermal conductivity (k) measurement device coupled with multiscale models to accurately predict the thermal conductivity of TRISO fuel composites. This project overcomes the issue plaguing many "localized" microscale measurements, namely the inability to scale local measurements up to engineering scale properties. This will be done by using Bayesian inference techniques and finite element models to predict effective thermal conductivity. | Document | Fuels | FY2023 |
| Understanding Constituent Redistribution, Thermal Transport, and Fission Gas Behavior in U-Zr Annular Fuel Without a Sodium Bond | University of Florida | $999,462 | This project will investigate the reason for changed constituent redistribution in annular U-Zr fuel without a sodium bond and how it changes the fission gas behavior and thermal conductivity. This will be achieved using a combination of microstructure characterization and thermal conductivity measurements of irradiated U-Zr annular fuel and multiscale modeling and simulation using the MARMOT and BISON fuel performance codes. | Document | Fuels | FY2023 |
| Getting AnCers: Metallothermic Molten Salt Synthesis and Reaction Thermodynamics of Actinide Ceramic Fuels | Oregon State University | $1,000,000 | Synthesis of high quality actinide ceramics (AnCers) remains a costly challenge. A low-temperature, high-yield, short-duration reaction that directly synthesizes UN and UC could reduce the cost of these advanced fuels greatly. This proposal aims to demonstrate a method by which the costs of AnCers can be greatly reduced-metallothermic molten salt synthesis. Optimization and thermodynamics data will be obtained. | Document | Fuels | FY2023 |
| Integrated Stand-off Optical Sensors for Molten Salt Reactor Monitoring | University of Pittsburgh | $1,000,000 | This project intends to develop robust and stand-off optical sensors to perform real-time molten salt levels, flow, and impurity measurements of molten salts. | Document | Instrumentation and Controls | FY2023 |
| Optical Sensors for Impurity Measurement in Liquid Metal-cooled Fast Reactors | University of Michigan | $1,000,000 | This project will investigate whether a unique combination of two versatile optical techniques-laser-induced breakdown spectroscopy (LIBS) and two-photon absorption laser-induced fluorescence (TALIF)-could provide a sensitive, robust, and convenient method for in-situ, real-time detection of trace impurities ( | Document | Instrumentation and Controls | FY2023 |
| Cybersecurity in advanced reactor fleet by cyber-informed design, real-time anomaly detection, dynamic monitoring, and cost-effective mitigation strategies | University of Wisconsin-Madison | $1,000,000 | The goal of this research is to provide technical solutions to unique cybersecurity challenges in future microreactor fleet through cyber-informed design (C-ID), real-time anomaly detection, dynamic monitoring, and cost-effective mitigation strategies. The efforts will significantly improve the economics and effectiveness of cybersecurity risk management in future microreactor fleets. | Document | Instrumentation and Controls | FY2023 |
| Building Cyber-Resilient Architecture for Advanced Reactors via Integrated Operations and Network Digital Twin | Georgia Institute of Technology | $1,000,000 | The research will develop a secure-by-design architecture via integrating plant operation and network digital twins for advanced reactors. Automatic attack path and vulnerability analysis will be developed and used to assess and harden critical digital assets (CDA) against cyber risks prior to and during operation to identify vulnerabilities, attack pathways, and threat vectors. A CDA selection method will also be developed by combining vulnerability scores and assets importance. | Document | Instrumentation and Controls | FY2023 |
| Extending PRA and HRA legacy methods and tools with a cause-based model for comprehensive treatment of human error dependency | University of California, Los Angeles | $1,000,000 | This project aims at developing a solution to HRA dependency assessment in PRA from methodological and practical/computational perspectives within legacy PRA tools and methods. The solutions will include procedures for quantifying dependency when using PRA legacy tools, a method for modeling and quantifying dependency in HRA comprising a BN-causal model suitable for use with legacy PRA methods and tools, and the computational tools for its integration. | Document | Licensing and Safety | FY2023 |
| An Integrated Elemental and Isotopic Detector for Real-Time Molten Salt Monitoring | North Carolina State University | $1,000,000 | The overarching theme of the proposed research is to develop and demonstrate a real-time elemental and isotopic detector of molten salts for advanced reactors and fuel fabrication and recycling processes. The detector's longevity, limits, and latency will be tested in static uranium chloride salts, in pyroprocessing chloride salt, and on flowing fluoride salt with evolving actinide composition, respectively. | Document | Licensing and Safety | FY2023 |
| Development of a Thin-Layer Electrochemical Sensor for Molten Salt Reactors and Fuel Cycle Processes | Brigham Young University | $811,755 | A thin-layer electrochemical sensor capable of detecting uranium, plutonium and other species of interest in molten salts, at both high and low concentrations, will be developed for application in molten salt reactors and fuel cycle process units. This will provide a valuable tool for performing material control and accountancy measurements. | Document | Licensing and Safety | FY2023 |
| Risk-Informed Consequence-Driven Hybrid Cyber-Physical Protection System Security Optimization for Advanced Reactor Sites | Georgia Institute of Technology | $1,000,000 | This project aims to develop an expanded methodology for designing a novel cybersecurity-integrated physical protection system (PPS) framework for advanced reactor concepts that serves to reduce the operational costs for the life of a reactor against that of a traditional light water reactor PPS design, promoting efforts to credit safety features of advanced reactors through proposed amendments to current security regulations, while integrating health and economic consequence analyses. | Document | Licensing and Safety | FY2023 |
| A risk analysis framework for evaluating the safety, reliability, and economic implications of electrolysis for hydrogen production at NPPs | University of Maryland, College Park | $1,000,000 | The RAFELHyP project will develop a modular risk analysis framework that enables evaluating the safety, reliability, and economic implications of upcoming deployments of electrolyzers to produce hydrogen at nuclear power plants. The framework will be implemented to conduct an integrated safety, reliability, and economic analysis of multiple plant configurations to provide detailed recommendations for plant protective features and layouts. | Document | Licensing and Safety | FY2023 |
| Reduced Order Modeling of Heat and Fluid Flow: Multi-Scale Modeling of Advanced Reactors to Enable Faster Deployment | University of Illinois at Urbana-Champaign | $1,000,000 | Novel multi-scale algorithms for thermal-hydraulics (TH) simulations of advanced reactors will be developed. The methods will leverage recent advances in hardware and reduced order modeling approaches to enable TH simulations of vastly accelerated speed, while maintaining accuracy comparable to high-fidelity methods, such as large-eddy simulation. The methods will allow designers to perform parameter sweeps, develop closures, and enable high fidelity simulation of transients. | Document | Modeling and Simulation | FY2023 |
| Embedded Monte Carlo | Massachusetts Institute of Technology | $1,000,000 | Monte Carlo methods have long been considered the standard in terms of accuracy and have seen increased use in design of small nuclear systems; however, the uncertainty quantification (UQ) of the desired output is often relegated to later stages of the design process. This project seeks to embed nuclear data UQ in a single Monte Carlo simulation, such that each desired quantity will not only provide the mean value and statistical uncertainty, but also the related nuclear data uncertainty. | Document | Modeling and Simulation | FY2023 |
| A Low Order Transport Method Based on the Dynamic Truncation of the Integral Transport Matrix Method (ITMM) that Converges to the SN Solution with Increasing Cell Optical Thickness | North Carolina State University | $1,000,000 | A novel low-order transport operator capable of approximating Monte Carlo (MC) results within a variance range will be developed. This does not require MC reference solutions to calibrate the low-order model, so repeated solutions of the latter in-transient scenarios does not require repeated MC simulations. Truncation of the low-order operator is done dynamically for evolving configurations to ensure accuracy of the low-order solution. This will involve proof of principle on Cartesian meshes, then implementation in Griffin. | Document | Modeling and Simulation | FY2023 |
| CFD based Critical Heat Flux predictions for enhanced DNBR margin | Massachusetts Institute of Technology | $1,000,000 | This project seeks to demonstrate a robust high-fidelity CFD-based methodology to predict CHF behavior at varying quality conditions, enabling the development of advanced DNBR correlations with reduced uncertainty, and in support of upgraded plant economics. The availability of a virtual CHF methodology will allow greatly extending the database for DNBR correlations development and further support advancement in the design of high-performing nuclear fuel. | Document | Modeling and Simulation | FY2023 |
| Immersed Boundary Methods for Modeling of Complex Geometry: A Leap Forward in Multiscale Modeling using NekRS | University of Illinois at Urbana-Champaign | $1,000,000 | A major challenge to Computational Fluid Dynamics (CFD) modeling of complex geometries is the need to generate body-fitted meshes, which can occupy 80% of the CFD practitioner's time. Immersed boundary methods will be added in the NekRS CFD code, dramatically simplifying modeling of complex 3-D structures and facilitating a new paradigm for CFD-informed multiscale analysis. This will be demonstrated by informing SAM transient systems-level models with NekRS heat exchanger correlations for advanced reactors. | Document | Modeling and Simulation | FY2023 |
| Uncertainty Quantification of Model Extrapolation in Neural Network-informed Turbulent Closures for Plenum Mixing in HTGRs | Utah State University | $1,000,000 | This project will quantify the uncertainty in prediction of Neural Network-informed Turbulent Closures when they are operating in a model extrapolation state. Once the method is developed for canonical buoyant jets, the protocols will be applied to plenum mixing in HTGRs. | Document | Modeling and Simulation | FY2023 |
| Impact of moisture on corrosion of NiCr alloys in MgCl2-NaCl Salt Systems | University of Wisconsin-Madison | $999,983 | This project aims to gain a fundamental understanding of the impact of moisture and salt chemistry on corrosion of NiCr alloys in molten chloride salts. A novel approach coupling multiscale simulations and experiments will be designed to determine salt acidity, its dependence on salt composition (i.e., the NaCl to MgCl2 ratio), and its effects on the transport of H2O and Cr ions and the corrosion kinetics of NiCr alloys in chloride salt. | Document | Reactor Development and Plant Optimization | FY2023 |
| Transforming Microreactor Economics Through Hydride Moderator Enabled Neutron Economy | State University of New York, Stony Brook | $1,000,000 | Microreactors will potentially require the cost of electricity to be 10 MWD/kg at >3 kW/kg core specific power. These goals are best achieved through a well-thermalized spectrum. Neutron economy as a core material selection criterion to advance entrained hydride composite moderators will be used with the primary goal of significantly reducing fuel costs through novel microreactor designs. | Document | Reactor Development and Plant Optimization | FY2023 |
| Integrating Nuclear with ZLD Seawater Desalination and Mining | University of Wisconsin-Madison | $1,000,000 | An integrated nuclear system will be developed that would utilize electricity and waste heat to operate a desalination and mining process from adjacent seawater. The desalination approach targets zero-liquid discharge with multiple marketable minerals extracted. The ability of nuclear facilities to load follow is increasingly important, so a cold thermal storage system will be incorporated. The desalination and mineral extraction process will be experimentally validated at lab scale. | Document | Reactor Development and Plant Optimization | FY2023 |
| Reference Designs of Green Ammonia Plants Powered by Small Modular Reactors | Utah State University | $1,000,000 | The overarching goal of this project is to develop two reference designs for green ammonia plants. One design uses freshwater as the source for hydrogen, while the other design uses seawater (or brackish water) as the source. In both designs, a small modular reactor (SMR) is used as the primary energy source providing both electricity and steam for the plants. | Document | Reactor Development and Plant Optimization | FY2023 |
| Development of the Technical Bases to Support Flexible Siting of Microreactors based on Right-Sized Emergency Planning Zones | Pennsylvania State University | $1,000,000 | The objective of this project is to provide the technical basis to support the application of a right-sized Emergency Planning Zone (EPZ) size to support the deployment of a microreactor at the Penn State University Park campus. This research study will serve as a template to provide flexible siting in support of future microreactor deployments that may be placed closer to demand centers, thereby making them more economically competitive. | Document | Reactor Development and Plant Optimization | FY2023 |
| Bayesian Optimization for Automatic Reactor Design Optimization | Arizona State University | $1,000,000 | The objective of this project is to develop analytical tools based on Gaussian process modeling and Bayesian Optimization that facilitate reactor design optimization by modeling the responses from the physics simulator. Existing capabilities will be applied in an AI field and they will be adapted to address the key characteristics of nuclear reactor design problem. This project will automate the simulation-based design procedure, reduce the number of iterations, and minimize the design cycle time. | Document | Reactor Development and Plant Optimization | FY2023 |
| A Pathway for Implementation of Advanced Fuel Technologies in Light Water Small Modular Reactors | Texas A&M University | $1,000,000 | A comprehensive characterization of the performance of the Lightbridge Helical Cruciform advanced fuel design will be performed, which will generate unique sets of experimental data of friction factor, flow and heat transfer behavior under NuScale's LW-SMR simulated normal and off-normal conditions. The project will accelerate the deployment of advanced fuels for LW-SMR applications by leveraging the use of existing testing infrastructures. | Document | Reactor Development and Plant Optimization | FY2023 |
| Engaging New Mexican communities in developing an equitable and just approach to siting advanced reactor facilities | University of Michigan | $1,000,000 | This project will engage diverse New Mexican communities to develop an equitable approach for advanced reactor siting. The findings of this project will shed light on how technology developers and the DOE can explore and potentially site advanced reactors with the informed consent and engagement of host communities, regions, and states. The findings of this study will also more generally apply to the potential for equitably exploring both brownfield and greenfield sites for nuclear facilities. | Document | Reactor Development and Plant Optimization | FY2023 |
| Deciphering Irradiation Effects of YHx through In-situ Evaluation and Micromechanics for Microreactor Applications | University of New Mexico | $998,000 | This project addresses a critical gap in accelerated testing of YH evolution coupling multi-length scale mechanical testing with ion irradiation and advanced characterization to establish a baseline understanding of YH evolution under ion irradiation. Our approach will couple ion irradiation and gamma irradiation with small scale mechanical testing to decipher multi-scale impacts on phase stability to advance understanding of YH in a microreactor moderator application. | Document | Reactor Development and Plant Optimization | FY2023 |
| Active Learning Estimation and Optimization (ALEO) of Irradiation Experimental Design for Efficient Accelerated Fuel Qualification | University of Texas at San Antonio | $997,247 | This collaborative project creates novel AI/ML models and algorithms integrated with physical knowledge and expertise to explore more efficient ways to calculate irradiation temperatures and fuel specimen burnups for new fuel sample configurations of MiniFuel experiments proposed for irradiation in the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL). | Document | Reactor Development and Plant Optimization | FY2023 |
| Unraveling how mixing vane spacers affect cladding-to-coolant heat transfer phenomena in light water reactors | Massachusetts Institute of Technology | $500,000 | Experiments will be conducted to quantify the effect of mixing vane spacers on cladding-to-coolant heat transfer phenomena, namely single-phase forced convection, nucleate boiling, and CHF. The results of the experimental research will allow elucidating the physical phenomena triggered by the presence of mixing vane spacers. They will also allow assessing the performance of M-CFD tools developed within CASL and in use by the nuclear community. | Document | Strategic Needs Blue Sky | FY2023 |
| Quantum Computing Algorithms for Deterministic Neutron Transport | University of Michigan | $500,000 | This project will develop algorithms for solving the k-eigenvalue form of the neutron transport equation in a nuclear reactor physics context on a quantum computer. The asymptotic scaling of the algorithms will be analyzed. Investigation into implementation will be made by making resource estimates by synthesizing explicit circuits for the algorithms and be studied by emulation on a classical computer. | Document | Strategic Needs Blue Sky | FY2023 |
| Optimizing Application-Dependent Energy Group Structures for Multigroup Neutron Transport Models using Machine Learning | Colorado School of Mines | $500,000 | Machine Learning methods will be developed that will dramatically reduce both the computational run-time and manual effort needed to find multigroup energy structures that accurately capture the underlying physics of neutron reactions, while allowing multigroup simulations to run quickly without overwhelming available memory. | Document | Strategic Needs Blue Sky | FY2023 |
| Functionally-graded Cermet Coatings for Molten Salt Technologies by High Throughput Finite Element Modeling and Additive Manufacturing | Rensselaer Polytechnic Institute | $500,000 | This project proposes an integrated approach/methodology to design, manufacture and verify functionally-graded metal-ceramic composite coatings on structural alloys with desired interfacial properties, capabilities of mitigating residual stress and improved corrosion resistance for molten salt reactor applications. | Crosscutting Technologies | FY2022 | |
| An Innovative Monitoring Technology for the Reactor Vessel of Micro-HTGR | Texas A&M University | $800,000 | This project seeks to develop an innovative sensor technology for real-time monitoring of the thermo-mechanical stresses in the reactor vessel of micro-HTGR. The technology will be based on a sparse network of outer wall temperature measurements and plant operating conditions. An integrated software-hardware sensing system aimed at monitoring the health of the pressure vessel of gas micro-reactors will be implemented and tested. The proposed work will have a broad impact on sensing in other reactor designs. | Crosscutting Technologies | FY2022 | |
| High throughput mechanical testing of additively-manufactured materials | University of California, Berkeley | $500,000 | This project proposes fast and high throughput mechanical testing of AM produced materials. It will include the generation of automated tensile testing, hardness testing and microstructure assessment and data comparison to build data via machine learning. | Crosscutting Technologies | FY2022 | |
| Accelerated irradiation creep testing coupled with self-adaptive accelerated molecular dynamics simulations for scalability analysis | University of Michigan | $500,000 | The goal of the proposed work is to accelerate traditional irradiation creep using instrumented in-situ ion irradiation creep and long-time molecular dynamics simulations to accelerate traditional neutron irradiation creep testing. This goal will be accomplished by coupling a novel ion beam flux jump test using tapered creep specimens and self-adaptive accelerated molecular dynamics. The outcome is a rapid, low-cost accelerated method to determine the fundamental irradiation creep mechanisms. | Crosscutting Technologies | FY2022 | |
| Creation of a Pebble Database for Material Control and Accountancy in Pebble Bed Reactors | Virginia Commonwealth University | $399,969 | The primary goal of this proposed project is to develop a database of NDA signatures from a wide variety of used PBR pebbles. This database can be used for facility operations, safety, security, and safeguards (3S) to directly measure fission product content and indirectly 235U and plutonium content of each PBR pebble. This project has significant synergy with current 3S PBR research at ANL, BNL, and ORNL, all of whom are collaborators to this proposed project. | Crosscutting Technologies | FY2022 | |
| Integrated Marine Platform for Hydrogen and Ammonia Production | Massachusetts Institute of Technology | $800,000 | This study investigates the economic and environmental value of a floating integrated GW-scale green hydrogen/ammonia production facility powered by an advanced nuclear reactor. Floating Production Storage and Offloading units (FPSOs) are deployed worldwide in the oil and gas industry, and can be used for hydrogen and ammonia processing. Deployment of an advanced reactor on a floating platform offers several advantages, including the efficiencies of shipyard fabrication. | Crosscutting Technologies | FY2022 | |
| Quantifying Aerosol Deposition Mechanisms in Model Dry Cask Storage Systems | Clemson University | $800,000 | The objective of this work is to measure aerosol deposition and resuspension rates in laboratory models of dry cask storage systems to compare with and validate the DOE deposition model. The project team will conduct experiments to directly measure the deposition/resuspension rates of bulk aerosol in the system and to isolate and quantify individual aerosol deposition mechanisms, with a focus on those sensitive to variable humidity and surface temperature. | Fuel Cycle R&D | FY2022 | |
| Using Amide-Functionalized Electrodes to Elucidate Interfacial Actinide Redox Chemistry for Improved HALEU Supply | Florida International University | $400,000 | The goal is to decrease HALEU fuel cycle costs by examination of the redox behavior of U, Np, and Pu at the water-organic interface using amide functionalized electrodes, and in organic media after extraction with amides. Experiments with redox active interferences including additional actinides in different oxidation states will also be conducted. | Fuel Cycle R&D | FY2022 | |
| Advancing the technical readiness of FeCrAl alloys and ODS steels under extreme conditions for fast reactor fuel cladding | North Carolina State University | $800,000 | A key technology gap for advanced high-performance fuel applications is the current unavailability of materials that can withstand extremely high doses without significant degradation of cladding performance. The project team will perform in-situ thermo-mechanical experiments (tension, torsion, creep, and creep-fatigue and nanoindentation) on ion-irradiated (to 400 dpa) cladding materials (up to 700 C) along with microstructures using TEM and mesoscale phase field simulations. | Fuel Cycle R&D | FY2022 | |
| A molten salt community framework for predictive modeling of critical characteristics | Pennsylvania State University | $400,000 | This research aims to develop a molten salt community framework to address the needs in advanced fuel cycles, including understanding salts via new theory of liquids, predicting salt characteristics via simulations (DFT, MD, and CALPHAD by implementing advanced models), optimizing inversely molten salts, and verifying simulations by experiments. This project has outstanding value for US taxpayers, educates students, and delivers outreach opportunities for academia, industry, and the public. | Fuel Cycle R&D | FY2022 | |
| Understanding the Interfacial Structure of the Molten Chloride Salts by in-situ Electrocapillarity and Resonant Soft X-ray Scattering (RSoXS) | Pennsylvania State University | $400,000 | The objective of the proposed research is to investigate the interplay between the interfacial structure of the molten salts and their electrochemical corrosion properties in Molten Salt Reactors (MSRs). | Fuel Cycle R&D | FY2022 | |
| Clay Hydration, Drying, and Cracking in Nuclear Waste Repositories | Princeton University | $800,000 | This project will develop a new multiscale model of the thermal-hydrologic-mechanical-chemical (THMC) evolution of an engineered clay barrier in the near field of a nuclear waste repository, including initial hydration and eventual post-closure criticality. This new model will directly link micro-scale material properties to large-scale barrier performance, thus facilitating future design advances or modifications, and enable robust validation of large-scale simulation predictions. | Fuel Cycle R&D | FY2022 | |
| Physics-guided Smart Scaling Methodology for Accelerated Fuel Testing | Purdue University | $800,000 | This project proposes to employ novel informatics algorithms for mapping/scaling uncertainties from experimentally accessible scaled state to application/prototypical state, informed by an equivalent mapping obtained from high-fidelity multi-physics simulations for the fuel thermo-mechanical behavior, specifically, a rate theory-based model for thermal conductivity and fission gas behavior in the BISON code, and employing relevant HALDEN reactor and FAST experiments. | Fuel Cycle R&D | FY2022 | |
| Materials Accountancy During Disposal and Waste Processing of Molten Salt Reactor Fuel Salts | Texas A&M University | $399,997 | The objective of this work is to develop and validate a method for measuring and predicting hold-up to eliminate operational risks and expenses during disposal of salt-wetted MSR components. These objectives will be met by applying robust measurement/detection methods to realistic salt loop environments to validate their use in decommissioning MSRs. | Fuel Cycle R&D | FY2022 | |
| Advanced Screening Approaches for Accelerating Development of Separations Technologies | University of California, Berkeley | $400,000 | The goal of this project is to establish a unified selection criterion for chelating molecular structures to more efficiently address ligand applicability to metal ion separation problems, for current and future nuclear fuel cycles. By establishing this criterion, the team will seek to enable the accelerated, cost-effective discovery of new separation workflows, as well as their implementation beyond early radiotracer experiments. | Fuel Cycle R&D | FY2022 | |
| Advancing NMA of TRISO-fueled pebbles using fast and accurate gamma-ray spectroscopy | University of Colorado, Boulder | $385,307 | This proposal will provide new Nuclear Materials Analysis (NMA) capabilities for TRISO-fueled pebbles using gamma-ray spectroscopy, through a program of simulations of expected signatures from irradiated pebbles, resulting in a detailed measurement plan to monitor burnup and actinide content throughout the fuel cycle. These simulations will be used to develop requirements for NMA sensor technology and identify opportunities for focused technology development to meet these requirements. | Fuel Cycle R&D | FY2022 | |
| Development of Irradiation and Creep Resistant High-Cr Ferritic/Martensitic Steels via Magnetic Field Heat Treatment | University of Kentucky | $800,000 | The objective of this proposed study is to develop and test new generation of Ferritic/Martensitic (F/M) steels specifically designed for advanced reactors that will exceed the current limitations due to temperature and irradiation dose. To achieve this objective, a systematic study is proposed to employ an innovative tempering heat treatment under high external magnetic field (up to 9T) on F/M steel HT9 to engineer an optimized microstructure composed of refined carbides and martensite laths. | Fuel Cycle R&D | FY2022 | |
| Investigation into the processing parameters of phosphate-based dehalogenation for chloride-based waste salt | University of Nevada, Reno | $399,999 | This proposal will focus on several topics needed to advance the iron phosphate process: 1) Dehalogenation/vitrification processes using salt simulants to generate process flow sheets, 2) Reactions of crucible materials with phosphate products and byproducts, 3) Collection of glass property-composition data to develop models based on the glass-forming regions, 4) Development of a process for reacting recovered NH4Cl with metals that need to be fed into the system (U, Li, etc.). | Fuel Cycle R&D | FY2022 | |
| A Validated Framework for Seismic Risk Assessment of Spent Fuel Storage Facilities | University of Nevada, Reno | $799,883 | This is a collaborative research program with a primary objective of developing a validated numerical framework for seismic risk analysis of spent fuel storage facilities from the global cask behavior to the localized behavior of internal spent fuel assemblies. In building and validating this framework, advanced data analysis, data assimilation, and forward and inverse modeling techniques will be utilized. | Fuel Cycle R&D | FY2022 | |
| International Collaboration to Advance the Technical Readiness of High Uranium Density Fuels and Composites for Small Modular Reactors | University of Texas at San Antonio | $800,000 | An international team of high uranium density fuels (HDFs) experts advised by industry leaders in nuclear reactor innovation propose a US-UK collaboration to advance the technical readiness of UN, UB2, and their composites for fuel forms specific to small modular reactors (SMRs). The project will bridge the critical data gaps in HDF performance specific to the impact of common impurities and microstructural variations that originate at fabrication. | Fuel Cycle R&D | FY2022 | |
| Development of Advanced Control Rod Assembly for Improved Accident Tolerance and High Burnup Fuel Cycle | University of Wisconsin-Madison | $800,000 | Research will focus on the development of new materials' designs for control rod sheaths and neutron absorbers, coupled with neutronics analysis and thermo-mechanical modeling to improve accident tolerance and to achieve higher fuel burnup in PWRs. Functionality of the proposed designs consisting of Cr coated control rod sheaths of current and advanced alloys as well as novel neutron absorbers will be evaluated in prototypical reactor conditions and accident scenarios. | Fuel Cycle R&D | FY2022 | |
| Optical Basicity Determination of Molten Fluoride Salts and its Influence on Structural Material Corrosion | University of Wisconsin-Madison | $400,000 | The proposed research is aimed at developing ion probes to determine the optical basicity of molten fluoride salts and studying its influence on structural material corrosion. Combining with the molten salt structure study using X-ray absorption spectroscopy, the salt chemical constitution, the resulting optical basicity, and molten salt structure will be inextricably linked and their connections will be unveiled. | Fuel Cycle R&D | FY2022 | |
| Extending the HMF71 Benchmark Series for Graphite Reflector Thickness up to 18 Inches | University of Tennessee at Knoxville | $399,522 | The objective of this proposal is to extend the HEU-MET-FAST-071 (HMF-71) experiment benchmark series in ICSBEP by evaluating the historical (existing) experimental data for critical experiments with graphite reflector thickness from 3 inches up to 18 inches. | Nuclear Energy | FY2022 | |
| Fast and Rigorous Methods for Multiphysics SPn Transport in Advanced Reactors | University of Michigan | $600,000 | This project proposes to perform rigorous theoretical and numerical analysis of the Generalized SPn method and underlying cross section models to enable a fast and robust multiphysics low-order transport capability for advanced reactors. This includes 5 major tasks focused on the efficient discretization and solution of the GSPn equations, numerical analysis of XS models having multiphysics and depletion, analysis of equivalence factors, improved MC estimators, and several V&V applications of the methods. | NEAMS | FY2022 | |
| Development of Hydrogen Transport Models for High Temperature Metal Hydride Moderators | Colorado School of Mines | $800,000 | Understanding the transient behavior of metal hydride moderator materials at high temperatures is a key challenge to the design and deployment of future microreactors. This project will use neutron radiography techniques provide the necessary data for this understanding and demonstrate the development of time and temperature dependent hydrogen transport models using both commercial FEA software coupled to MCNP and coupled models developed in the MOOSE framework. | RCRD&D | FY2022 | |
| Characterizing fast reactor fuel failure mode through separate effect and prototypic tests | Oregon State University | $800,000 | The project consists of conducting separate effect fuel pin failure tests with surrogate fluid and prototypic test with sodium. The outcome of this study will generate an experimental database that will be used to develop mechanistic model and validate the CDAP module of the SAS4A/SASSYS-1 code. Ultimately the quality data can be used to benchmark other fuel codes developed for LMFR application, which are seeking validation for licensing purpose. | RCRD&D | FY2022 | |
| Science-based development of ASTM standard tests for graphite-based fuel pebbles | University of California, Berkeley | $700,000 | This project proposes the development of mechanical test procedures as well as wear and friction tests on Graphite fuel pebbles | RCRD&D | FY2022 | |
| Role of Heterogeneity in Manganese and Nickel Rich Precipitate Distribution on Hardening of Reactor Pressure Vessel Steels: Integrated Modeling and Experimental Characterization | University of Florida | $799,803 | The hypothesis of this work is that the different nucleation and coarsening kinetics of manganese and nickel rich precipitates (MNPs) compared to copper rich precipitates, and the heterogeneous distribution of manganese and nickel rich precipitates on or near dislocations, both lead to unique hardening behavior at high neutron fluence. The objective of this work is to understand hardening in reactor pressure vessel steels caused by MNPs via integrated multiscale modeling and experiments. | RCRD&D | FY2022 | |
| Integrated Thermal-Electric Energy Management of All-Electric Ship with Advanced Nuclear Reactors | University of Texas at Dallas | $400,000 | The overall objective of this research is to comprehensively model, design, and evaluate the use of advanced nuclear reactors in future nuclear-powered ships, to enhance the efficiency, reliability, and resilience of shipboard energy distribution systems. The novelty of the proposed approach lies in (i) integrated thermal-electric modeling of advanced nuclear-powered shipboard energy system, and (ii) novel solutions for total-ship energy management to improve energy efficiency and resiliency. | RCRD&D | FY2022 | |
| Open Architecture for Nuclear Cost Reduction | University of Wisconsin-Madison | $800,000 | Open architecture has potential to reduce advanced reactor (AR) costs, through exploiting modular design and construction, with common, openly available interfaces between modules. A comprehensive assessment of the challenges and opportunities of open architecture for ARs will be performed. Supported by a pilot study, actionable recommendations for the implementation or otherwise of open architecture for ARs will be developed. | RCRD&D | FY2022 | |
| Telescopic Control Rod for Significant Reduction in HTR Height and therefore Cost | University of Wisconsin-Madison | $800,000 | This project proposes a design for a small modular High Temperature Reactor (HTR) control rod that extends telescopically, consisting of ~5 concentric annuli that nest together above the core when withdrawn. This compact component substantially reduces the length of the depth of the silo. Modelling and experimental testing will be performed to develop the control rod to evaluate feasibility, plus perform a cost-benefit analysis, with a view to its inclusion in both pebble bed and prismatic HTR designs. | RCRD&D | FY2022 | |
| NEUP Project 21-24394: Computer vision and machine learning for microstructural qualification | Carnegie Mellon University | $497,518 | Quantifying and understanding microstructure is a key driver for performance-based materials qualification. In this proposal, well-curated data sets of microstructural images will be gathered and computer vision and machine learning will be applied to build quantitative deep learning frameworks to accelerate and enable qualification of nuclear materials based on microstructural features. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-24156: Experimental thermofluidic validation of TCR fuel elements using distributed temperature and flow sensing | Kansas State University | $798,250 | The overall goal of this project will be to test the performance of 3D printed Transformational Challenge Reactor core geometry parts using existing Helium flow loops and distributed temperature, and velocity sensing systems. Thermal transport capabilities of scaled 3D printed ceramic core will be evaluated experimentally and measurements will be used to qualify computational models. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-24636: Risk-informed Consequence-driven Physical Protection System Optimization for Microreactor Sites | Texas A&M University | $400,000 | This proposed project will utilize a risk-informed, consequence-driven analysis to develop an approach for "right-sizing" physical protection systems (PPS) for microreactors. The hypothesis presented for this proposal is that the explicit coupling of consequence modeling to PPS design will provide a similar benefit that can be applied prior to reactor construction. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-24131: Total Mass Accounting in Advanced Liquid Fueled Reactors | The Ohio State University | $400,000 | A total mass determination method for nuclear materials accounting (NMA) in liquid-fueled molten salt reactors will be validated with fuel-bearing salt, mixed with a + radioisotope of known activity, that will be irradiated to reproduce the practical NMA scenario in a molten salt loop. Irradiated fuel salt will be sampled and measured for its mass and activity. The mass-to-activity ratio will be used to calculate the unknown salt mass in the original container. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-24037: Design and intelligent optimization of the thermal storage and energy distribution for the TerraPower Molten Chloride Fast Reactor in an Integrated Energy System (IES) | University of Tennessee at Knoxville | $800,000 | The objective of this project is to explore the application of advanced reactors within Integrated Energy Systems, use extensive existing data from UIUC for model development and validation, and extend the predictions to larger grids and commercial applications. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-24522: Targeted Materials Characterization and Testing of Additively Manufactured Metals and Ceramics to Inform Print/Build Data Analytics | University of Texas at San Antonio | $800,000 | A collaborative program between the University of Texas at San Antonio and Boise State University is proposed to supply materials testing and characterization data sets to be leveraged by the TCR program to inform build/print data analytics. With the data provided by the proposing team, correlations among steam oxidation performance, micromechanical properties, chemical composition, local microstructure, and location specific print/build data will be achieved. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-24431: Location-specific material characterization of LPBF SS316L & IN718 TCR core structural materials | Utah State University | $800,000 | In this proposed work, we will experimentally characterize the spatial variability of the quasi-static (tensile), creep (strength and impression), and creep-fatigue properties as well as the underlying structures (microstructure and defect structures) for LPBF SS316L and IN718 components to be used as training data to the TCR program data-driven model. The resulting correlation will be used to drive the design process for an application as TCR core structural materials. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-23978: Rapid, Non-Radioactive Methods for Prediction and Quantification of Radiolytic Radical Decomposition Products in Nuclear Separations | Clemson University | $399,999 | High-throughput, non-radioactive, radical assays will be used to determine decomposition of monoamide separations complexants. Radical assay results will be correlated with classic radiolytic damage results to develop predictive models for screening complexant stability. These models will aid in single-stage separations complexant optimization, in the transition from lab-to industrial-scale nuclear waste separations and, ultimately, could yield field tests for radiolytic damage. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24350: Phosphate Mineral and Glass Waste Forms for Advanced Immobilization of Chloride and Fluoride-based Waste Streams | Clemson University | $600,000 | This proposal is intended to develop three waste form options for immobilizing the fluoride-and chloride-salt waste stream in highly durable and easily processable phosphate minerals and glasses, including phosphate apatite ceramic waste forms, phosphate glass waste forms, and phosphate glass-ceramic waste forms with apatite phase. Multiple monolithic waste form samples will be provided to DOE national laboratories for further testing. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24292: Passive multimodal tomography for dry storage casks imaging using passive neutron and gamma dosimetry and cosmic ray muons | Colorado School of Mines | $800,000 | A method for multimodal tomography of dry storage casks will be developed to determine fuel relocation and cladding failures using passive neutrons and gamma emissions in combination with cosmic ray muons. The use of multimodal imaging will allow 3-D reconstructions of the dry storage cask that would be unachievable with any single radiation source. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24374: Effects of Radiolysis on Pertechnetate under Solvent Extraction Conditions, including Tri-Butyl Phosphate | CUNY, Hunter College | $399,624 | The overarching objective of the proposed work is to assess the impact of radiolysis on pertechnetate speciation during tri-butylphosphate (TBP) solvent extractions from the molecular level to macroscale. The research in this project is designed to understand the interplay of radiolysis, degradation product formation, other important redox active metals, and oxidation states of technetium on its speciation and distribution coefficients in solvent extraction processes. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24183: Experimental investigation and development of models and correlations for cladding-to-coolant heat transfer phenomena in transient conditions in support of TREAT and the LWR fleet. | Massachusetts Institute of Technology | $800,000 | Thermal-hydraulics transient heat transfer phenomena of relevance for the safety and the operation of the TREAT and light water reactors will be investigated. The performance of accident tolerant fuel materials during a reactivity initiated accident scenario and post-critical heat flux and reflood scenarios will be elucidated, as well as the development of models and correlations to be integrated into computational tools for the design and safety analysis of nuclear systems. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24666: Wireless Multifunctional Ultrasonic Arrays with Interdigital and Airborne Transducers for Monitoring Leakage and Corrosion Conditions of Welded Dry Storage Canisters | Mississippi State University | $800,000 | This project aims to develop and validate wireless, multifunctional, ultrasonic sensor arrays that enable on-demand, quantitative interrogation and real-time monitoring of both the canister leakage indicators (helium, helium/air mixture, internal pressure, and temperature) and corrosion conditions (free and/or vapor water). The developed arrays will be fully functional, wirelessly powered and communicated, and compact. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24188: Uranium recovery from used nuclear fuel using metal sulfides | Northwestern University | $400,000 | An alternative and original method to recover uranium from spent fuel is proposed. This method will utilize a new type of regenerable sorbent materials with high selectivity in capturing uranium from complex mixtures in acidic solutions, such as those found in used nuclear fuel of high-assay low-enriched uranium. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24225: Characterizing Fuel Response and Quantifying Coolable Geometry of High-Burnup Fuel | Oregon State University | $800,000 | This study seeks to objectively determine, through empirical and numerical means, the actual impact of fuel dispersion in-core after fuel failure and whether high burnup dispersed fuel compromises coolable geometry and long-term cooling. The outcome of this study will yield an objective means of assessing two criteria (coolable geometry and long-term cooling) within the existing regulatory process to comprehensively understand whether it is feasible to increase burnup, while satisfying 10 CFR 50.46. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24288: Innovative Methods for Interrogation of DSC Internal Conditions | Oregon State University | $800,000 | The proposed work takes a two-pronged approach. The team will study techniques involving only external sensors and equipment, which could be deployed on existing dry storage canisters. In addition, small sensors located inside the canister that can be externally powered and read through the canister wall will also be investigated. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24439: Development of Novel Corrosion-Responsive Buffer Materials for Long-Term Immobilization of High-Level Nuclear Waste | Pennsylvania State University | $800,000 | The goal of this project is to develop a novel cementitious buffer material (CBM) for the safe disposal of spent nuclear fuel (SNF). The primary aim is to identify and characterize novel Mg-Al-P CBMs, complete with assessments of their repository stability as well as their transport and immobilization of radionuclides. The secondary aim is to use in-situ UT-EIS monitoring to understand the corrosive failure at the canister-CBM interface and provide long-term performance modeling of SNF packages. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24461: Estimation of low temperature cladding failures during an RIA transient | Pennsylvania State University | $800,000 | Researchers aim to create a multiphysics description of cladding response during a RIA, especially at high burnup, coupling reactor physics, thermal hydraulics and mechanics. The creation of a thermomechanical model in Bison will be the result of this project which can be used to evaluate the likelihood of low temperature cladding failures during a postulated RIA on a typical fuel rod (as these can lead to channel blockage), and thus identify the most important conditions to be studied at TREAT. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24460: Multiscale Modeling and Experiments for Investigating High Burnup LWR Fuel Rod Behavior Under Normal and Transient Conditions | Texas A&M University | $800,000 | The main objective of this work is to achieve a mechanistic understanding of and to develop a predictive model for the fuel rod behavior at high burn-up under both normal and transient conditions. Therefore, this study will provide the nuclear industry with validated, physics-based criteria to fuel fragmentation thresholds and rod mechanical integrity limits. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24388: Redox Chemistry of UO2 under Repository Relevant Conditions in the Presence of Zircaloy and Waste Canister Material | University of California, Irvine | $800,000 | This project will seek to improve understanding of spent nuclear fuel (SNF) corrosion. Hydrothermal experiments of SNF with cladding and waste canister material will give insights into the redox potential formed due to secondary phase formation as consequence of corrosion in a failed canister. The experimentally derived data about secondary phase formation will be utilized for phase relationship analysis to decipher the redox conditions and thus provide source term for performance assessment models of deep geologic repositories. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24006: High-fidelity modeling of fuel-to-coolant thermomechanical transport behaviors under transient conditions | University of Florida | $800,000 | The objective of the proposal is to develop a high-fidelity modeling tool that can capture some of the important phenomena in high burnup UO2 and ATF fuels during transient conditions. The BlueCRAB tool set will be improved and used to analyze TREAT loss of coolant accident experimental results. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24312: Accelerating the development of reliable and robust machine learning-based interatomic potentials for the prediction of molten salt structure and properties | University of Massachusetts Lowell | $400,000 | Machine learning-based interatomic potentials (MLIPs) used in molecular dynamics (MD) can accurately and efficiently predict molten salt properties. However many machine learning-based methods require large training sets, and can fail unpredictably. This project will overcome these challenges by developing a method for efficiently sampling diverse configurations from MD to train reliable and robust neural network potentials, and develop new models for predicting errors in MLIPs. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24697: Dual External Leak Sensing and Monitoring for Dry Storage Canister | University of Nebraska, Lincoln | $800,000 | Researchers aim to develop two complementary external sensing methods to evaluate the integrity of DSC through internal pressure monitoring and helium leakage detection. The proposed diffuse ultrasonic wave method will be able to measure biaxial strains in the canister wall with high sensitivity and minimum temperature effects. An innovative capacitance MEMS sensor will be developed for helium concentration measurement in air based on the extremely low permittivity of helium. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24449: Multi-modal Surface Acoustic Wave Sensing System for Pressure and Temperature monitoring of Spent Fuel Canisters | University of North Texas | $800,000 | University of North Texas (UNT) will collaborate with Oak Ridge National Laboratory (ORNL) and National Energy Technology Laboratory (NETL) to develop a multi-modal wireless passive SAW (Surface Acoustic Wave) sensor array, which are deployed on the outside surface of the canister, to monitor the strain of the canister and thus determine the inside pressure. In addition, the SAW strain sensor could also measure the surface temperature and potentially monitor helium gas leak. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24265: Fragmentation and Thermal Energy Transport of Cr-doped Fuels under Transient Conditions | University of Pittsburgh | $799,999 | This project will focus on multiple aspects of experimental testing and engineering-scale modeling in understanding thermal energy transport from high burnup, fractured/fragmented accident tolerant fuels, establishing a strong scientific basis to fill a critical knowledge data gap for modeling and simulation of transient fuel performance and safety, such as loss of coolant accident, for future integral testing and fuel licensing. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24310: Fusion of Distributed Fiber Optics, Acoustic NDE, and Physics-Based AI for Spent Fuel Monitoring | University of Pittsburgh | $800,000 | The proposal will leverage new concepts in the fusion between fiber optic distributed acoustic sensing and advanced acoustic nondestructive evaluation techniques with artificial intelligence enhanced classification frameworks to quantitatively characterize the state of dry cask storage containers for spent fuel monitoring, externally and non-invasively, without introducing additional risks of failure. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24261: Internal Wireless Sensors for Dry Cask Storage | University of South Carolina | $800,000 | The effort will test the reliability of wireless, internal sensors after exposure to drying and storage conditions. These sensors are used to internally monitor temperature, pressure, and dose. Radiation shielding will also be designed to protect sensors during long-term storage. The effort will develop piezoelectric techniques for miniaturization of optical emission spectroscopy for internal monitoring of gas composition during drying and long-term storage. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24533: Non-destructive Evaluation of Dry Storage Canisters Using Acoustic Sensing | University of Southern California | $800,000 | The objective of this project is to develop a robust non-destructive evaluation (NDE) technique based on acoustic sensing to detect impurity gases in a sealed (welded) dry storage canister (DSC) using only measurements collected on the external surface of the DSC. The method is based on the time-of-flight analysis of acoustic signals propagating through the fill gas of a DSC, which is influenced by the composition, density and temperature of the propagation medium. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-23984: Safety Implications of High Burnup Fuel for a 2-Year PWR Fuel Cycle | University of Tennessee at Knoxville | $800,000 | The objective of this project is to perform safety analysis of high burnup fuel for a Westinghouse 4-Loop Pressurized Water Reactor. The work aims to identify potential opportunities and gaps for high burnup fuel by utilizing both well-established and modern methodologies to model reactor physics, thermal-hydraulics, and plant system-level response that ultimately provide feedback to fuel performance analysis. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-23985: Fuel-to-Coolant Thermomechanical Behaviors Under Transient Conditions | University of Tennessee at Knoxville | $800,000 | This project will enhance the prediction of thermo-mechanical fuel-to-coolant heat transfer under transient conditions by using a coupled analysis and experiment approach. The effort is relevant to both high-burnup (> 62GWd/t) fuel applications and Accident Tolerant Fuel. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24070: Modeling high-burnup LWR fuel behavior under normal operating and transient conditions | University of Tennessee at Knoxville | $800,000 | This project aims to develop a high-burnup light water reactor fuel modeling capability to implement in the BISON code that would enable the accurate fuel rod behavior simulation during normal operation and design basis accidents, as wells as the identification of the rod life-limiting factors. Mechanistic engineering models will be developed for key phenomena, in particular, high burnup structure evolution, fuel fragmentation, and fission gas release. Traditional and accident tolerant fuels will be considered. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24033: Redox Chemistry in Nuclear Materials Storage Matrices under Ambient and Accelerated Aging Conditions | University of Washington | $800,000 | Deep geologic repositories must safely contain hazardous, high-activity nuclear wastes at geologic time-scales. However, such capability is centrally dependent on the element-specific redox chemistry within and at the interface of storage vessels. A comprehensive study of redox chemistry in cements used in long-term storage is proposed and emphasizes: 1) the actual consequences of accelerated aging modalities and 2) the novel use of newly available capabilities in advanced x-ray spectroscopies. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24063: Post-DNB Thermo-mechanical Behavior of Near-term ATF Designs in Simulated Transient Conditions | University of Wisconsin-Madison | $800,000 | The goals of the proposed research are to conduct coupled experimental and modeling investigations of thermo-mechanical performance of coated accident tolerant zirconium alloy claddings with simulated burnup doped fuels under thermal transients to predict complex thermal and mass transport phenomena of near-term Accident Tolerant Fuel designs in accident conditions. Experiments and modeling for understanding both cladding-coolant and fuel-coolant interactions will be performed. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24582: Machine-Learning-Accelerated Molecular Dynamics Approaches for Molten Salts | University of Wisconsin-Madison | $399,477 | New machine learning potential (MLP) approaches and new MLPs to enable rapid prediction of molten salt (FLiBe and Nal-MgCl2 with impurities) properties with near ab initio quantum mechanical accuracy will be developed. Uncertainty quantification with active learning and on-the-fly fitting will greatly accelerate MLP training. This work will support dramatically increased simulation speeds and associated data generation and understanding for molten salts. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24067: Development of Full Understanding of Mechanical-Chemical Coupling in Bentonite THMC processes | Virginia Polytechnic Institute and State University | $800,000 | The central hypothesis is that mechanical stress in an engineered barrier can lead to pressure solution of solid minerals, leading to significant changes in pore water chemistry, which affects bentonite stability, longevity of the waste pack, and dissolution and migration of nuclides. The overall objective of this project is to develop full understanding of the role of pressure solution on pore water chemistry, the implications to large-scale heterogeneity, and THMC processes. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24186: Regenerating Missing Experimental Parameters with Data-Assimilation Methods for MSRE Transient Benchmark Development and Evaluation | Virginia Commonwealth University | $400,000 | The proposed project will regenerate the undocumented basic data from available experimental data of the MSRE using advanced data-assimilation methods to facilitate the whole-loop modeling of the representative MSRE transients, and perform a thorough MSRE transient benchmark evaluation for the IRPhEP handbook. | Nuclear Energy | FY2021 | |
| NEUP Project 21-24630: Integral Benchmark Evaluation of Zero-Power Tests and Multi-Cycle Depletion Experimental Data of TVA WB1 Cycles 1-3 | North Carolina State University | $400,000 | This project proposes to develop an integral benchmark evaluation of available experimental data for zero-power tests and multi-cycle depletion for consistent and comprehensive validation of both novel high-fidelity and traditional multi-physics tools. The benchmark evaluation will be based on operational and measured data from the Pressurized Water Reactor Watts Bar Unit 1 released by Tennessee Valley Authority. | Nuclear Energy | FY2021 | |
| NEUP Project 21-23987: Separate and Multi-Physics Effects IRPhEP Benchmark Evaluation using SNAP Experiments | Georgia Institute of Technology | $400,000 | The proposed project will develop an International Reactor Physics Experiment Evaluation Project (IRPhEP) mulitphysics microreactor benchmark evaluation based on data from the Systems for Nuclear Auxiliary Power (SNAP) program. This work will include systematic assessments of the experimental data with meticulous compilation and documentation, and validation of specific NEAMS tools to model effects that are unique to microreactors technologies. | NEAMS | FY2021 | |
| NEUP Project 21-24194: Implementation of improved quasi-static, time-dependent, multi-physics methodology in Shift | Georgia Institute of Technology | $600,000 | A practical reference calculation route for time-dependent coupled Monte Carlo calculations, using Shift, will be developed. The proposed framework will be tailored to depletion and slowly varying transients, but with the flexibility to perform thermal-hydraulic time-dependent calculations with minimal computational overheads. This method relies on a hybrid-resolution stochastic approach in conjunction with a substep technique. | NEAMS | FY2021 | |
| NEUP Project 21-24078: Material transport model development and integration in the System Analysis Module (SAM) code | Rensselaer Polytechnic Institute | $400,000 | This project proposes to develop and implement models for System Analysis Module, which accurately characterize the sink, source, and interaction terms of key material species that are or may be present in various advanced reactor designs. | NEAMS | FY2021 | |
| NEUP Project 21-24195: Enhancing Yellowjacket for Modeling the Impact of Radiation and Stress on the Corrosion of Molten-Salt-Facing Structural Components | University of Florida | $692,088 | The objective of this project is to add the capability to model the impact of radiation and stress on corrosion to the Yellowjacket code, as well as to use Yellowjacket to create surrogate models that will be added to engineering-scale codes like Grizzly. We will also collect new experimental data for validation that quantifies the impact of stress and radiation on corrosion of 316 stainless steel in molten fluoride salts. | NEAMS | FY2021 | |
| NEUP Project 21-24405: Development of a High-fidelity Flow Boiling Database for Validation of High-void-fraction Flow Regime Models | University of Michigan | $800,000 | The primary objective of this proposed research is to develop a comprehensive, high-resolution, multiphase computational fluid dynamics validation-grade flow boiling data from rod bundle geometry simulating current light water reactor fuel designs by taking advantage of the instrumentation and facility developed by the research team. In addition, the applicability of the data through initial evaluations of selected test cases using Nek-2P boiling closure models will be studied and demonstrated for two-phase flow simulations. | NEAMS | FY2021 | |
| NEUP Project 21-24471: Technical Basis of Microstructure Criteria and Accelerated Testing for Qualifying Additively-manufactured 316H Stainless Steel for High-temperature Cyclic Service | Auburn University | $800,000 | This project seeks to reveal the fundamental relationship for AM 316H SS working at 500-750 C between additively-manufactured microstructures and creep/creep-fatigue properties through a multiscale experimental and modeling approach. The project also seeks to establish the technical basis for the microstructure criteria and accelerated testing method to support near-term nuclear qualification. | RCRD&D | FY2021 | |
| NEUP Project 21-24152: Direct heating of chemical catalysts for hydrogen and fertilizer production using Microreactors | Kansas State University | $799,202 | This proposal presents a novel integration approach to deliver process heat from microreactors by directly heating the catalyst particles from the primary heat transfer fluid in a moving packed bed heat exchanger (MPBHX). In this design, the tube side of the MPBHX can be a heat pipe or primary Helium coolant as in several microreactor designs. The shell side will be moving catalyst particles, which will enter the high temperature chemical reactor upon heating. | RCRD&D | FY2021 | |
| NEUP Project 21-24287: Investigating heat transfer in horizontally oriented HTGR under normal and PCC conditions | Kansas State University | $799,762 | Experimental research will be conducted to understand heat transfer inside the graphite matrix of horizontal microscale High Temperature Gas-cooled Reactors. Existing high temperature test facilities will be used to simulate normal operation and Pressurized Conduction Cooldown. The focus of these experiments is to generate benchmark data under forced and natural convection with coupled multi-mode heat transfer in scaled-down prismatic blocks. | RCRD&D | FY2021 | |
| NEUP Project 21-24104: Thermal Hydraulics Investigation of Horizontally Orientated Layout Micro HTGRs Under Normal Operation and PCC Conditions Using Integrated Advanced Measurement Techniques | Missouri University of Science and Technology | $800,000 | The proposed novel work will make a significant pioneering contribution to advance the knowledge and understanding of horizontal micro-high temperature gas cooled reactors. Quantification of metrics will pertain to convective heat transfer coefficients along the channel and gaps, comparative rates of convective and radiative heat transfer, location of peak temperature and its temporal variation, timescales for onset of natural convection, local gas velocity profiles, gas dispersion, crossflows, and temperature profiles over channel diameter and gap thickness. | RCRD&D | FY2021 | |
| NEUP Project 21-24004: An Open Source, Parallel, and Distributed Web-Based Probabilistic Risk Assessment Platform to Support Real Time Nuclear Power Plant Risk-Informed Operational Decisions | North Carolina State University | $800,000 | The main objective of the proposed work is to develop, demonstrate, and evaluate a probabilistic risk assessment (PRA) software platform needed to address the major challenges of the current legacy PRA tools. This includes better quantification speed, integration of multi-hazard models into traditional PRAs, and model modification/simplification and documentation automation. | RCRD&D | FY2021 | |
| NEUP Project 21-24228: Quantifying the Dynamic and Static Porosity/Microstructure Characteristics of Irradiated Graphite through Multi-technique Experiments and Mesoscale Modeling | North Carolina State University | $800,000 | This project proposes a joint experimental-computational approach to probe and quantify the porosity and microstructure characteristics of irradiated nuclear graphite grades and their influence on dimensional changes and turnaround behavior, as well as mechanical properties. The chief focus will be on quantifying both the static and dynamic porosity and crack characteristics in various graphitic phases through several experimental techniques. | RCRD&D | FY2021 | |
| NEUP Project 21-24247: Multi-scale Effects of Irradiation Damage on Nuclear Graphite Properties | Pennsylvania State University | $800,000 | Irradiation induces microstructural damage in graphite, causing both dimensional and property (stiffness, strength and creep) changes as a function of the displacement damage and temperature. The biggest gap remains is the fundamental deformation mechanisms behind the property changes. Researchers propose to eliminate this gap in knowledge with a comprehensive, multi-scale experimental framework exploiting in-situ transmission electron and X-ray computed tomography. | RCRD&D | FY2021 | |
| NEUP Project 21-23975: Development of Thermal Power Dispatch Simulation Tools for BWR Flexible Plant Operation and Generation | Rensselaer Polytechnic Institute | $800,000 | In the U.S. domestic light water reactor fleet, about one-third of operational nuclear power reactors are boiling water reactors (BWRs). Thermal power extraction technologies to be designed for BWRs will be different from those for pressurized water reactors due to differences in steam generation. This study proposes to investigate the thermal and electric power dispatch and required control algorithms for dynamic heat dispatch of up to 50% of the thermal energy from a BWR plant to a hydrogen plant. | RCRD&D | FY2021 | |
| NEUP Project 21-24111: Experimental Investigations of HTGR Fission Product Transport in Separate-effect Test Facilities Under Prototypical Conditions for Depressurization and Water-ingress Accidents | Texas A&M University | $800,000 | Experimental investigations will be performed for fission product (FP) lift-off, washoff, vaporization from plateout surfaces, and transport of FP at prototypical conditions representing depressurization and water-ingress accidents. Measurements will be performed on existing separate-effect facilities using intrusive and non-intrusive techniques to obtain shear stress, deposition velocity, thermal gradient, and gas impurity for advanced correlations. Modeling will be performed using system and computational fluid dynamics codes. | RCRD&D | FY2021 | |
| NEUP Project 21-24644: High-Resolution Measurements and Advanced Modeling for Design Optimization of Advanced Small Modular Reactor Steam Generators | Texas A&M University | $800,000 | Experiments and simulations will be performed to acquire multi-parameters of pressure drop, heat and mass transfer, and flow-induced vibration (FIV) effect for the design optimization of advanced small modular reactor steam generators (SMR SG). Measurements are performed on existing SMR SG facilities using intrusive/non-intrusive techniques to obtain velocity, temperature, pressure, heat flux, and FIV effects for various geo-dimensions, spacing, pitch angles. Simulations will be performed in StarCCM, Nek5000 and coupling with Diablo | RCRD&D | FY2021 | |
| NEUP Project 21-24332: A Virtual Reality Environment for Human Reliability Assessment in the Context of Physical Security Attacks | The Ohio State University | $800,000 | Recent studies have shown that the physical security workforce accounts for 20% of the entire workforce and, therefore, is responsible for significant operational and maintence costs. To reduce the security staffing, improve performance and reduce threats, modeling and simulation and models of attacker, defender and operator behavior could be employed. This proposal aims to model human behavior using a combination of known human reliability analyses models and experimental evidence from virtual reality experiments. | RCRD&D | FY2021 | |
| NEUP Project 21-24389: High Temperature Electromagnetic Acoustic (EMAT) Transducers for Structural Health Monitoring | University of Cincinnati | $800,000 | The aim of this project is to produce an electromagnetic acoustic transducer (EMAT) technology to enable ultrasonic structural health monitoring at the METL facility and similar high temperature assets. Ultrasonic nondestructive evaluation methods can be used for monitoring a range of damage mechanisms including thermal fatigue and corrosion. The project will seek to establish core design solutions that can be used as the basis of a range of EMAT designs for different applications. | RCRD&D | FY2021 | |
| NEUP Project 21-24380: Probabilistic Validation and Risk Importance Ranking Methodology for Automation Trustworthiness and Transparency in Nuclear Power Plants | University of Illinois at Urbana-Champaign | $800,000 | This project develops a methodology to improve trustworthiness and transparency of automation technologies in nuclear power plants. The proposed methodology will monitor risk emerging from automation processes and rank the criticality of automation factors influencing automation output, plant equipment, and system performance. The feasibility and practicality of the proposed methodology will be demonstrated with two case studies focusing on implementation of nuclear power plant automation technologies. | RCRD&D | FY2021 | |
| NEUP Project 21-24162: Self-powered wireless sensor system for health monitoring of liquid-sodium cooled fast reactors | University of Notre Dame | $800,000 | The goal of this project is to develop self-powered wireless multimodal sensors and instrumentation for health monitoring and diagnosing early-stage materials degradation for high-risk components in liquid-sodium cooled fast reactors. The synergistic and innovative integrations of the multimodal sensor array, wireless communication, and thermoelectric energy harvester have crosscutting benefit for a wide range of advanced reactors. | RCRD&D | FY2021 | |
| NEUP Project 21-24102: High temperature Molten salt reactor pump component development and testing | University of Wisconsin-Madison | $800,000 | This project will provide relevant key information on the tribology of bearing material and components (such as magnets, couplers, ceramic coated wire, and coatings) in high temperature molten salts that will be required in the design of reactor pumps. Investigation of in-service inspection and monitoring of the pump internals will also be addressed in an effort to reduce down time and operation and maintenance costs. | RCRD&D | FY2021 | |
| NEUP Project 21-24226: Cost Reduction of Advanced Integration Heat Exchanger Technology for Micro-Reactors | University of Wisconsin-Madison | $799,713 | Heat exchanger technology is a high-cost component of a micro-reactor system that is also critical to the overall reliability and performance. This project will develop the underlying advanced heat exchanger technology necessary to integrate a micro-reactor with any end-user application, as well as providing internal heat exchange. Economic optimization of the heat exchanger and experimental demonstration of the technology will be accomplished. | RCRD&D | FY2021 | |
| NEUP Project 21-24382: Advanced High-Fluence Low-Flux RPV Mechanical Property Models for Extended Life | University of Wisconsin-Madison | $799,717 | This project will further develop accurate models of the mechanical property changes under life-extension conditions in reactor pressure vessel (RPV) steels using reduced order Avrami models, cluster dynamics, and atomistic methods combined with massive comprehensive databases on irradiated steels. The work will provide models critical to extending the life of U.S. pressurized water reactors, as well as new fundamental insights into flux and fluence effects and sink and precipitate evolution in reactor pressure vessels and related steels. | RCRD&D | FY2021 | |
| NEUP Project 21-24394: Computer vision and machine learning for microstructural qualification | Carnegie Mellon University | $497,518 | Quantifying and understanding microstructure is a key driver for performance-based materials qualification. In this proposal, well-curated data sets of microstructural images will be gathered and computer vision and machine learning will be applied to build quantitative deep learning frameworks to accelerate and enable qualification of nuclear materials based on microstructural features. | Crosscutting Technologies | FY2020 | |
| NEUP Project 21-24156: Experimental thermofluidic validation of TCR fuel elements using distributed temperature and flow sensing | Kansas State University | $798,250 | The overall goal of this project will be to test the performance of 3D printed Transformational Challenge Reactor core geometry parts using existing Helium flow loops and distributed temperature, and velocity sensing systems. Thermal transport capabilities of scaled 3D printed ceramic core will be evaluated experimentally and measurements will be used to qualify computational models. | Crosscutting Technologies | FY2020 | |
| NEUP Project 21-24636: Risk-informed Consequence-driven Physical Protection System Optimization for Microreactor Sites | Texas A&M University | $400,000 | This proposed project will utilize a risk-informed, consequence-driven analysis to develop an approach for "right-sizing" physical protection systems (PPS) for microreactors. The hypothesis presented for this proposal is that the explicit coupling of consequence modeling to PPS design will provide a similar benefit that can be applied prior to reactor construction. | Crosscutting Technologies | FY2020 | |
| NEUP Project 21-24131: Total Mass Accounting in Advanced Liquid Fueled Reactors | The Ohio State University | $400,000 | A total mass determination method for nuclear materials accounting (NMA) in liquid-fueled molten salt reactors will be validated with fuel-bearing salt, mixed with a + radioisotope of known activity, that will be irradiated to reproduce the practical NMA scenario in a molten salt loop. Irradiated fuel salt will be sampled and measured for its mass and activity. The mass-to-activity ratio will be used to calculate the unknown salt mass in the original container. | Crosscutting Technologies | FY2020 | |
| NEUP Project 21-24037: Design and intelligent optimization of the thermal storage and energy distribution for the TerraPower Molten Chloride Fast Reactor in an Integrated Energy System (IES) | University of Tennessee at Knoxville | $800,000 | The objective of this project is to explore the application of advanced reactors within Integrated Energy Systems, use extensive existing data from UIUC for model development and validation, and extend the predictions to larger grids and commercial applications. | Crosscutting Technologies | FY2020 | |
| NEUP Project 21-24522: Targeted Materials Characterization and Testing of Additively Manufactured Metals and Ceramics to Inform Print/Build Data Analytics | University of Texas at San Antonio | $800,000 | A collaborative program between the University of Texas at San Antonio and Boise State University is proposed to supply materials testing and characterization data sets to be leveraged by the TCR program to inform build/print data analytics. With the data provided by the proposing team, correlations among steam oxidation performance, micromechanical properties, chemical composition, local microstructure, and location specific print/build data will be achieved. | Crosscutting Technologies | FY2020 | |
| NEUP Project 21-24431: Location-specific material characterization of LPBF SS316L & IN718 TCR core structural materials | Utah State University | $800,000 | In this proposed work, we will experimentally characterize the spatial variability of the quasi-static (tensile), creep (strength and impression), and creep-fatigue properties as well as the underlying structures (microstructure and defect structures) for LPBF SS316L and IN718 components to be used as training data to the TCR program data-driven model. The resulting correlation will be used to drive the design process for an application as TCR core structural materials. | Crosscutting Technologies | FY2020 | |
| NEUP Project 21-23978: Rapid, Non-Radioactive Methods for Prediction and Quantification of Radiolytic Radical Decomposition Products in Nuclear Separations | Clemson University | $399,999 | High-throughput, non-radioactive, radical assays will be used to determine decomposition of monoamide separations complexants. Radical assay results will be correlated with classic radiolytic damage results to develop predictive models for screening complexant stability. These models will aid in single-stage separations complexant optimization, in the transition from lab-to industrial-scale nuclear waste separations and, ultimately, could yield field tests for radiolytic damage. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24350: Phosphate Mineral and Glass Waste Forms for Advanced Immobilization of Chloride and Fluoride-based Waste Streams | Clemson University | $600,000 | This proposal is intended to develop three waste form options for immobilizing the fluoride-and chloride-salt waste stream in highly durable and easily processable phosphate minerals and glasses, including phosphate apatite ceramic waste forms, phosphate glass waste forms, and phosphate glass-ceramic waste forms with apatite phase. Multiple monolithic waste form samples will be provided to DOE national laboratories for further testing. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24292: Passive multimodal tomography for dry storage casks imaging using passive neutron and gamma dosimetry and cosmic ray muons | Colorado School of Mines | $800,000 | A method for multimodal tomography of dry storage casks will be developed to determine fuel relocation and cladding failures using passive neutrons and gamma emissions in combination with cosmic ray muons. The use of multimodal imaging will allow 3-D reconstructions of the dry storage cask that would be unachievable with any single radiation source. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24374: Effects of Radiolysis on Pertechnetate under Solvent Extraction Conditions, including Tri-Butyl Phosphate | CUNY, Hunter College | $399,624 | The overarching objective of the proposed work is to assess the impact of radiolysis on pertechnetate speciation during tri-butylphosphate (TBP) solvent extractions from the molecular level to macroscale. The research in this project is designed to understand the interplay of radiolysis, degradation product formation, other important redox active metals, and oxidation states of technetium on its speciation and distribution coefficients in solvent extraction processes. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24183: Experimental investigation and development of models and correlations for cladding-to-coolant heat transfer phenomena in transient conditions in support of TREAT and the LWR fleet. | Massachusetts Institute of Technology | $800,000 | Thermal-hydraulics transient heat transfer phenomena of relevance for the safety and the operation of the TREAT and light water reactors will be investigated. The performance of accident tolerant fuel materials during a reactivity initiated accident scenario and post-critical heat flux and reflood scenarios will be elucidated, as well as the development of models and correlations to be integrated into computational tools for the design and safety analysis of nuclear systems. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24666: Wireless Multifunctional Ultrasonic Arrays with Interdigital and Airborne Transducers for Monitoring Leakage and Corrosion Conditions of Welded Dry Storage Canisters | Mississippi State University | $800,000 | This project aims to develop and validate wireless, multifunctional, ultrasonic sensor arrays that enable on-demand, quantitative interrogation and real-time monitoring of both the canister leakage indicators (helium, helium/air mixture, internal pressure, and temperature) and corrosion conditions (free and/or vapor water). The developed arrays will be fully functional, wirelessly powered and communicated, and compact. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24188: Uranium recovery from used nuclear fuel using metal sulfides | Northwestern University | $400,000 | An alternative and original method to recover uranium from spent fuel is proposed. This method will utilize a new type of regenerable sorbent materials with high selectivity in capturing uranium from complex mixtures in acidic solutions, such as those found in used nuclear fuel of high-assay low-enriched uranium. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24225: Characterizing Fuel Response and Quantifying Coolable Geometry of High-Burnup Fuel | Oregon State University | $800,000 | This study seeks to objectively determine, through empirical and numerical means, the actual impact of fuel dispersion in-core after fuel failure and whether high burnup dispersed fuel compromises coolable geometry and long-term cooling. The outcome of this study will yield an objective means of assessing two criteria (coolable geometry and long-term cooling) within the existing regulatory process to comprehensively understand whether it is feasible to increase burnup, while satisfying 10 CFR 50.46. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24288: Innovative Methods for Interrogation of DSC Internal Conditions | Oregon State University | $800,000 | The proposed work takes a two-pronged approach. The team will study techniques involving only external sensors and equipment, which could be deployed on existing dry storage canisters. In addition, small sensors located inside the canister that can be externally powered and read through the canister wall will also be investigated. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24439: Development of Novel Corrosion-Responsive Buffer Materials for Long-Term Immobilization of High-Level Nuclear Waste | Pennsylvania State University | $800,000 | The goal of this project is to develop a novel cementitious buffer material (CBM) for the safe disposal of spent nuclear fuel (SNF). The primary aim is to identify and characterize novel Mg-Al-P CBMs, complete with assessments of their repository stability as well as their transport and immobilization of radionuclides. The secondary aim is to use in-situ UT-EIS monitoring to understand the corrosive failure at the canister-CBM interface and provide long-term performance modeling of SNF packages. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24461: Estimation of low temperature cladding failures during an RIA transient | Pennsylvania State University | $800,000 | Researchers aim to create a multiphysics description of cladding response during a RIA, especially at high burnup, coupling reactor physics, thermal hydraulics and mechanics. The creation of a thermomechanical model in Bison will be the result of this project which can be used to evaluate the likelihood of low temperature cladding failures during a postulated RIA on a typical fuel rod (as these can lead to channel blockage), and thus identify the most important conditions to be studied at TREAT. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24460: Multiscale Modeling and Experiments for Investigating High Burnup LWR Fuel Rod Behavior Under Normal and Transient Conditions | Texas A&M University | $800,000 | The main objective of this work is to achieve a mechanistic understanding of and to develop a predictive model for the fuel rod behavior at high burn-up under both normal and transient conditions. Therefore, this study will provide the nuclear industry with validated, physics-based criteria to fuel fragmentation thresholds and rod mechanical integrity limits. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24388: Redox Chemistry of UO2 under Repository Relevant Conditions in the Presence of Zircaloy and Waste Canister Material | University of California, Irvine | $800,000 | This project will seek to improve understanding of spent nuclear fuel (SNF) corrosion. Hydrothermal experiments of SNF with cladding and waste canister material will give insights into the redox potential formed due to secondary phase formation as consequence of corrosion in a failed canister. The experimentally derived data about secondary phase formation will be utilized for phase relationship analysis to decipher the redox conditions and thus provide source term for performance assessment models of deep geologic repositories. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24006: High-fidelity modeling of fuel-to-coolant thermomechanical transport behaviors under transient conditions | University of Florida | $800,000 | The objective of the proposal is to develop a high-fidelity modeling tool that can capture some of the important phenomena in high burnup UO2 and ATF fuels during transient conditions. The BlueCRAB tool set will be improved and used to analyze TREAT loss of coolant accident experimental results. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24312: Accelerating the development of reliable and robust machine learning-based interatomic potentials for the prediction of molten salt structure and properties | University of Massachusetts Lowell | $400,000 | Machine learning-based interatomic potentials (MLIPs) used in molecular dynamics (MD) can accurately and efficiently predict molten salt properties. However many machine learning-based methods require large training sets, and can fail unpredictably. This project will overcome these challenges by developing a method for efficiently sampling diverse configurations from MD to train reliable and robust neural network potentials, and develop new models for predicting errors in MLIPs. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24697: Dual External Leak Sensing and Monitoring for Dry Storage Canister | University of Nebraska, Lincoln | $800,000 | Researchers aim to develop two complementary external sensing methods to evaluate the integrity of DSC through internal pressure monitoring and helium leakage detection. The proposed diffuse ultrasonic wave method will be able to measure biaxial strains in the canister wall with high sensitivity and minimum temperature effects. An innovative capacitance MEMS sensor will be developed for helium concentration measurement in air based on the extremely low permittivity of helium. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24449: Multi-modal Surface Acoustic Wave Sensing System for Pressure and Temperature monitoring of Spent Fuel Canisters | University of North Texas | $800,000 | University of North Texas (UNT) will collaborate with Oak Ridge National Laboratory (ORNL) and National Energy Technology Laboratory (NETL) to develop a multi-modal wireless passive SAW (Surface Acoustic Wave) sensor array, which are deployed on the outside surface of the canister, to monitor the strain of the canister and thus determine the inside pressure. In addition, the SAW strain sensor could also measure the surface temperature and potentially monitor helium gas leak. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24265: Fragmentation and Thermal Energy Transport of Cr-doped Fuels under Transient Conditions | University of Pittsburgh | $799,999 | This project will focus on multiple aspects of experimental testing and engineering-scale modeling in understanding thermal energy transport from high burnup, fractured/fragmented accident tolerant fuels, establishing a strong scientific basis to fill a critical knowledge data gap for modeling and simulation of transient fuel performance and safety, such as loss of coolant accident, for future integral testing and fuel licensing. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24310: Fusion of Distributed Fiber Optics, Acoustic NDE, and Physics-Based AI for Spent Fuel Monitoring | University of Pittsburgh | $800,000 | The proposal will leverage new concepts in the fusion between fiber optic distributed acoustic sensing and advanced acoustic nondestructive evaluation techniques with artificial intelligence enhanced classification frameworks to quantitatively characterize the state of dry cask storage containers for spent fuel monitoring, externally and non-invasively, without introducing additional risks of failure. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24261: Internal Wireless Sensors for Dry Cask Storage | University of South Carolina | $800,000 | The effort will test the reliability of wireless, internal sensors after exposure to drying and storage conditions. These sensors are used to internally monitor temperature, pressure, and dose. Radiation shielding will also be designed to protect sensors during long-term storage. The effort will develop piezoelectric techniques for miniaturization of optical emission spectroscopy for internal monitoring of gas composition during drying and long-term storage. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24533: Non-destructive Evaluation of Dry Storage Canisters Using Acoustic Sensing | University of Southern California | $800,000 | The objective of this project is to develop a robust non-destructive evaluation (NDE) technique based on acoustic sensing to detect impurity gases in a sealed (welded) dry storage canister (DSC) using only measurements collected on the external surface of the DSC. The method is based on the time-of-flight analysis of acoustic signals propagating through the fill gas of a DSC, which is influenced by the composition, density and temperature of the propagation medium. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-23984: Safety Implications of High Burnup Fuel for a 2-Year PWR Fuel Cycle | University of Tennessee at Knoxville | $800,000 | The objective of this project is to perform safety analysis of high burnup fuel for a Westinghouse 4-Loop Pressurized Water Reactor. The work aims to identify potential opportunities and gaps for high burnup fuel by utilizing both well-established and modern methodologies to model reactor physics, thermal-hydraulics, and plant system-level response that ultimately provide feedback to fuel performance analysis. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-23985: Fuel-to-Coolant Thermomechanical Behaviors Under Transient Conditions | University of Tennessee at Knoxville | $800,000 | This project will enhance the prediction of thermo-mechanical fuel-to-coolant heat transfer under transient conditions by using a coupled analysis and experiment approach. The effort is relevant to both high-burnup (> 62GWd/t) fuel applications and Accident Tolerant Fuel. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24070: Modeling high-burnup LWR fuel behavior under normal operating and transient conditions | University of Tennessee at Knoxville | $800,000 | This project aims to develop a high-burnup light water reactor fuel modeling capability to implement in the BISON code that would enable the accurate fuel rod behavior simulation during normal operation and design basis accidents, as wells as the identification of the rod life-limiting factors. Mechanistic engineering models will be developed for key phenomena, in particular, high burnup structure evolution, fuel fragmentation, and fission gas release. Traditional and accident tolerant fuels will be considered. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24033: Redox Chemistry in Nuclear Materials Storage Matrices under Ambient and Accelerated Aging Conditions | University of Washington | $800,000 | Deep geologic repositories must safely contain hazardous, high-activity nuclear wastes at geologic time-scales. However, such capability is centrally dependent on the element-specific redox chemistry within and at the interface of storage vessels. A comprehensive study of redox chemistry in cements used in long-term storage is proposed and emphasizes: 1) the actual consequences of accelerated aging modalities and 2) the novel use of newly available capabilities in advanced x-ray spectroscopies. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24063: Post-DNB Thermo-mechanical Behavior of Near-term ATF Designs in Simulated Transient Conditions | University of Wisconsin-Madison | $800,000 | The goals of the proposed research are to conduct coupled experimental and modeling investigations of thermo-mechanical performance of coated accident tolerant zirconium alloy claddings with simulated burnup doped fuels under thermal transients to predict complex thermal and mass transport phenomena of near-term Accident Tolerant Fuel designs in accident conditions. Experiments and modeling for understanding both cladding-coolant and fuel-coolant interactions will be performed. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24582: Machine-Learning-Accelerated Molecular Dynamics Approaches for Molten Salts | University of Wisconsin-Madison | $399,477 | New machine learning potential (MLP) approaches and new MLPs to enable rapid prediction of molten salt (FLiBe and Nal-MgCl2 with impurities) properties with near ab initio quantum mechanical accuracy will be developed. Uncertainty quantification with active learning and on-the-fly fitting will greatly accelerate MLP training. This work will support dramatically increased simulation speeds and associated data generation and understanding for molten salts. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24067: Development of Full Understanding of Mechanical-Chemical Coupling in Bentonite THMC processes | Virginia Polytechnic Institute and State University | $800,000 | The central hypothesis is that mechanical stress in an engineered barrier can lead to pressure solution of solid minerals, leading to significant changes in pore water chemistry, which affects bentonite stability, longevity of the waste pack, and dissolution and migration of nuclides. The overall objective of this project is to develop full understanding of the role of pressure solution on pore water chemistry, the implications to large-scale heterogeneity, and THMC processes. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-23987: Separate and Multi-Physics Effects IRPhEP Benchmark Evaluation using SNAP Experiments | Georgia Institute of Technology | $400,000 | The proposed project will develop an International Reactor Physics Experiment Evaluation Project (IRPhEP) mulitphysics microreactor benchmark evaluation based on data from the Systems for Nuclear Auxiliary Power (SNAP) program. This work will include systematic assessments of the experimental data with meticulous compilation and documentation, and validation of specific NEAMS tools to model effects that are unique to microreactors technologies. | Nuclear Energy | FY2020 | |
| NEUP Project 21-24630: Integral Benchmark Evaluation of Zero-Power Tests and Multi-Cycle Depletion Experimental Data of TVA WB1 Cycles 1-3 | North Carolina State University | $400,000 | This project proposes to develop an integral benchmark evaluation of available experimental data for zero-power tests and multi-cycle depletion for consistent and comprehensive validation of both novel high-fidelity and traditional multi-physics tools. The benchmark evaluation will be based on operational and measured data from the Pressurized Water Reactor Watts Bar Unit 1 released by Tennessee Valley Authority. | Nuclear Energy | FY2020 | |
| NEUP Project 21-24186: Regenerating Missing Experimental Parameters with Data-Assimilation Methods for MSRE Transient Benchmark Development and Evaluation | Virginia Commonwealth University | $400,000 | The proposed project will regenerate the undocumented basic data from available experimental data of the MSRE using advanced data-assimilation methods to facilitate the whole-loop modeling of the representative MSRE transients, and perform a thorough MSRE transient benchmark evaluation for the IRPhEP handbook. | Nuclear Energy | FY2020 | |
| NEUP Project 21-24194: Implementation of improved quasi-static, time-dependent, multi-physics methodology in Shift | Georgia Institute of Technology | $600,000 | A practical reference calculation route for time-dependent coupled Monte Carlo calculations, using Shift, will be developed. The proposed framework will be tailored to depletion and slowly varying transients, but with the flexibility to perform thermal-hydraulic time-dependent calculations with minimal computational overheads. This method relies on a hybrid-resolution stochastic approach in conjunction with a substep technique. | NEAMS | FY2020 | |
| NEUP Project 21-24078: Material transport model development and integration in the System Analysis Module (SAM) code | Rensselaer Polytechnic Institute | $400,000 | This project proposes to develop and implement models for System Analysis Module, which accurately characterize the sink, source, and interaction terms of key material species that are or may be present in various advanced reactor designs. | NEAMS | FY2020 | |
| NEUP Project 21-24195: Enhancing Yellowjacket for Modeling the Impact of Radiation and Stress on the Corrosion of Molten-Salt-Facing Structural Components | University of Florida | $692,088 | The objective of this project is to add the capability to model the impact of radiation and stress on corrosion to the Yellowjacket code, as well as to use Yellowjacket to create surrogate models that will be added to engineering-scale codes like Grizzly. We will also collect new experimental data for validation that quantifies the impact of stress and radiation on corrosion of 316 stainless steel in molten fluoride salts. | NEAMS | FY2020 | |
| NEUP Project 21-24405: Development of a High-fidelity Flow Boiling Database for Validation of High-void-fraction Flow Regime Models | University of Michigan | $800,000 | The primary objective of this proposed research is to develop a comprehensive, high-resolution, multiphase computational fluid dynamics validation-grade flow boiling data from rod bundle geometry simulating current light water reactor fuel designs by taking advantage of the instrumentation and facility developed by the research team. In addition, the applicability of the data through initial evaluations of selected test cases using Nek-2P boiling closure models will be studied and demonstrated for two-phase flow simulations. | NEAMS | FY2020 | |
| NEUP Project 21-24471: Technical Basis of Microstructure Criteria and Accelerated Testing for Qualifying Additively-manufactured 316H Stainless Steel for High-temperature Cyclic Service | Auburn University | $800,000 | This project seeks to reveal the fundamental relationship for AM 316H SS working at 500-750 C between additively-manufactured microstructures and creep/creep-fatigue properties through a multiscale experimental and modeling approach. The project also seeks to establish the technical basis for the microstructure criteria and accelerated testing method to support near-term nuclear qualification. | RCRD&D | FY2020 | |
| NEUP Project 21-24152: Direct heating of chemical catalysts for hydrogen and fertilizer production using Microreactors | Kansas State University | $799,202 | This proposal presents a novel integration approach to deliver process heat from microreactors by directly heating the catalyst particles from the primary heat transfer fluid in a moving packed bed heat exchanger (MPBHX). In this design, the tube side of the MPBHX can be a heat pipe or primary Helium coolant as in several microreactor designs. The shell side will be moving catalyst particles, which will enter the high temperature chemical reactor upon heating. | RCRD&D | FY2020 | |
| NEUP Project 21-24287: Investigating heat transfer in horizontally oriented HTGR under normal and PCC conditions | Kansas State University | $799,762 | Experimental research will be conducted to understand heat transfer inside the graphite matrix of horizontal microscale High Temperature Gas-cooled Reactors. Existing high temperature test facilities will be used to simulate normal operation and Pressurized Conduction Cooldown. The focus of these experiments is to generate benchmark data under forced and natural convection with coupled multi-mode heat transfer in scaled-down prismatic blocks. | RCRD&D | FY2020 | |
| NEUP Project 21-24104: Thermal Hydraulics Investigation of Horizontally Orientated Layout Micro HTGRs Under Normal Operation and PCC Conditions Using Integrated Advanced Measurement Techniques | Missouri University of Science and Technology | $800,000 | The proposed novel work will make a significant pioneering contribution to advance the knowledge and understanding of horizontal micro-high temperature gas cooled reactors. Quantification of metrics will pertain to convective heat transfer coefficients along the channel and gaps, comparative rates of convective and radiative heat transfer, location of peak temperature and its temporal variation, timescales for onset of natural convection, local gas velocity profiles, gas dispersion, crossflows, and temperature profiles over channel diameter and gap thickness. | RCRD&D | FY2020 | |
| NEUP Project 21-24004: An Open Source, Parallel, and Distributed Web-Based Probabilistic Risk Assessment Platform to Support Real Time Nuclear Power Plant Risk-Informed Operational Decisions | North Carolina State University | $800,000 | The main objective of the proposed work is to develop, demonstrate, and evaluate a probabilistic risk assessment (PRA) software platform needed to address the major challenges of the current legacy PRA tools. This includes better quantification speed, integration of multi-hazard models into traditional PRAs, and model modification/simplification and documentation automation. | RCRD&D | FY2020 | |
| NEUP Project 21-24228: Quantifying the Dynamic and Static Porosity/Microstructure Characteristics of Irradiated Graphite through Multi-technique Experiments and Mesoscale Modeling | North Carolina State University | $800,000 | This project proposes a joint experimental-computational approach to probe and quantify the porosity and microstructure characteristics of irradiated nuclear graphite grades and their influence on dimensional changes and turnaround behavior, as well as mechanical properties. The chief focus will be on quantifying both the static and dynamic porosity and crack characteristics in various graphitic phases through several experimental techniques. | RCRD&D | FY2020 | |
| NEUP Project 21-24247: Multi-scale Effects of Irradiation Damage on Nuclear Graphite Properties | Pennsylvania State University | $800,000 | Irradiation induces microstructural damage in graphite, causing both dimensional and property (stiffness, strength and creep) changes as a function of the displacement damage and temperature. The biggest gap remains is the fundamental deformation mechanisms behind the property changes. Researchers propose to eliminate this gap in knowledge with a comprehensive, multi-scale experimental framework exploiting in-situ transmission electron and X-ray computed tomography. | RCRD&D | FY2020 | |
| NEUP Project 21-23975: Development of Thermal Power Dispatch Simulation Tools for BWR Flexible Plant Operation and Generation | Rensselaer Polytechnic Institute | $800,000 | In the U.S. domestic light water reactor fleet, about one-third of operational nuclear power reactors are boiling water reactors (BWRs). Thermal power extraction technologies to be designed for BWRs will be different from those for pressurized water reactors due to differences in steam generation. This study proposes to investigate the thermal and electric power dispatch and required control algorithms for dynamic heat dispatch of up to 50% of the thermal energy from a BWR plant to a hydrogen plant. | RCRD&D | FY2020 | |
| NEUP Project 21-24111: Experimental Investigations of HTGR Fission Product Transport in Separate-effect Test Facilities Under Prototypical Conditions for Depressurization and Water-ingress Accidents | Texas A&M University | $800,000 | Experimental investigations will be performed for fission product (FP) lift-off, washoff, vaporization from plateout surfaces, and transport of FP at prototypical conditions representing depressurization and water-ingress accidents. Measurements will be performed on existing separate-effect facilities using intrusive and non-intrusive techniques to obtain shear stress, deposition velocity, thermal gradient, and gas impurity for advanced correlations. Modeling will be performed using system and computational fluid dynamics codes. | RCRD&D | FY2020 | |
| NEUP Project 21-24644: High-Resolution Measurements and Advanced Modeling for Design Optimization of Advanced Small Modular Reactor Steam Generators | Texas A&M University | $800,000 | Experiments and simulations will be performed to acquire multi-parameters of pressure drop, heat and mass transfer, and flow-induced vibration (FIV) effect for the design optimization of advanced small modular reactor steam generators (SMR SG). Measurements are performed on existing SMR SG facilities using intrusive/non-intrusive techniques to obtain velocity, temperature, pressure, heat flux, and FIV effects for various geo-dimensions, spacing, pitch angles. Simulations will be performed in StarCCM, Nek5000 and coupling with Diablo | RCRD&D | FY2020 | |
| NEUP Project 21-24332: A Virtual Reality Environment for Human Reliability Assessment in the Context of Physical Security Attacks | The Ohio State University | $800,000 | Recent studies have shown that the physical security workforce accounts for 20% of the entire workforce and, therefore, is responsible for significant operational and maintence costs. To reduce the security staffing, improve performance and reduce threats, modeling and simulation and models of attacker, defender and operator behavior could be employed. This proposal aims to model human behavior using a combination of known human reliability analyses models and experimental evidence from virtual reality experiments. | RCRD&D | FY2020 | |
| NEUP Project 21-24389: High Temperature Electromagnetic Acoustic (EMAT) Transducers for Structural Health Monitoring | University of Cincinnati | $800,000 | The aim of this project is to produce an electromagnetic acoustic transducer (EMAT) technology to enable ultrasonic structural health monitoring at the METL facility and similar high temperature assets. Ultrasonic nondestructive evaluation methods can be used for monitoring a range of damage mechanisms including thermal fatigue and corrosion. The project will seek to establish core design solutions that can be used as the basis of a range of EMAT designs for different applications. | RCRD&D | FY2020 | |
| NEUP Project 21-24380: Probabilistic Validation and Risk Importance Ranking Methodology for Automation Trustworthiness and Transparency in Nuclear Power Plants | University of Illinois at Urbana-Champaign | $800,000 | This project develops a methodology to improve trustworthiness and transparency of automation technologies in nuclear power plants. The proposed methodology will monitor risk emerging from automation processes and rank the criticality of automation factors influencing automation output, plant equipment, and system performance. The feasibility and practicality of the proposed methodology will be demonstrated with two case studies focusing on implementation of nuclear power plant automation technologies. | RCRD&D | FY2020 | |
| NEUP Project 21-24162: Self-powered wireless sensor system for health monitoring of liquid-sodium cooled fast reactors | University of Notre Dame | $800,000 | The goal of this project is to develop self-powered wireless multimodal sensors and instrumentation for health monitoring and diagnosing early-stage materials degradation for high-risk components in liquid-sodium cooled fast reactors. The synergistic and innovative integrations of the multimodal sensor array, wireless communication, and thermoelectric energy harvester have crosscutting benefit for a wide range of advanced reactors. | RCRD&D | FY2020 | |
| NEUP Project 21-24102: High temperature Molten salt reactor pump component development and testing | University of Wisconsin-Madison | $800,000 | This project will provide relevant key information on the tribology of bearing material and components (such as magnets, couplers, ceramic coated wire, and coatings) in high temperature molten salts that will be required in the design of reactor pumps. Investigation of in-service inspection and monitoring of the pump internals will also be addressed in an effort to reduce down time and operation and maintenance costs. | RCRD&D | FY2020 | |
| NEUP Project 21-24226: Cost Reduction of Advanced Integration Heat Exchanger Technology for Micro-Reactors | University of Wisconsin-Madison | $799,713 | Heat exchanger technology is a high-cost component of a micro-reactor system that is also critical to the overall reliability and performance. This project will develop the underlying advanced heat exchanger technology necessary to integrate a micro-reactor with any end-user application, as well as providing internal heat exchange. Economic optimization of the heat exchanger and experimental demonstration of the technology will be accomplished. | RCRD&D | FY2020 | |
| NEUP Project 21-24382: Advanced High-Fluence Low-Flux RPV Mechanical Property Models for Extended Life | University of Wisconsin-Madison | $799,717 | This project will further develop accurate models of the mechanical property changes under life-extension conditions in reactor pressure vessel (RPV) steels using reduced order Avrami models, cluster dynamics, and atomistic methods combined with massive comprehensive databases on irradiated steels. The work will provide models critical to extending the life of U.S. pressurized water reactors, as well as new fundamental insights into flux and fluence effects and sink and precipitate evolution in reactor pressure vessels and related steels. | RCRD&D | FY2020 | |
| NEUP Project 19-16987: Novel miniature creep tester for virgin and neutron irradiated clad alloys with benchmarked multiscale modeling and simulations | North Carolina State University | $800,000 | This project will develop a miniature creep machine to collect rapid thermal creep and load relaxation data for two selected ferritic alloys under "as-received" and irradiated conditions. Fast and accurate measurements of creep deformation are essential for qualifying new alloys for long term use in current and next generation reactors. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-17150: Speciation and Behavior of Neptunium and Zirconium in Advanced Separation Process | Oregon State University | $800,000 | This project will further develop the understanding of nuclear fuel reprocessing using Co-Decontamination (CoDCon). Radiolytic degradation products of tributylphosphate, nitric acid, redox buffer, masking agent, and water greatly affect the redox speciation, complexation and partitioning of the recycled metals. Fundamental understanding of chemical speciation and partitioning of Neptunium and Zerconium under such conditions is required. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-17395: Modeling and Uncertainty Analysis of MSR Nuclear Material Accounting Methods for Nuclear Safeguards | Pennsylvania State University | $800,000 | This project will model and analyze the limits of detection for the diversion of nuclear materials from a molten salt reactor (MSR) fuel cycle. MSR depletion under a range of uranium and/or plutonium diversion to quantify the resulting differences in salt composition will be evaluated. Sensors will also be investigated to quantify fuel salt contents and correlate the outputs with the reactor models to predict diversion detection. Results will be coupled with robust uncertainty analysis to determine limits of detection. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-16583: Neutron Radiation Effect on Diffusion between Zr (and Zircaloy) and Cr for Accurate Lifetime Prediction of ATF | The Ohio State University | $499,997 | This project will perform systematic diffusion studies on both neutron-irradiated and unirradiated accident tolerant fuel samples to obtain precise diffusion coefficients. This will result in a precise evaluation of the pure neutron irradiation effect on diffusion in these systems and enable accurate life prediction of the accident tolerant fuels. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-17381: High Throughput Assessment of Creep Behavior of Advanced Nuclear Reactor Structural Alloys by Nano/microindentation | University of Minnesota, Twin Cities | $800,000 | This project will develop a high throughput assessment of creep behavior of advanced nuclear reactor structural alloys by nano/microindentation. Experimental datasets will inform polycrystalline deformation models to predict material response over a variety of creep conditions. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-16549: Thermal Conductivity Measurement of Irradiated Metallic Fuel Using TREAT | University of Pittsburgh | $500,000 | This project intends to provide accurate thermal conductivity and thermal diffusivity data with microstructure characterization of metallic (U-Pu-Zr) fuel as a function of burnup and attain fundamental understanding of the thermal conductivity of the irradiated fuel to inform and validate computational models. This will be accomplished using an innovative thermal wave technique in the Transient Reactor Test Facility at the Idaho National Laboratory, with the Minimal Activation Reusable Capsule Holder. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-17002: Remote Laser-based Nondestructive Evaluation for Post-Irradiation Examination of ATF Cladding | University of South Carolina | $800,000 | To enable advanced nondestructive characterization techniques for light water reactor fuels that can be applied to the cladding coating, a remote nondestructive evaluation post irradiation inspection approach will be developed. This technique will measure the cladding coating layer thickness and detect defects within the cladding such as corrosion, micro-cracking and delamination. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-17276: Radiation-Induced Swelling in Advanced Nuclear Fuel | University of Tennessee at Knoxville | $799,989 | The microstructural evolution of advanced fuel (uranium carbide and uranium nitride) under fission-fragment type radiation has not been studied and remains unclear. This project will utilize advanced synchrotron X-ray characterization using microgram samples to obtain detailed nanoscale information on radiation-induced volumetric swelling and microstrain. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-16848: Metal-Functionalized Membranes for Radioiodine Capture | University of Utah | $799,031 | This proposed research will investigate high-surface area (>300 m2/g) metal-functionalized membranes. These novel chemically durable and mechanically robust membranes are formed using an aqueous fabrication process, which results in an interconnected porosity that is highly controllable, providing hierarchical structures ranging from the nano-to micrometer-scales. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-17350: Development and Experimental Validation of Pitting and SCC Models for Welded Stainless Steel Dry Storage Containers Exposed to Atmospheric Environments | University of Virginia | $799,027 | The specific goals of this project are to: (a) validate the maximum pit size model for dry storage canister relevant corrosion conditions as well as quantifying the effects of limited cathodic current on stress corrosion cracking (SCC) kinetics, (b) demonstrate a means to quantitatively rank the risk of SCC based on measurable parameters, (c) perform probabilistic predictions of SCC growth, and (d) validate the model predictions. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-16879: Proactive Hybrid Nuclear with Load Forecasting | Brigham Young University | $799,933 | This project develops new capabilities of design and dispatch optimization of nuclear hybrid energy systems (NHES) in the "Risk Analysis Virtual Environment (RAVEN)" modelling software. Blended (physics-based and data-driven) machine learning will be applied to forecast demand and production of thermal and electrical loads. Two experimental case studies are proposed to test the software developments with a lab-scale thermal energy storage and with a large district energy system. As a final step, the software developments will be generalized to other NHES. | Nuclear Energy | FY2019 | |
| NEUP Project 19-17461: Development and Evaluation of Neutron Thermalization Integral Benchmarks for Advanced Reactor Applications | North Carolina State University | $400,000 | This project will develop integral benchmarks that aim to examine thermal neutron scattering data for graphite (ideal and nuclear), light water, and molten salt. The benchmark evaluations will be contributed to the International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhEP) database. | Nuclear Energy | FY2019 | |
| NEUP Project 19-16739: Improvements of Nuclear Data Evaluations for Lead Isotopes in Support of Next Generation Lead-Cooled Fast Systems | Rensselaer Polytechnic Institute | $400,000 | The objective of this project is to improve the accuracy of neutronics simulation of lead-based systems by improving the nuclear data of lead isotopes. The nuclear data for lead will be reevaluated with emphasis of the intermediate and fast energy regions that are required by reactor applications currently sought by several industrial entities. The deliverables of this project are new lead isotopes evaluations that will be candidates for inclusion in a future Evaluated Nuclear Data Library (ENDF) release. | Nuclear Energy | FY2019 | |
| NEUP Project 19-17219: Using Integral Benchmark Experiments to Improve Differential Nuclear Data Evaluations | University of New Mexico | $400,000 | This project will use the results of integral benchmark experiment to inform differential nuclear data evaluations and improve the predictive capability of modeling and simulation (M&S) tools. This goal will be accomplished by developing capabilities to assess the sensitivity of integral benchmark results to evaluated nuclear data parameters, and by using data assimilation tools to directly adjust the evaluated data parameters and improve the accuracy of M&S tools. | Nuclear Energy | FY2019 | |
| NEUP Project 19-16743: Paths Forward for Nuclear Energy: Using a Nationwide Post-Stratified Hierarchical Model to Facilitate Matching of New Nuclear Technologies to Receptive Host Communities | University of Oklahoma | $390,393 | This project will enable deployment of advanced nuclear technologies by developing a model, and an accompanying web-based tool that can be utilized by technology entrepreneurs, that identifies public support for siting new nuclear technologies at very local spatial scales across the US. The model will employ hierarchically structured, post stratified analysis of the largest US pooled-time series dataset on geocoded public support for nuclear technologies. | Nuclear Energy | FY2019 | |
| NEUP Project 19-16995: A Cyber-Attack Detection Platform for Cyber Security of Digital Instrumentation and Control Systems | University of Tennessee at Knoxville | $799,995 | The proposed research will develop a robust cyber-attack detection system (CADS) for monitoring digital instrumentation and control (I&C) systems. The project will develop a robust research tool for evaluating cyber defense of digital I&C systems and provide a framework for a cyber-attack detection system that provides continuous assurance of the security of digital I&C systems in nuclear power plants (NPPs). | Nuclear Energy | FY2019 | |
| NEUP Project 19-17327: Multi-Timescale Nuclear-Renewable Hybrid Energy Systems Operations to Improve Electricity System Resilience, Reliability, and Economic Efficiency | University of Texas at Dallas | $800,000 | The overarching objective of this project is to develop a multi-timescale nuclear-renewable hybrid energy systems (N-R HESs) operations framework to provide different types of grid products. The project will model and analyze the capabilities of N-R HESs to provide power grid services at different timescales ranging from seconds to days, such as day-ahead unit commitment, flexible ramping (5-45 minutes), regulation reserves (1-5 minutes), and frequency response (less than seconds). | Nuclear Energy | FY2019 | |
| NEUP Project 19-17192: The Design and Investigation of Novel Mechanical Filters for Molten Salt Reactors | Abilene Christian University | $762,246 | Researchers will develop a novel mechanical filtration system. The project will include the collection of filter media performance data and filter regeneration performance data for a novel sintered nickel-based filter prototype. The project will also provide a filter design that facilitates remote filter removal, cooling, replacement, and assay of fissile material hold-up in the filter media. | RCRD&D | FY2019 | |
| NEUP Project 19-16980: Determining the Effects of Neutron Irradiation on the Structural Integrity of Additively Manufactured Heat Exchangers for Very Small Modular Reactor Applications | Auburn University | $400,000 | Researchers will determine how to best use laser-powder bed fusion additive manufacturing methods for generating radiation-resistant channel/pore-embedded structures from Inconel (alloy 625 or 718) nickel-based superalloys for special purpose reactor (i.e. very small modular reactor) heat exchangers. | RCRD&D | FY2019 | |
| NEUP Project 19-17413: Validated, Multi-Scale Molecular Dynamics Simulations to Predict the Thermophysical Properties of Molten Salts Containing Fuel, Fission, and Corrosion Products | Brigham Young University | $798,291 | Researchers will use first principles molecular dynamics (FPMD) simulations on molten salts containing impurities including fuel, fission products, and corrosion products. These will be used to develop a classical molecular dynamics (CMD) potential. CMD will then be used to predict properties for a wide variety of salt compositions and temperatures, and physical property measurements will be performed to validate those predictions. Property correlations will be developed from this data. | RCRD&D | FY2019 | |
| NEUP Project 19-17183: Mixing of helium with air in reactor cavities following a pipe break in HTGRs | City College of New York | $800,000 | Researchers will conduct separate effects tests to obtain experimental validation data on mixing of helium and air in reactor building cavities during and after blowdown in HTGRs. Air and helium concentrations, and gas mixture velocity and temperature fields will be measured in simulated reactor cavities. An existing helium flow loop will be used as the source of high pressure/high temperature helium for injection into the cavities and different break configurations will be experimentally investigated. | RCRD&D | FY2019 | |
| NEUP Project 19-16391: GuArDIAN: General Active Sensing for conDItion AssessmeNt | Duke University | $800,000 | Researchers will develop a dependable, autonomous or semi-autonomous (i.e. low human involvement), and minimally disruptive framework for monitoring equipment and components in nuclear reactors. The project will develop GUARDIAN; a robust active sensing framework through the integration of model-based inference and mobile actuating/sensing robots. | RCRD&D | FY2019 | |
| NEUP Project 19-17251: Measuring Mechanical Properties of Select Layers and Layer Interfaces of TRISO Particles via Micromachining and In-Microscope Tensile Testing | Idaho State University | $799,815 | Researchers will characterize the strength of TRISO-coated particle layers and interfaces using FIB micro-machining and in-TEM tensile testing. Tensile test samples from coating layers of (1) unirradiated surrogate (fuel) TRISO particles, (2) unirradiated fueled TRISO particles and (3) irradiated fueled TRISO particles will be studied. Results of this project will both benefit and leverage the AGR Program. | RCRD&D | FY2019 | |
| NEUP Project 19-17185: Demonstrating Reactor Autonomous Control Framework using Graphite Exponential Pile | Massachusetts Institute of Technology | $400,000 | Researchers will demonstrate a detection-prediction-feedback framework for nuclear system autonomous control. It will adopt multiple detector channels to enable control feedback to spatially dependent perturbations. It will also utilize high-fidelity solutions trained surrogate models for real-time prediction and decision-making. In addition to the method development, the proposal will entail a first-of-a-kind engineering demonstration using the MIT Graphite Exponential Pile (MGEP). | RCRD&D | FY2019 | |
| NEUP Project 19-16754: Simultaneous Corrosion/Irradiation Testing in Lead and Lead-Bismuth Eutectic: The Radiation Decelerated Corrosion Hypothesis | Massachusetts Institute of Technology | $762,823 | Researchers will test candidate FeCrSi and F/M alloys in a new, simultaneous corrosion/radiation facility to try to identify an alloy that will satisfy all requirements for Lead Fast Reactor structural materials. Microstructural characterization, mechanical property testing, and corrosion tests, both during irradiation and following ion/He pre-conditioning, will assess how irradiation affects corrosion, potentially slowing it. | RCRD&D | FY2019 | |
| NEUP Project 19-17173: Ni-based ODS alloys for Molten Salt Reactors | North Carolina State University | $800,000 | The objective of this work is to (i) propose and develop a new Nickel (Ni) based Oxide Dispersion-Strengthened (ODS) alloy that can be used for structural applications in Molten Salt Reactor (MSR) and other nuclear reactor harsh environments, (ii) to demonstrate that its high temperature mechanical properties are adequate for MSR operating temperatures, (iii) to demonstrate its radiation damage resistance through ion irradiation testing and (iv) to demonstrate its improved corrosion resistance in MSR environment. | RCRD&D | FY2019 | |
| NEUP Project 19-17037: Investigation of HTGR Reactor Building Response to a Break in Primary Coolant Boundary | Purdue University | $799,832 | Researchers will perform a series of experiments to simulate HTGR reactor building response due to a break in the primary coolant boundary in a well-scaled test facility to obtain spatial distribution of oxygen concentration, perform analysis of the whole system response with 1-D thermal hydraulics codes and use CFD to make detailed localized predictions. The tests will be carried out with different locations and sizes of the breaks to create various vent and flow paths in the reactor cavity. | RCRD&D | FY2019 | |
| NEUP Project 19-17093: Integrating Multi-modal Microscopy Techniques and the MOSAIC Simulation Environment to Assess Changes in the Physical Properties and Chemical Durability of Concrete Following Radiation Exposure | University of California, Los Angeles | $800,000 | Researchers will develop unprecedented multi-modal imaging methodologies that integrate multiple microscopy techniques. The team will develop a generalizable protocol for quantifying the changes in physical properties and chemical durability of concrete and concrete constituents (minerals and aggregates) following radiation exposure. The imaging analyses will be input into the MOSAIC framework to reveal the nature and extent of degradation that is expected to result. The outcomes offer insights that are needed to enable and inform second license renewals. | RCRD&D | FY2019 | |
| NEUP Project 19-17167: Atomistically Informed and Experimentally Validated Model for Helium Bubble Growth in Welded Irradiated Metals | University of Florida | $797,861 | Researchers will construct a validated computational model for He bubble growth on grain boundaries in irradiated Fe-Ni-Cr microstructures, including intergranular fracture, as a function of material conditions and welding heat input. This model will be based on the phase-field methodology, leveraging numerical solvers in the MOOSE simulation platform, with critical inputs and validation provided by both atomic-level simulations and experiments. | RCRD&D | FY2019 | |
| NEUP Project 19-16909: Learning-based Computational Study of the Thermodynamic, Structural, and Dynamic Properties of Molten Salts at the Atomic and Electronic Scale and Experimental Validations | University of Illinois at Urbana-Champaign | $800,000 | Researchers will obtain the thermophysical, thermochemical, and transport properties, construct the phase diagrams, and build empirical physical models of molten salts that are relevant to Molten Salt Reactors (MSRs) with first-principles accuracy using molecular dynamics simulations driven by machine-learned high-dimensional neural network potentials combined with neutron/X-ray scattering and thermodynamic experimental validations. | RCRD&D | FY2019 | |
| NEUP Project 19-16298: I-PRA Decision-Making Algorithm and Computational Platform to Develop Safe and Cost-Effective Strategies for the Deployment of New Technologies | University of Illinois at Urbana-Champaign | $800,000 | Researchers will develop an integrated probabilistic risk assessment decision-making algorithm to support risk-and-cost-informed decision-making related to the deployment of new technologies. The project will enhance the financial analysis module and the challenging interface of social and technical systems to advance the algorithm. The project will conduct a case study for evaluating the safety impact and cost-effectiveness of FLEX strategies to support operational flexibility. | RCRD&D | FY2019 | |
| NEUP Project 19-16802: Evaluation of Semi-Autonomous Passive Control Systems for HTGR Type Special Purpose Reactors | University of Michigan | $400,000 | Researchers will investigate the use of variable flow controllers and a variable reflector as passive or semi-autonomous reactivity control mechanisms for multi-module HTGR type special purpose reactors. This applies to the commercially developed special purpose reactor concepts from HolosGen. The incorporation of these systems will reduce the movable parts count and enable more robust load follow capabilities over broader power ranges and local and global reactivity control. | RCRD&D | FY2019 | |
| NEUP Project 19-17467: Understanding the Speciation and Molecular Structure of Molten Salts Using Laboratory and Synchrotron based In Situ Experimental Techniques and Predictive Modeling | University of Nevada, Reno | $800,000 | Researchers will develop a methodology to accurately determine the structure and speciation of the molten salt electrolyte using laboratory-based spectroscopic techniques (Raman and UV-Vis-NIR) and synchrotron-based (scattering and absorption) techniques, in combination with computational modeling. | RCRD&D | FY2019 | |
| NEUP Project 19-17231: Prevention of Common Fault-Trigger Combinations for Qualification of Digital Instrumentation and Control Technology | University of Tennessee at Knoxville | $800,000 | Researchers will provide an effective design evaluation approach based on prevention of concurrent triggering conditions to eliminate common-cause failures (CCF) and enable qualification of digital I&C technology for application in nuclear plant modernization. The research involves classifying commonality among digital devices, categorizing faults and triggering conditions, determining fault-trigger relationships, and defining preventive design measures to resolve the potential for CCF. | RCRD&D | FY2019 | |
| NEUP Project 19-17087: Economic Risk-Informed Maintenance Planning and Asset Management | University of Tennessee at Knoxville | $800,000 | Researchers will provide a holistic framework for cost-minimizing risk-informed maintenance planning, including inspection. They will develop a two-tier framework that coarsely minimizes the total maintenance cost during the remaining normal operating cycle and uses the outputs of the first model to maximize the financial impact of these activities in the short term. | RCRD&D | FY2019 | |
| NEUP Project 19-16811: Liquid Metal-cooled Fast Reactor Instrumentation Technology Development | University of Wisconsin-Madison | $800,000 | Researchers will explore three different areas that will help to improve commercialization of SFRs and to aid in testing for the VTR. These include: 1. Advancement in understanding of low prandtl number heat transfer 2. Testing of compact heat exchangers for use with sodium 3. Development of in pool submersible flow meters. | RCRD&D | FY2019 | |
| NEUP Project 19-16954: Innovative In-Situ Analysis and Quantification of Corrosion and Erosion of 316 Stainless Steel in Molten Chloride Salt Flow Loops | University of Wisconsin-Madison | $800,000 | Researchers will use a thin-layer activation technique for the first time in molten salts, on 316H samples placed in natural convection and forced flow loops. The individual and synergistic effects of corrosion, irradiation and thermo-mechanical treatments will be evaluated in-situ to predict component service lifetimes and design limits. The effects of molten chloride flow velocity will also be assessed. | RCRD&D | FY2019 | |
| NEUP Project 19-17168: Fuel Salt Sampling and Enriching System Technology Development | Vanderbilt University | $799,989 | Researchers will combine insights from the Molten Salt Reactor Experiment with decades of advancements in applicable technologies into an enhanced Sampler Enricher (SE) concept to develop and test a flexible, reliable, and workable design. The prototype will then be tested in an existing salt loop. | RCRD&D | FY2019 | |
| NEUP Project 18-15345: Multiphysics Degradation Processes, and Their Mitigation, in Engineered and Geological Bariers: Experiments and Simulation | Duke University | $800,000.00 | This project will focus on filling the gaps in understanding of mechanisms of a series of degradation processes (thermal, hydric, geo-chemical, and transport processes phenomena) potentially affecting geo-materials used in repositories. The objectives of the work are to better recognize the conditions leading to preferential paths of radionuclide transport and rock weakening, and to build mathematical models and implement them into existing codes to predict material degradation and develop strategies to reduce the adverse consequences. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15043: Integration of Nuclear Material Accounting Data and Process Monitoring Data for Improvement on Detection Probability in Safeguarding Electrochemical Processing Facilities | Oregon State University | $800,000.00 | The goal of this project is to further studies on fusion of process monitoring (PM) data and nuclear material accounting (NMA) data. PM data, which includes monitoring by various types of equipment (radiation detectors, cameras, voltage, current sensors), can supplement NMA data to help improve safeguards. For aqueous-based reprocessing facilities, it is reported that PM, integrated with traditional NMA, has a high-detection probability for specific diversions. For electrochemical reprocessing, preliminary studies have shown that PM data can support traditional NMA by providing a basis to estimate some of the in-processing nuclear material inventories. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15148: Recovery of Rare-Earth Elements (Nd, Gd, Sm) in Oxide Wasteform Using Liquid Metals (Bi, Sn) | Pennsylvania State University | $800,000.00 | This project investigates a new approach for recovering rare-earth (RE) fission products (Nd, Gd, and Sm) from molten chlorine salts using liquid metal (Bi and Sn) electrodes. The research aids molten salt recycling by converting the RE products into chloride-free RE oxides, which could be incorporated into conventional glass/ceramic waste forms. Successful outcomes of the project include advanced separation of fission products from molten salts with better control of chemical selectivity and high-recovery yield. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15103: Microstructure-Based Benchmarking for Nano/Microscale Tension and Ductility Testing of Irradiated Steels | Purdue University | $800,000.00 | The objective of this project is to standardize methods for nano/micro-scale tensile and ductility testing of irradiated Fe-Cr steels, through microstructure-based benchmarking. The study will investigate key process parameters for TEM in situ tension and ductility testing. Coupling experimental studies with multiscale models, the research will identify the approaches that provide consistent deformation mechanisms between the nano/micro-scale and macro-scale tests, from which standard practices will be obtained. The primary project outcome will be a set of recommended guidelines for nano/microscale mechanical testing, which will lead to unprecedented reductions in the time and cost for qualifying materials for in-reactor service and to ensure consistency of methods and validity of results. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15559: Cold Spray Repair & Mitigation of Stress Corrosion Cracks in Spent Nuclear Fuel Dry Storage Canisters | Purdue University | $799,982.00 | This goal of this project is to demonstrate cold spray repair and mitigation of chloride-induced stress corrosion cracks (SCC) and pits in stainless steel dry storage canisters. The research will optimize the repair process and gain a scientifically informed understanding of SCC mechanisms. The outcome is to further develop cold spray as an attractive solution for the repair of existing SCC and mitigation of potential SCC necessary to ensure long-term integrity, security, and regulatory compliance of spent nuclear fuel storage. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15596: Capture of Organic Iodides from Vessel Off-Gas Streams | Syracuse University | $799,548.00 | This project will study the capture of radioactive organoiodides from off-gas streams produced during nuclear fuel reprocessing by conducting adsorption experiments using a selected silver adsorbents. Multifaceted simulation adsorption models will be developed to assist in the design of necessary capture systems for off-gas streams. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15585: Impact of Coupled Gas Migration and Thermo-hydro-mechanical Processes on the Performance of Repositories for High Level Nuclear Waste | Texas A&M University | $608,375.00 | The main goal of this project is to better understand the possible effect of gas migration (particularly through discontinuities) on the performance and long-term behavior of engineered barrier systems (EBS) envisaged for the isolation of high-level radioactive waste (HLW). Specific outcomes of this study will be an improved understanding of the role of gas migration and discontinuities in the performance of HLW disposals, with the underlying aim to improve design of EBS used for HLW. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15531: Repair and Mitigation of Chloride-Induced Pitting and Chloride-Induced Stress Corrosion Cracking in Used Nuclear Fuel Dry Cask Canister Materials | The Ohio State University | $800,000.00 | This project will evaluate and develop a set of tools to repair and mitigate chloride-induced pitting and stress corrosion cracking in stainless steel nuclear fuel canisters. Advanced processes, including low temperature friction stir welding and cold spray deposition, will be evaluated according to various criteria, such as corrosion performance. In addition, technologies that have not yet been evaluated for UNF applications, including vaporizing foil actuator welding and soldering will be assessed. The two most promising technologies will selected for further development and comprehensive study. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-14912: Bridging the Length Scales on Mechanical Property Evaluation | University of California, Berkeley | $800,000.00 | This project combines experimental and modeling methods to gain a comprehensive approach for addressing scaling effects on small-scale mechanical testing. Multiscale experiments, together with modeling on reactor-relevant and model alloys, will provide better understanding of appropriate scaling relationships. The study aims to gain fundamental understanding of plasticity interactions with specific strength-determining features, such as precipitates and grain boundaries. The goal of this work is to provide the basis to add small-scale mechanical testing in the toolbox for nuclear materials research. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-14911: Understanding of degradation of SiC/SiC materials in nuclear systems and development of mitigation strategies | University of California, Berkeley | $800,000.00 | This project investigates the best possible coatings to prevent SiCf/SiCm corrosion in LWR environments. The research features a computational and experimental rapid screening approach for numerous coating compositions. The work includes autoclave exposure of rapid screening coupons in prototypical environments in combination with thermodynamic modeling (CALPHAD) and Finite Element Methods (FEM). Small-scale mechanical testing, together with thermal cycling and FEM modeling, will provide guidance on the ideal coating system design. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15701: Time-dependent THMC Properties and Microstructural Evolution of Damage Rocks in Excavation Damage Zone | University of Colorado, Boulder | $799,978.00 | The proposed project focuses on the geomechanical aspects of modeling by addressing the time-dependent evolution of rock microstructure and its coupling with the THC processes that are of first-order importance to the stability and the isolation performance of repositories. The research will delineate an integrated experimental, theoretical and numerical strategy in assessing the evolution EDZ over time and its implication on the long-term migration of hazardous species. These results will enhance the confidence of the predicted long-term performance of repositories, which helps to move forward the goal of one-million-year isolation of high-level nuclear wastes. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15381: Multiaxial Failure Envelopes and Uncertainty Quantification of Nuclear-Grade SiCf/SiC Woven Ceramic Matrix Tubular Composites | University of Florida | $800,000.00 | This project proposes to develop a comprehensive experimental and computational approach for determining constitutive relations and multiaxial failure envelopes of nuclear-grade continuous silicon fiber (SiCf) and SiC matrix woven tubular composites. The result of this work can be adopted in industry for design refinement, optimization of performance under the desired operating conditions, and reliable prediction of failure under unforeseen accidental scenarios. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15496: Formation of Zeolites Responsible for Waste Glass Rate Acceleration: An Experimental and Computational Study for Understanding Thermodynamic and Kinetic Processes | University of Houston | $800,000.00 | Through experimental and computational studies, this project will expose the factors governing zeolite crystallization and their role in Stage III dissolution of radionuclide-containing glass waste forms generated in advanced nuclear fuel cycles. The overall goal of this project is to understand the formation of zeolite phases in order to develop process control methods to suppress Stage III dissolution. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-14998: Novel Processes for Capture of Radioactive Iodine Species from Vessel Off-Gas Streams | University of Idaho | $800,000.00 | The goal of this project is to develop a comprehensive understanding of the sorption system performance and effectiveness for capture of radioiodine species present in the off-gas streams from the used nuclear fuel (UNF) recycling operations, focusing particularly on the organic iodine species. The dynamic sorption experimentation and theoretical modeling will offer fundamental insights on the mechanism enabling the design and prediction the control system performance. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15261: Friction Stir Based Repair Welding of Dry Storage Canisters and Mitigation Strategies: Effect of Engineered Barrier Layer on Environmental Degradation | University of Idaho | $800,000.00 | The project goal is to apply friction stir based repair and mitigation technique for eliminating failure associated with pitting and stress corrosion cracking in dry storage canisters for spent fuels. The goal of these activities is to obtain a fundamental understanding of the processing-structure-properties correlations. This work will contribute to the development of a crack repair/mitigation strategy based on friction stir technology that can be efficiently implemented for spent fuel dry storage casks, which will enhance safety and reliability of these systems. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15263: X-ray Studies of Interfacial Molecular Complexes in ALSEP Back-Extraction | University of Illinois at Chicago | $800,000.00 | This project will use synchrotron X-rays to characterize the interfacial molecular complexes (of extractants and radiologically derived impurities, complexants, buffers, and metal ions) formed during the Actinide-Lanthanide Separation Process (ALSEP) back-extraction. This work addresses the critical knowledge gap of slow stripping kinetics in ALSEP, as well as the influence of radiolytic degradation products. The outcome of the project will be a molecular-level understanding of the role of different components in the interfacial mechanism of back-extraction in the ALSEP process, therefore leading to development of more efficient and faster metal stripping relevant to the separation of actinides from lanthanides in the nuclear fuel cycle. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15030: Mechanistic Understanding of Radiolytically Assisted Hydrothermal Corrosion of SiC in LWR Coolant Environments | University of Michigan | $800,000.00 | The objective of this project is to develop a mechanistic understanding of the hydrothermal corrosion behavior of monolithic SiC and SiC/SiC composites in LWR environment under the influence of water radiolysis products and radiation damage. Complementary atomistic simulations will be carried out to determine the rate controlling mechanisms for dissolution under different water chemistries and in the presence of radiation. Activation energies and kinetic rates will be calculated directly from these simulations and compared to experimentally fitted values. The dissolution rate constants determined and validated in this integrated experimental and modeling approach will allow predictions of long-term SiC corrosion behavior. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-14999: Probabilistic Failure Criterion of SiC/SiC Composites Under Multi-Axial Loading | University of Minnesota, Twin Cities | $800,000.00 | This project aims to develop a probabilistic failure criterion of SiC/SiC composites under multi-axial loading and to incorporate the criterion into a reliability analysis of the structural integrity of LWR SiC/SiC fuel cladding. This research will be anchored by a seamless integration of novel experimental and analytical tools, which will lead to a robust methodology for dependable analysis of SiC/SiC composite structures for LWR fuel cladding, as well as other nuclear applications. The resulting model will be experimentally validated and applied to analyze the reliability of LWR SiC/SiC fuel cladding. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15502: Reducing Uncertainty in Radionuclide Transport Prediction Using Multiple Environmental Tracers | University of Montana | $724,906.00 | In this project, direct modeling of multiple environmental tracers will be used to improve predictions of radionuclide transport in a shallow alluvial aquifer discharge. The research will take advantage of recent theoretical developments considering the use of environmental tracers, and advances in high-performance reactive flow and transport models, to obtain the maximum information on the transport system. The goal is to develop a new methodology to characterize natural reactive flow and transport systems, reduce predictive uncertainty in radionuclide transport simulations, determine the maximum information content of the tracer suite, and optimize future groundwater characterization efforts. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15578: Computational and Experimental Investigation of Thermal-Mechanical-Chemical Mechanisms of High-burnup Spent Nuclear Fuel (SNF) Processes at Elevated Temperatures and Degradation Behavior in Geologic Repositories | University of Nevada, Las Vegas | $800,000.00 | The overarching goal of this project is to use combined computational and experimental research and development activities to enhance understanding of the mechanisms and thermal-mechanical-chemical (TMC) parameters controlling the instant release fraction (IRF) and matrix dissolution of high-burnup (HB; burnup > 45 GWd/MTU) spent nuclear fuels (SNFs) and the subsequent formation, stability, and phase transformations of HB SNF alteration products under long-term storage and geological disposal conditions (e.g., high-temperature storage,-radiolysis). The results of this research will be used to enhance the mechanistic detail of process models to reduce uncertainty in, and improve the technical bases of, safety cases and performance assessment analyses. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15439: Radiolytic Dissolution Rate of Silicon Carbide | University of Notre Dame | $400,000.00 | This project seeks to develop a matrix of dissolution rates for high-purity SiC material, using intense electron beam irradiation, and to measure the products of dissolution (silicic acid and CO2 (or CO)) in the water downstream of the irradiation zone. The objective is to determine the rate of SiC dissolution and gather sufficient insight about its mechanism in LWRs, so that the use of SiC/SiC composite materials for accident tolerant fuel cladding can proceed with confidence. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15061: Development of an MC&A Toolbox for Liquid-fueled Molten Salt Reactors with Online Reprocessing | University of Tennessee at Knoxville | $799,207.00 | The purpose of this project is to develop a toolbox of swappable mass flow modules for liquid-fueled molten salt reactor (MSR) systems for the purposes of evaluating material control & accountancy measurement techniques. When combined together, these modules enable modeling of the time-dependent mass flows for a variety of MSR variants. The test platform will consist of a toolbox of independent process modules representing discrete physical units, each with its own self-contained physics responsive to the input mass flow, along with appropriate measurement models that can be coupled to key flow points. These dynamic physical signatures would allow testing of the viability and efficacy of potential accountancy techniques under the full range of reactor operating conditions. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15307: A Novel and Flexible Approach for Converting LWR UNF Fuel Into Forms That Can Be Used to Fuel a Variety of Gen-IV Reactors | University of Tennessee at Knoxville | $400,000.00 | This project will investigate the chemical decladding and the digestion of whole MOX-based fuel rods, using thionyl chloride and surrogate materials. Digesting entire LWR fuel assemblies results in product streams that include pure decontaminated ZrCl4; pure UCl4; and a stream containing TRU/FPs, as well as alloying metals (as chloride salts). The objectives of this project are to provide a new, highly efficient protocol for the transformation of used nuclear fuel into useful components and to effectively contain a concentrated stream of highly radioactive materials for appropriate handling. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15459: Reduced Diffusion and Enhanced Retention of Multiple Radionuclides from Pore Structure Studies of Barrier Materials for Enhanced Repository Performance | University of Texas at Arlington | $567,831.00 | The project seeks to better understand and quantify the pore structure (geometry and topology) and pore connectivity of porous media and its emergent effect on diffusion and retention of various radionuclides in barrier materials. The anticipated outcome of the project will be to more accurately evaluate the performance of geological repositories. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15649: Benchmarking Microscale Ductility Measurements | University of Utah | $776,669.00 | The objectives of this project are to establish best practices for obtaining tensile microscale ductility measurements and to validate methodologies for comparing them to macroscale ductility measurements. Anticipated outcomes of the project are: 1) measurement of grain and sub-grain localization processes micro and macroscales; 2) establishment of best practices for microtensile experimentation; 3) identification of statistically significant relationships between specimen geometry, microstructure variables and mechanical behavior; 4) modified phenomenological elongation-based ductility models to enable direct upscaling of ductility measurements from microscale to macroscopic. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15003: Advanced Coating and Surface Modification Technologies for SiC-SiC Composite for Hydrothermal Corrosion Protection in LWR | University of Wisconsin-Madison | $799,990.00 | This project focuses on the development of coatings and surface modification approaches for hydrothermal corrosion protection of SiC-SiC composite in normal LWR operation environments. Innovative surface treatment recipes will be explored using processes including, interfacial stitching to improve adhesion, multi-layered structures to improve ductility, and compositions and structures resulting from thermal treatments. The surface treatment concepts involve corrosion resistant metallic and ceramic materials, and are amenable to industrial scalability for the cladding application. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15332: Low-Force Solid-State Technologies for Mitigation of Stress Corrosion Cracking in Dry Storage Canisters | University of Wisconsin-Madison | $800,000.00 | This project will focus on evaluating and developing two technologies used for field mitigation and repair of stress corrosion cracking (SCC): 1) additive friction stir welding; and 2) cold spray deposition. The work involves developing low-force, low-heat input solid state technologies to lessen and repair SCC in stainless steel canisters for used nuclear fuel (UNF). This outcome of the study will inform feasibility of using the two technologies to conduct on-site field repairs. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-14913: The Role of Temperature on Non-Darcian Flows in Engineered Clay Barriers | Virginia Polytechnic Institute and State University | $800,000.00 | This project intends to accomplish three tasks: 1) to develop a predictive model to facilitate experimental data interpretation and provide mechanistic insights into the role of temperature on non-Darcian flows in low-permeability engineered clay barriers; 2) conduct experiments to unravel the role of temperature on the threshold gradient of non-Darcian flow in both saturated and unsaturated bentonite; and 3) use molecular dynamics (MD) simulation to improve fundamental understanding. The experimental data, associated with the MD simulation, will provide valuable information to improve fundamental understanding and scientific knowledge with respect to the temperature dependence of threshold gradient in non-Darcian flows, because very limited experimental data for saturated flow and no experimental data for unsaturated flow are available. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-14815: C-SiOC-SiC Coated Particle Fuels for Advanced Nuclear Reactors | Virginia Polytechnic Institute and State University | $400,000.00 | This project will study a new concept for nuclear fuel encapsulation using an amorphous SiOC plus carbon system as the inner coating and nanocrystalline SiC plus minor carbon as the outer coating for nuclear fuel kernel particles. The outcomes of this work are: 1) new directions and possible replacement guidance for current nuclear fuel materials in operation; 2) new fuel materials for future nuclear reactor material design and development; 3) nuclear composite microstructure evolution and performance degradation understanding; 4) screening tools to guide future nuclear fuel material activities; and 5) mechanisms of nuclear fuel material evolution and degradation and effective strategies to mitigate/reduce undesirable fuel behaviors. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15226: An Evaluated, Transient Experiment based on Simultaneous, 3-D Neutron-Flux and Temperature Measurements | Kansas State University | $399,972.00 | This project will evaluate existing and near-term experimental data for inclusion in the International Reactor Physics Experiment Evaluation Project (IRPhEP) handbook. The data to be evaluated include compositions from a recent fuel replacement as part of an LEU conversion, a number of critical, fresh-fuel configurations, fuel temperature measurements at fresh-fuel configurations, and records from nearly a decade of operation. The proposed work would lead to a first-of-a-kind evaluation of transient, spatially-dependent reaction rates. | Nuclear Energy | FY2018 | |
| NEUP Project CFA-18-15773: Evaluation of the Thermal Scattering Law for Advanced Reactor Neutron Moderators and Reflectors | North Carolina State University | $398,821.00 | The objective of this project is to narrow the nuclear data gap for advanced nuclear reactors that are driven by thermal neutrons. This includes concepts such as gas-cooled high-temperature reactors and molten salt or salt-cooled high temperature reactors. The generated data TSL libraries will be provided in EDNF File 7 format to the National Nuclear Data Center (NDDC) to immediately include in beta releases of the ENDF/B libraries and to consider for the future release of ENDF/B-VIII.1. | Nuclear Energy | FY2018 | |
| NEUP Project 18-15602: Modeling and Experimental Verification of Thermal Energy Storage Systems to Enable Load Following Capability for Nuclear Reactors | University of Idaho | $761,640.00 | This project purposes to integrate new thermal energy storage (TES) models, developed in Modelica, with ongoing nuclear-renewable hybrid energy systems (NRHES) modeling efforts, in order to evaluate economic potential and advantages of new process designs over baseload electricity production. The computational phase of this project includes developing mathematical and physics-based TES models, which could later be translated to Modelica and integrated with existing NRHES components. The testing and optimization would be conducted using RAVEN. A techno-economic analysis will be performed to evaluate the compatibility of the newly formed integration, as well as to quantify its feasibility and economic benefits. The experimental aspect is focused on the development of scaled TES systems, which serve as verification for the Modelica models and allow system testing upon being integrated with DETAIL. | Nuclear Energy | FY2018 | |
| NEUP Project 18-14963: Development of Nuclear Hybrid Energy Systems: Temperature Amplification through Chemical Heat Pumps for Industrial Applications | University of Idaho | $800,000.00 | The overall goal of this project is to develop and demonstrate, through modeling and experimental investigations, temperature amplification capabilities of a chemical heat pump (CHP) system that can be coupled to a conventional light water reactor or a near-term small modular reactor. The outcomes would include nuclear hybrid energy system architecture containing a CHP, experimental data on the CHP performance, and dynamic model of the system, validated through experimentation, which could be used for scale-up and design. | Nuclear Energy | FY2018 | |
| NEUP Project 18-15008: Development of Thermal Inelastic Scattering Covariance Data Capabilities with Demonstration of Light Water Evaluation | University of Michigan | $400,000.00 | The goal of this project is to produce a format for covariance data for inelastic thermal neutron scattering data for moderators in the ENDF format. To demonstrate the viability of this new format, an evaluation of the covariance data for thermal scattering in light water in this format will be produced, along with the capabilities to generate the files and test their efficacy. A capability for calculating sensitivity coefficients using multigroup methods to the fundamental physics parameters governing light-water scattering will be developed to facilitate identifying nuclear data needs related to thermal scattering. | Nuclear Energy | FY2018 | |
| NEUP Project 18-15056: Model-Based Diagnostics and Mitigation of Cyber Threats | University of Michigan | $800,000.00 | This project intends to develop a toolkit for modeling digital instrumentation and control (I&C) systems for nuclear power plants so that the consequences of cyber-attacks on I&C systems may conveniently be modeled using nuclear plant simulation software. The results of the toolkit-based models, the corresponding responses, and the performance of the diagnostic schemes will be tested on a virtual control room driven by a plant simulator. | Nuclear Energy | FY2018 | |
| NEUP Project 18-15055: NICSim: Nuclear Instrumentation and Control Simulation for Evaluating Response to Cyber-attacks | University of New Mexico | $799,945.00 | The objective of the project is to develop a Nuclear Instrumentation and Control Simulation (NICSim) platform with a novel emulytics capability to simulate control systems and components in nuclear power plants. The outcome of this work would be a first-in-class emulytics platform with an associated documentation and library of physical models of components that could be used by analysts and designers to assess the resilience and cybersecurity risks of different control system designs for a wide range of power plants. | Nuclear Energy | FY2018 | |
| NEUP Project 18-15324: Validation of Pressure Relaxation Coefficient in RELAP-7 Seven-Equation Model | George Washington University | $800,000.00 | This project aims to validate the Seven-Equation model in RELAP-7 by: 1) measuring velocity and pressure in each phase and the interface as well as return to equilibrium in fast transients with high-speed non-intrusive laser diagnostics in canonical experiments; 2) complementing experimental data with a multiscale computational approach, including a 3D proprietary direct numerical solver; and 3) validating RELAP-7 with a combination of experimental data and first-principle simulations. This combination would provide unique and complete datasets to validate RELAP-7 with high confidence and offer a new class of experimental and numerical tools. | NEAMS | FY2018 | |
| NEUP Project CFA-18-15104: Demonstration of Utilization of High-fidelity NEAMS Tools to Inform the Improved Use of Conventional Tools within the NEAMS Workbench on the NEA/OECD C5G7-TD Benchmark | North Carolina State University | $800,000.00 | The goal of this project is to demonstrate the utilization of high-fidelity Nuclear Energy Advanced Modeling and Simulation (NEAMS) tools (PROTEUS, Nek5000, and BISON) to inform the improved use of conventional tools (DIF-3D, CTF, and CTFFuel) within the NEAMS Workbench on the NEA/OECD C5G7-TD benchmark. This would result in more accurate predictions of safety parameters and margins, which is important for both safety and performance improvements of the nuclear power plants being currently operated and built. The developed Workbench-based framework will also assist end users to apply high-fidelity simulations to inform lower-order models for the design, analysis, and licensing of advanced nuclear systems. | NEAMS | FY2018 | |
| NEUP Project 18-14741: Demonstration of a Methodology for Direct Validation of MARMOT Irradiation-Induced Microstructural Evolution and Physical Property Models Using U-10Zr | Texas A&M University | $500,000.00 | The objective of this project is to demonstrate, for the first time, a methodology that enables the direct validation of microstructural evolution models for fuel in MARMOT, and the direct correlation of changes in physical properties with specific irradiation-induced microstructural features. Properly implementing this methodology will result in rapid development of MARMOT mesoscale models. | NEAMS | FY2018 | |
| NEUP Project 18-15520: Accurate and Efficient Parametric Model-Order Reduction for Turbulent Thermal Transport | University of Illinois at Urbana-Champaign | $800,000.00 | The project objective is to develop reduced-order models (ROMs) that will improve accuracy of LMR system-level analysis with low overhead. These new models will systematically mine high-fidelity DNS, LES, or uRANS simulations to construct low-order dynamical systems that can couple with a systems analysis code, such as the SAM code being developed under NEAMS. These simulations provide useful data and will be made available to the scientific community, and the overall effort will contribute to more efficient LMR conceptual design studies and licensing. | NEAMS | FY2018 | |
| NEUP Project 18-15484: A Novel High Fidelity Continuous-energy tTansport Tool for Efficient FHR Transient Calculations | Georgia Institute of Technology | $800,000.00 | The objective of the project is to develop a high-fidelity continuous energy (CE) transport tool for efficient transient calculations in fluoride salt-cooled high-temperature reactors with prismatic core/fuel assembly design. This will be accomplished by extending the high-fidelity 3-D continuous energy coarse mesh radiation transport (COMET) code with formidable computational speed to solve transient problems in FHRs with accurate thermal hydraulic feedback. The new capability would enable plant system codes to perform analyses necessary to address complex technical design, regulatory, reactor safety, and economic hurdles prior to construction. | RCRD&D | FY2018 | |
| NEUP Project 18-15093: Determination of Molecular Structure and Dynamics of Molten Salts by Advanced Neutron and X-ray Scattering Measurements and Computer Modeling | Massachusetts Institute of Technology | $800,000.00 | This project will seek detailed knowledge about molecular structure and dynamics of molten salts to inform the design of new molten-salt reactors. A combination of advanced neutron and x-ray scattering and ab initio molecular dynamics simulations will be used to model the ionic-cluster structure of the fluid and solubility of impurities. Machine learning will be applied to regress from simulations and experiments in order to develop the model and predict chemical potentials as a function of composition and temperature. | RCRD&D | FY2018 | |
| NEUP Project 18-15171: Oxidation Behavior of Silicon Carbide and Graphitic Materials | Missouri University of Science and Technology | $800,000.00 | The objectives of this project are to determine the oxidation behavior of silicon carbide and graphitic materials in oxygen and/or moisture, to accurately measure the kinetic parameters of oxidation, to ascertain the oxidation mechanisms in relation to the microstructures, to determine the effect of irradiation on oxidation behavior, and to provide data and input to the safety analysis of high-temperature gas reactors under air and moisture ingress accident conditions. | RCRD&D | FY2018 | |
| NEUP Project 18-15276: Coping Time and Cost Analysis of Accident Tolerant Plant Design based on Dynamic PRA Methodology | Rensselaer Polytechnic Institute | $800,000.00 | This project will evaluate the failure modes of accident tolerant fuel ATF candidates to understand the different failure characteristics. The research aims to obtain a response surface of coping time by investigating the various uncertainties of accident mitigation in PWR and BWR reactors. These outputs will aid the decision making process on the implementation of ATF and FLEX to existing LWR plants from the perspective of risk reduction and economic feasibility. | RCRD&D | FY2018 | |
| NEUP Project 18-15270: Innovative Use of Accident Tolerant Fuels (ATF) with the RCIC System to Enhance Passive Safety of Commercial LWRs | Texas A&M University | $748,000.00 | The overarching objectives of this project are to: 1) demonstrate new operational strategies with the combined use of Accident Tolerant Fuels (ATF) and the Reactor Core Isolation Cooling (RCIC) System to increase the passive safety capabilities of current Boiling Water Reactors (BWRs) in delaying or preventing core damage; and 2) pursue the delay of containment venting until after a 72-hour coping period through new BWR Suppression Pool mixing procedures. The research will use both simulation and experimental data to validate the objectives. The work has the potential to increase the ability of existing nuclear power plants to passively respond to beyond design basis events using existing equipment and without changes to the plants. | RCRD&D | FY2018 | |
| NEUP Project 18-15346: Big Data For Operation and Maintenance Cost Reduction | The Ohio State University | $800,000.00 | This project will develop a first-of-a-kind framework for integrating Big Data capability into the daily activities of our current fleet of nuclear power plants. This research will mainly focus on incorporating the wide range of data heterogeneities in nuclear power plants into an integrated Big Data Analytics capability. The primary end product of this work will be a Big Data framework that is capable of dealing with the large volume and heterogeneity of the data found in nuclear power plants to extract timely and valuable information on equipment performance and to enable optimization of plant operation and maintenance based on the extracted information. | RCRD&D | FY2018 | |
| NEUP Project 18-15065: in situ Measurement and Validation of Uranium Molten Salt Properties at Operationally Relevant Temperatures | University of Connecticut | $799,979.00 | This project proposes to use advanced spectroscopic and scattering methods to provide information at the atomic and molecular scale. The research will use synchrotron-based x-ray absorption fine structure (XAFS) spectroscopy and Raman spectroscopy, at operationally relevant temperatures, to measure the local and intermediate structure as well as speciation of chloride fuel salts (NaCl, ZrCl, UCl3) for fast-spectrum applications and fluoride fuel salts ( 7 LiF, UF4) primarily for thermal spectrum applications This approach is expected to generate theories and concepts that would allow models to predict behavior, and develop the means for in situ monitoring. | RCRD&D | FY2018 | |
| NEUP Project 18-15058: High-resolution Experiments for Extended LOFC and Steam Ingress Accidents in HTGRs | University of Michigan | $800,000.00 | The objective of this project is to better understand key phenomena in high-temperature gas-cooled reactors relevant to steam ingress and loss of forced circulation (LOFC) accidents. Specifically, the research will: 1) experimentally investigate, using an existing integral-effect test facility with some improvements, the steam-ingress accident caused by a postulated steam generator tube rupture initiating event; 2) carry out integral-effect tests for the extended LOFC accident to study the establishment of global natural circulation flow in the primary loop; 3) design, based on a scaling analysis, and construct a separate-effect test facility to study the complex helium flows in the core and hot plenum during the extended LOFC accident; and 4) perform detailed, high-resolution, separate-effects experiments using the results obtained as boundary/initial conditions. | RCRD&D | FY2018 | |
| NEUP Project 18-15471: Integral Experimental Investigation of Radioisotope Retention in Flowing Lead for the Mechanistic Source Term Evaluation of Lead Cooled Fast Reactor | University of New Mexico | $800,000.00 | The purpose of this project is to experimentally investigate the integral effects of radioisotope interactions with liquid lead to support the following technical goals: 1) evaluating the mechanistic source term of the Lead-cooled Fast Reactor (LFR); 2) developing a universal integral effect test methodology for liquid metal source term evaluations; and 3) establishing a basis for the comparison of radioisotope retention between lead and sodium. This aim of the research is to advance the LFR licensing pathway by establishing the phenomenological foundation of the interaction between fission products and liquid lead. | RCRD&D | FY2018 | |
| NEUP Project 18-15153: Understanding Molten Salt Chemistry Relevant to Advanced Molten Salt Reactors through Complementary Synthesis, Spectroscopy, and Modeling | University of Tennessee at Knoxville | $800,000.00 | The goal of the proposed research is to understand molten salt chemistry relevant to advanced molten salt reactors through complementary synthesis, spectroscopy, and modeling. Through complementary synthetic, spectroscopic, and computational efforts, the aim is to achieve atomistic and molecular-level understanding of liquid structure, coordination geometry, chemical bonding, and reactivity of novel molten salt melts relevant to advanced molten reactor designs. | RCRD&D | FY2018 | |
| NEUP Project 18-15111: Improving Nuclear Power Plant Efficiency Through Data Analytics | University of Tennessee at Knoxville | $799,727.00 | This project aims to develop and provide data analytics solutions to improve nuclear power plan economic efficiency by utilizing empirical models to integrate disparate data sources while providing uncertainty estimates to quantify risk and support decisions. The outcomes will enhance the technical and economic competitiveness by enabling advanced monitoring of critical assets, improving the operating capability of the existing fleet, and helping achieve enhancements in organizational effectiveness. Additionally, the research would provide an agile and modular data analytic framework that would have high commercialization value and supports the industry-wide drive towards digital innovation. | RCRD&D | FY2018 | |
| NEUP Project 18-14846: Development of Corrosion Resistant Coatings and Liners for Structural Materials for Liquid Fueled Molten Salts Reactors | University of Wisconsin-Madison | $800,000.00 | The goal of the proposed research is to develop corrosion-resistant coatings and liners for structural materials for use in fuel dissolved molten salt environment for future Molten Salt Reactors (MSRs). Innovative, but industrially scalable, surface cladding approaches are proposed to lead to promising surface and interfacial compositions. The processes themselves are commercial, and have high technology readiness levels, and consequently would facilitate the accelerated developments of MSRs. | RCRD&D | FY2018 | |
| NEUP Project 18-15280: Advanced Alloy Innovations for Structural Components of Molten Salt Reactors | University of Wisconsin-Madison | $796,792.00 | The goal of the proposed research is to develop and evaluate specific advanced metallic alloys for structural components in fluoride salt-cooled molten salt reactors (MSRs). The research will investigate four categories of metallic alloys: advanced Ni-based; radiation damage tolerant high entropy; refractory Mo-based, and compositionally-graded, designed for high-surface corrosion resistance and good bulk strength. Additionally, the propensity for radiation embrittlement, as well as weldability, of the alloys will be evaluated. | RCRD&D | FY2018 | |
| NEUP Project 18-14957: Big Data Analytics Solutions to Improve Nuclear Power Plant Efficiency: Online Monitoring, Visualization, Prognosis, and Maintenance Decision Making | University of Wisconsin-Madison | $797,820.00 | The overarching goal of this project is to significantly advance the ability to assess equipment condition and predict the remaining useful life to support optimal maintenance decision making in nuclear power plants. This research will work toward accomplishing and establishing a modern set of data-driven modeling, online monitoring, visualization, prognosis, and operation decision-making methodologies to address the significant opportunities and challenges arising from the emerging data-rich environment in nuclear plants. The potential impact of the work is significant and transformative and could deliver important advances in productivity with reduced unscheduled downtime and improved equipment performance. | RCRD&D | FY2018 | |
| NEUP Project 18-15097: Oxidation Study of High Temperature Gas-Cooled Reactor TRISO Fuels at Accidental Conditions | Virginia Polytechnic Institute and State University | $800,000.00 | This project is to study the oxidation behaviors of TRISO fuels during accidental air and water vapor ingress conditions. The work focuses on the oxidation and burn-off of the graphite fuel matrix and oxidation of the TRISO fuel SiC layer at high-temperature accidental states in the presence of air and/or water vapor. It will include both unirradiated and irradiated graphite fuel matrix and simulated fuel particles with the SiC layer. | RCRD&D | FY2018 |
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 | |
|---|---|---|---|---|---|---|
| Understanding PM-HIP Interparticle Evolution and its Influence on Fracture Toughness in Alumina-Forming Steels | Purdue University | $1,100,000 | This project aims to understand how interparticle evolution during hot isostatic pressing (HIP) influences fracture toughness of Al-bearing steels. The team will use a series of interrupted HIP experiments with phase field models to understand the formation mechanisms of interparticle defects during HIP of alumina-forming austenitic (AFA) stainless steels and FeCrAl steels, and the influence of these defects on fracture behavior. | Document | Advanced Manufacturing Technologies | FY2024 |
| Multiscale high-throughput experiment/modeling approach to understanding creep behavior in Additively Manufactured reactor steels | University of Minnesota, Twin Cities | $1,043,271 | This project proposes to develop a predictive capability for processing-microstructure-property correlations in additive manufactured microstructures utilizing a multiscale approach encompassing bulk creep tests, miniaturized tensile testing, and a high-throughput, indentation based, cost-effective method for elevated temperature mechanical mapping of additively manufactured 316H Stainless Steel, Grade 91, and Titanium-Zirconium-Molybdenum (TZM) alloys. | Document | Advanced Manufacturing Technologies | FY2024 |
| Hi-fidelity characterization of molten salt-graphite pore interactions through experiments and embedded modeling | North Carolina State University | $1,100,000 | We propose a suite of fuel salt (FLiBe + U) infiltration experiments (University of Michigan-UM) followed by X-ray computed tomography, XCT (NCSU), in-situ mechanical property evaluation with scanning electron microscopy (NCSU) and high fidelity data analytics and modeling (NCSU/Leeds) along with complimentary porosimetry measurements (ORNL) and XPS analysis at University of Manchester (UoM). Three graphite grades are selected in this project: NBG-18, IG-110 and POCO: ZXF-5Q. | Document | Advanced Nuclear Materials | FY2024 |
| Assessing molten salt corrosion resistance of stainless steel 316H in nuclear reactor environments | North Carolina State University | $1,100,000 | The proposed goal is to leverage a blend of innovative molten salt corrosion experiments and cutting-edge characterization techniques to advance our understanding of molten salt corrosion in both commercial and additively manufactured (AM) stainless steel (SS) 316H, particularly under radiation or stress environments. | Document | Advanced Nuclear Materials | FY2024 |
| Polymer-Derived C-SiC Coatings on Kernel Particles for Advanced Nuclear Reactors | University of Alabama at Birmingham | $1,100,000 | This program is to use a polymer-derived ceramic approach to develop C-SiC/ZrC coatings on ZrO2 kernel substitute particles. We aim to create new fuel encapsulation materials in replacement of the coatings on fuel kernel particles, including the TRISO layers, for advanced reactors, conduct ion irradiation testing of the new materials for nuclear performance evaluation, and carry out detailed microstructure and composition characterization to assess the C-SiC/ZrC coated fuel particle behaviors. | Document | Advanced Nuclear Materials | FY2024 |
| Sorbent regeneration, recycling, and transformation: A transformative approach to iodine capture and immobilization | University of Nevada, Reno | $1,000,000 | The project will focus on the development of materials and processes for regeneration and recycling of sorbents, and the transformation of iodine-loaded sorbents into waste forms. A combination of computational and experimental studies will be conducted to understand (a) how the components in a primary off-gas stream interact with the sorbent, (b) how this off-gas stream affects the regeneration lifetime, and (c) low-temperature binders and processing paths that leads to durable waste forms. | Document | Advanced Nuclear Materials | FY2024 |
| Developing place-based understandings of respectful community engagement for consent-based siting | University of Michigan | $1,100,000 | Through this project we seek to develop (1) guiding principles for respectful community engagement-to support consent-based siting-empirically rooted in the lived experiences of Native Communities; (2) metrics and indicators of consent; and (3) a generative AI tool to facilitate community-based storytelling of the past and imagining of the future to visualize how nuclear infrastructures have and could in the future alter community landscapes. | Document | Consent-based Siting for SNF Management | FY2024 |
| Informing Consent-Based Siting of a Consolidated Interim Storage Facility (CISF): Examining Public Engagement Through History and Evaluation of Prior & Current Outreach Results | Vanderbilt University | $1,000,000 | We will use two phases of research to assist NE in understanding factors that influence the quality and extent of public engagement needed to address different people and communities seeking to make decisions regarding the siting of a CISF. Supporting NE's the consent-based siting process we have developed an accelerated 2-year schedule, focusing on three geographic areas of the US: IL, TX & NM and the area served by the TVA/Duke Power Ñeach contain multiple SNF storage facilities. | Document | Consent-based Siting for SNF Management | FY2024 |
| Accident Tolerant Fuels to Support Power Uprates in LWRs | University of Wisconsin-Madison | $1,100,000 | This project will demonstrate that power uprates higher than the current state of operation can be reached using accident tolerant fuels in light water reactors while not exceeding reactor safety margins during normal operation and accidents. We will analyze it considering fuel enriched up to 10% and peak rod average burnup up to 75GWd/tU concerning reactor physics, thermal-hydraulics, reactor safety, and economics. Considerations will be made in consultation with the named industry advisory board. | Document | Existing Plant Optimization | FY2024 |
| Comparative study of three-dimensional microstructural imaging and thermal conductivity evolution of irradiated solid and annular U-Zr fuels | Massachusetts Institute of Technology | $1,000,000 | Uranium-zirconium (U-Zr) annular metallic fuel holds the promise to simultaneously increase sodium fast reactor (SFR) core uranium loading and reduce peak cladding temperatures, thus greatly improving fuel performance. However, key convolved fuel degradation mechanisms during irradiation at temperature threaten to hold back its real-world applicability, requiring more detailed understanding to both predict U-Zr fuel performance and suggest improvements. | Document | Fuels | FY2024 |
| Mechanistic study and modeling of fission gas release in UO2 and doped UO2 | Oregon State University | $1,000,000 | The objective of this project is to enhance the safety and performance of light water reactors and other advanced reactor designs by gaining a fundamental understanding of fast gas reactor mechanisms and developing mechanistic models for UO2 and doped UO2 fuels under HBU and transient conditions. | Document | Fuels | FY2024 |
| Anisotropic Thermal Properties of SiC-SiC Cladding: Method Development & Characterization | University of Pittsburgh | $1,000,000 | We propose to develop a high-temperature nondestructive thermal conductivity (k) measurement system coupled with validated multiscale models to accurately determine the anisotropic thermal conductivity of SiC-SiC composite cladding tubes. The multiscale measurement and modeling results benefit both DOE ATF programs as well as providing a fundamental understanding of how the microstructure of the composite leads to its anisotropic properties. | Document | Fuels | FY2024 |
| Understanding the Performance of SiC-SiCf Composite Cladding Architectures with Cr Coating in Normal Operating and Accident Conditions in LWRs and Advanced Reactors | University of Wisconsin-Madison | $1,000,000 | The project will focus on investigating the impact of Cr-coating on the SiC-SiCf composite cladding of various architectures under normal operating and accident conditions in light water reactors and advanced reactors for the safe and economic deployment of SiC cladding. Cr-coating will provide protection from high-temperature corrosion and better hermeticity under accident conditions. The performance of the claddings will be evaluated through the corrosion test, reflood test, burst test, and non-destructive evaluation(NDE). | Document | Fuels | FY2024 |
| Developing critical insights on the effects of Mo on a' precipitation and dislocation loop formation in FeCrAl alloys | University of Wisconsin-Madison | $1,000,000 | This project aims at developing a mechanistic understanding on the effects of Mo on a' precipitation and dislocation loop formation in FeCrAl alloys in thermal and irradiation conditions and turns it into a set of design principles guiding further optimization, by integrating atomistic simulations, CALPHAD modeling, thermal aging, proton irradiation, and advanced characterization. The material discoveries will be generalized to other solutes other than Mo. | Document | Fuels | FY2024 |
| Inference of flow conditions from in-core detector measurements for accelerating SMR licensing | Massachusetts Institute of Technology | $1,000,000 | Reactor modelling relies on the detailed description of reactor systems but often lacks the true as-built characteristics of a system. This proposal seeks to fill these geometrical data gaps using available detector data, predictive models and machine learning in order to provide better information to analysis tools and thus better prediction of future performance. | Document | Licensing, Safety, and Security | FY2024 |
| Taggants in Future Nuclear Fuels by Design as an Enabling Technology to Track Nuclear Materials | Rensselaer Polytechnic Institute | $1,000,000 | The overarching goal of this project is to develop an innovative materials accounting and control technology by adopting an approach of "safeguard by design" during fuel fabrication to fill nuclear control technology gaps in tracing and tracking nuclear fuels for advanced nuclear reactors. The project is based on a concept of "taggants in fuels" that can greatly increase forensic attributes, and enhance intrinsic proliferation resistance and MPACT effectiveness for advanced nuclear fuel cycles. | Document | Licensing, Safety, and Security | FY2024 |
| Non-Destructive Plutonium Assay in Pyroprocessing Bulk Materials with a 3D Boron-Coated-Straw Detector Array | University of Illinois at Urbana-Champaign | $1,100,000 | The objective of the proposed project is to develop and demonstrate a 3D boron-coated-straw detector array (3D-BCSDA) with high efficiency and spatial resolution. This detection system will be specifically designed to accurately assess the fissile mass in bulk nuclear material during pyroprocessing operations, thereby improving the precision and reliability of accountability measurements during separation. | Document | Licensing, Safety, and Security | FY2024 |
| Improving the computational efficiency and usability of dynamic PRA with reinforcement learning | University of Maryland, College Park | $1,064,400 | The overall objective of the proposed research is to improve the efficiency and usability of dynamic probabilistic risk assessment (PRA). Specifically, the first objective is to develop a new algorithm for dynamic PRA analysis that can significantly increase the computational efficiency. The second objective is to develop a question-answering system to streamline the process of risk-informed decision-making based on results obtained from the dynamic PRA analysis using the new algorithm. | Document | Licensing, Safety, and Security | FY2024 |
| Development of a Benchmark Model for the Near Real-Time Radionuclide Composition Measurement System using Microcalorimetry for Advanced Reactors | Virginia Commonwealth University | $1,100,000 | The primary goal of this proposed project is to develop high fidelity Monte Carlo radiation transport models of a microcalorimetry detector informed by fuel depletion models of a molten salt reactor and a pebble bed reactor to quantify the current and future capabilities of this detector technology to characterize and assay used fuel from these reactors in near real-time. | Document | Licensing, Safety, and Security | FY2024 |
| Concurrent Surrogate Model Development with Uncertainty Quantification in the MOOSE Framework Using Physics-Informed Gaussian-Process Machine Learning | University of Florida | $999,999 | The objective of this project is to develop a general capability for concurrent generation and use of physics-informed Gaussian process (GP)-based surrogate models to facilitate multiscale and multiphysics modeling. We will implement this new capability as part of the Multiphysics Object-Oriented Simulation Environment (MOOSE) so that every application based on the MOOSE framework will have access to it. | Document | Modeling and Simulation | FY2024 |
| Unstructured Adaptive Mesh Algorithms for Monte Carlo Transport | University of Illinois at Urbana-Champaign | $1,098,000 | We propose to develop the fundamental methods and techniques for unstructured adaptive mesh refinement with Monte Carlo tallies. This work enables a transformative leap forward in speed, accuracy, and robustness to enhance the contribution of high-fidelity radiation transport to advanced simulation. Adaptive refinement is deployed on a challenging multiphysics simulation, cascading heat pipe failure, to study acceleration and stabilization properties. | Document | Modeling and Simulation | FY2024 |
| Feasibility Study of Micro-Nuclear Reactor Thermal Output for Air Rotary Kilns in the High-Temperature Manufacturing of Portland Cement Clinker | Pennsylvania State University | $998,793 | This project aims to design and test a micro-nuclear reactor for high-temperature portland cement clinker production, a process responsible for 6%-8% of global CO2 emissions. Leveraging advanced reactors' heat output, the project explores TRISO-based nuclear microreactor core modifications and new working fluids for heat pipes. The research addresses uncertainties in micro-nuclear reactor deployment for clinker production and investigates high-efficiency heat exchanger designs. | Document | Non-Traditional and Non-electric Applications | FY2024 |
| Redox potential, ionic speciation, and separation and recovery challenges from molten salts containing actinides and fission products | Massachusetts Institute of Technology | $999,999 | Establishing an efficient, safe, secure, and economical Molten-Salt Reactor (MSR) fuel cycle is imperative for MSR implementation. Molten salt fuel recycling technology requires predictive knowledge of the chemical and physical behavior of lanthanide and actinide ions with different oxidation states dissolved in solvent salts. A combination of off-gas and X-ray measurements with machine-learning simulations will be used to produce predictive modeling of separation and recovery conditions. | Document | Nuclear Fuel Recycle Technologies | FY2024 |
| Pre-Treatment and Bulk Separation of Used Fuels with Carbonate-Peroxide Solutions | Pennsylvania State University | $1,000,000 | To use carbonate-peroxide chemistries to develop a pre-processing method for used uranium-based fuels that enables the subsequent use and optimization of current solvent extraction reprocessing schemes. Using simple precipitation, this innovative method provides an initial, bulk separation of uranium from fission products and actinides. | Document | Nuclear Fuel Recycle Technologies | FY2024 |
| Optimization of Fueling Strategies and Material Surveillance through Real-time Pebble Tracking in Pebble Bed Reactors | University of Illinois at Urbana-Champaign | $1,100,000 | Flexible operation of the energy grid of the future introduces uncertainty in determining the optimal operating conditions of Pebble Bed Reactors. The proposed work will help to address these challenges and enable more economical operation by providing the tools to determine of optimal fuel reloading strategy through pebble identification and tracking. | Document | Reactor Development and Plant Optimization | FY2024 |
| Effects of Tritium-Graphite Interactions on Safety Transients in Graphite-Moderated Nuclear Reactors. | University of Illinois at Urbana-Champaign | $1,000,000 | MSRs, FHRs, and HTGRs have tritium production rates 10 to 10,000 times larger than LWRs. Objective of this project is to:-Quantify the concentration of tritium in graphite in new generation FHRs and HTGRs as a function of time and operational conditions-Assess the impact of the tritium content in graphite on reactor physics during normal operations and safety transients-Quantify tritium release rates and release kinetics during reactor transients inducing temperature increases | Document | Reactor Development and Plant Optimization | FY2024 |
| Experimental Study and Computational Modeling of P-LOFC and D-LOFC Accidents in the Fast Modular Reactor Consisting of Silicon Carbide Composite Rods | University of Michigan | $1,100,000 | The primary objectives of this proposed research are to better understand NC flow phenomena and heat transfer under both D-LOFC and P-LOFC accidents in the FMR, produce experimental data in a well-scaled integral-effects test facility for the two accidents, and develop and validate predictive CFD models for NC flow phenomena in both accidents. | Document | Reactor Development and Plant Optimization | FY2024 |
| Sodium heat pipes; design and failure mode assessment for micro-reactor applications | University of Wisconsin-Madison | $1,000,000 | The present proposal aims to experimentally investigate the thermal-hydraulics performance of liquid sodium heat pipes applied to microreactors, with a focus on exploring different design parameters, effects of different parameters on operating performance and understanding the evolution and impact of different failure modes. | Document | Reactor Development and Plant Optimization | FY2024 |
| Interfacial Interactions between Graphite and Molten Fluoride Fuel Salt | Virginia Polytechnic Institute and State University | $1,000,000 | NaF-KF-UF4 fuel salt will be selected to study graphite-salt interactions and impact of the existence of fission products (FPs) and corrosion products on the interactions at different temperatures and pressures. Fundamental mechanisms of graphite-salt interaction and degradation will be understood. | Document | Reactor Development and Plant Optimization | FY2024 |
| AI to Guide Sorption Data Acquisition and Assimilation into Uncertainty Quantifications for the Nuclear Waste Disposal Performance Assessment | Massachusetts Institute of Technology | $800,000 | The objective of this project is to develop machine learning (ML) and AI toolsets to effectively expand the global sorption database-the datasets collected by multiple institutions around the world-and to assimilate these datasets into the uncertainty quantification (UQ) in the performance assessment (PA) of nuclear waste repositories. | Document | Spent Fuel, Waste Science & Technology and Integrated Waste Management System | FY2024 |
| Local resonance-based linear and nonlinear NDE techniques for repaired DSC wall structures | University of Illinois at Urbana-Champaign | $1,000,000 | The proposed work plan will develop nondestructive examination (NDE) methods that develop and evaluate linear and nonlinear resonant ultrasound spectroscopy methods (such as NRUS, NIRAS, etc.) to cold spray (CS) repaired dry shielded canister (DSC) wall structures. With the support of our partners from Pacific Northwest National Laboratory (PNNL) and Oak Ridge National Laboratory (ORNL), we will perform technology development and validation on plain and cold spray-repaired DSC wall specimens. | Document | Spent Fuel, Waste Science & Technology and Integrated Waste Management System | FY2024 |
| Thermodynamic Models for Multivalent Actinide Solubility and Speciation as a Function of Temperature and Ionic Strength | University of Notre Dame | $1,000,000 | This proposed project will quantify the solubility and speciation of Np and Pu under temperatures, ionic strengths, and pH values that are relevant to the generic repository concept. The major deliverable will be full thermodynamic descriptions of the studied systems, which will lead to improved radionuclide transport models and support the development of a sound technical basis for the geologic disposal of spent nuclear fuel and other actinide-bearing wastes. | Document | Spent Fuel, Waste Science & Technology and Integrated Waste Management System | FY2024 |
| Advancing Fundamental Molten Salt Modeling using Ultrafast Spectroscopy | North Carolina State University | $600,000 | The overarching goal of the proposed research is to advance our fundamental understanding of molten salts by combining ultrafast spectroscopic experiments with high fidelity atomistic simulations. The proposed research will introduce a new experimental technique to the study of molten salts that will directly measure ion kinetics, specifically, terahertz time-domain spectroscopy (THz-TDS), which will further validate AIMD as a predictive modeling tool. | Document | Strategic Needs Blue Sky | FY2024 |
| Hydrodynamics of Two-Phase Flow Under the Geometric Effects of Pipe Orientation and U-bends | Purdue University | $600,000 | Most two-phase flow analyses have been performed in straight vertical-upward pipes. However, nuclear reactor systems include piping with different geometric components, such as elbows or U-bends, as well as changes in flow orientations. The proposed work performs experiments in a scaled test facility existing at the institution's lab to investigate the effects of flow orientations and geometries relevant to nuclear reactor systems on the hydrodynamics of two-phase flow. | Document | Strategic Needs Blue Sky | FY2024 |
| Interface-Resolved Experimental and Numerical Studies of Two-Phase Flow for Nuclear Engineering Applications | Virginia Polytechnic Institute and State University | $500,000 | The project aims at advancing the interface-resolved simulation capabilities for the two-phase flows found in various nuclear engineering applications. We will develop a comprehensive, high-resolution, interface-resolved database emphasizing bubble dynamics and bubble interaction mechanisms. The data will be used to validate the sub-grid models implemented in an interface-resolved simulation tool to improve simulation accuracy by developing physics-based coalescence models. | Document | Strategic Needs Blue Sky | FY2024 |
| Mechanism Driven Evaluations of Sequential and Simultaneous Irradiation-Creep-Fatigue Testing | University of Michigan | $1,000,000 | This project addresses a critical need for irradiation and creep-fatigue testing by carrying out a systematic, mechanistic-driven benchmarking for irradiation creep, irradiation fatigue and creep-fatigue tests under various environments. | Document | Advanced Nuclear Materials | FY2023 |
| Mechanisms-based Acceleration of Materials Qualifications for Creep-Fatigue Performance in Advanced Nuclear Systems | University of Illinois at Urbana-Champaign | $1,000,000 | The goal of this research is to fully understand, quantify and model creep-fatigue 'damage' as a function of loading patterns, temperature and microstructural evolution. Using this experimental information over a large range of relevant stress levels and temperatures, a mechanisms-based creep-fatigue analysis approach will be demonstrated which will properly qualify high temperature alloys for extended service in advanced nuclear systems where creep-fatigue is currently a major design limitation. | Document | Advanced Nuclear Materials | FY2023 |
| Subwavelength Ultrasonic Imaging for Rapid Qualification of Additively Manufactured Nuclear Structures and Components | University of Michigan | $1,000,000 | The objective of this project is to develop a transformational capability for rapid nondestructive quality assessment of actual nuclear additively manufactured structures and components through advanced ultrasonic imaging with subwavelength resolution. The resolution of conventional ultrasonic systems is limited by diffraction on the order of the wavelength. In this project, the goal is to break the diffraction limits of ultrasonic imaging by implementing a negative-index lens. | Document | Advanced Nuclear Materials | FY2023 |
| MXene as Sorbent Materials for Off-gas Radioiodine Capture and Immobilization | Clemson University | $1,000,000 | The overarching goal of this project is to develop efficient and stable new sorbent materials, for off-gas radioiodine capture and immobilization, that are based on MXenes with two-dimensional transition metal carbides/nitrides. The exploratory research will focus on three main objectives: 1) Design and synthesis of MXenes as radioiodine sorbent and support materials, 2) Quantification of iodine sorption capacity of MXenes in different forms, 3) Synthesis and characterization of consolidated waste forms. | Document | Advanced Nuclear Materials | FY2023 |
| Fundamental understanding of grain boundary cracking in LWR environments | University of California, Los Angeles | $1,000,000 | The objective of this project is to understand the details of stress corrosion cracking (SCC) and irradiation assisted stress corrosion cracking (IASCC) by targeted experiments and modeling efforts. A comprehensive model will be produced, which will predict the conditions under which these failure modes occur and when the materials may see onsets of the failure mode. This work will directly impact the nuclear industry by refining predictive models of component lifetime. | Document | Advanced Nuclear Materials | FY2023 |
| Facile manufacturing of fiber-reinforced-SiC/SiC composite using aerodynamic fiber deposition (AFD) and metal assisted polymer impregnation and pyrolysis processes (MAPIP) | University of Pittsburgh | $999,886 | SiC/SiC ceramic matrix composites (CMCs) are promising candidate materials for the cladding of accident tolerant fuels. Superior material properties of SiC/SiC CMC, however, come at a high manufacturing cost. The objective of the proposed research is to apply aerodynamic fiber deposition (AFD) and metal assisted polymer impregnation and pyrolysis (MAPIP) to develop a new facile manufacturing approach of SiC/SiC CMC. | Document | Advanced Nuclear Materials | FY2023 |
| High Concentration Monoamide Separations: Phase Modifiers and Transuranic Chemistry | Colorado School of Mines | $999,900 | Extraction of actinides from used nuclear fuel with high concentrations of monoamide extractants is a promising strategy to intensify separation processes; however key issues remain to be understood and resolved. This project will examine three questions: 1) Can phase modifiers mitigate issues with organic phase viscosity? 2) Can the chemistry of neptunium be controlled to ensure complete separation? 3) Do high concentrations of monoamides affect the oxidation states of important metals and can that be exploited? | Document | Fuel Cycle Technologies | FY2023 |
| Multiple Uranium Complexes in Chloride Fast Reactor Molten Salt Properties | University of Connecticut | $1,000,000 | Multivalent transition metal ions in a melt can exhibit multiple coordination states that affect molten salt properties. This project will use a new high-energy resolution fluorescence detection (HERFD) spectroscopy to overcome issues associated with measuring coordination numbers of multiple complexes, along with Raman spectroscopy and advanced simulations to accurately predict properties of molten salts with multiple uranium complexes. | Document | Fuel Cycle Technologies | FY2023 |
| Validation of Geochemical Reactive Transport Long-Term predictions Using Natural Cements and Ancient Cements Analogues | Vanderbilt University | $950,000 | This project will validate long-term performance predictions of rock/cement interfaces based on characterization of natural analogues, ancient cements and interfaces with rock formations, and demonstrate applicability of the established testing and simulation workflow with argillite rock (representative of potential U.S. repository systems). This project addresses the research gap of long-term validation and uncertainty assessment associated with cement barrier performance and multi-physics models. | Document | Fuel Cycle Technologies | FY2023 |
| Predicting Pitting and Stress Corrosion Cracking of Dry Cask Storage Canisters via High Throughput Testing, Multiscale Characterization, and 3D Computer Vision based Machine Learning | The Ohio State University | $1,000,000 | This project consists of a US-UK collaborative research program focusing on the nucleation and growth of pits and stress corrosion cracking of stainless steel 304 (a canister material used for dry cask storage of spent nuclear fuels) by leveraging multi-scale characterization techniques, 2D/3D computer vision, and machine learning approaches. The study will enable the understanding and prediction of how and when pitting corrosion can nucleate, grow, and transition into stress corrosion cracking. | Document | Fuel Cycle Technologies | FY2023 |
| Multiscale Residual Stress Tailoring of Spent Fuel Canister CISCC Resistance | Purdue University | $1,000,000 | The objective of this project is to understand the role of residual stress in chloride-induced stress corrosion cracking (CISCC) of austenitic steel, then tailor CISCC initiation and propagation through engineered multiscale residual stress distributions. Microscopic and macroscopic residual stresses will be systematically varied, then a novel sequence of advanced, site-specific, correlative characterization techniques will be applied to directly link residual stress, pitting, and crack propagation. | Document | Fuel Cycle Technologies | FY2023 |
| Illuminating Emerging Supply Chain and Waste Management Challenges | University of Illinois at Urbana-Champaign | $1,000,000 | Regional constraints on domestic fuel supply and greater variation in demand from advanced reactors has led to a shift in the U.S. fuel cycle, and modeling tools must reflect this. In this work, Cyclus will be updated to better reflect new and emergent regional supply constraints, spatial and temporal fluctuations in material needs, and those impacts on the back-end of the fuel cycle will be quantified. This work will allow for flexible, reproducible analysis to inform stakeholder decision-making. | Document | Fuel Cycle Technologies | FY2023 |
| Determination of Local Structure and Phase Stability of Uranium Species in Molten Halide Salts: Linking Microscopic Structure with Macroscopic Thermodynamics | Arizona State University | $1,000,000 | The goal of this project is to determine the local structures (valence state, coordination configuration and medium-range structure) and thermodynamic stability of uranium species in molten chloride and fluoride salts at high temperatures using a combination of experimental and modeling methods. The obtained results will allow for revelation of the structure-stability relations of the studied systems and development of acid-base scales to determine the solubility of uranium in molten halide salts. | Document | Fuel Cycle Technologies | FY2023 |
| Thermal-Hydraulics Assessment of SiC Compared to Other ATF Cladding Materials and its Performance to Mitigate CRUD | University of Wisconsin-Madison | $1,000,000 | This project aims to experimentally investigate the thermal-hydraulics performance of SiC compared to the Cr-coated zircaloys and APMT ATF cladding materials under accident scenarios, including both DNB and dryout conditions. The project is divided into five tasks that will advance the understanding of the operation and optimization of heat pipes for advanced nuclear reactors. | Document | Fuels | FY2023 |
| Physics-Informed Artificial Intelligence for Non-Destructive Evaluation of Ceramic Composite Cladding by Creating Digital Fingerprints | University of Florida | $1,000,000 | The objective of this project is to spatially map the material composition, structure, and defect distribution of SiCf-SiCm composite tubes from ultrasonic wavefields measured from the materials and the defects within them. Specifically, this project will delve into the unique ultrasonic fingerprints (i.e., dispersion relations and mode shapes) of the SiCf-SiCm composites using physics-informed machine learning to assess the quality of the manufactured tubes based on their spatial-spectral ultrasonic characteristics. | Document | Fuels | FY2023 |
| Improving Reliability of Novel TRISO Fuel Forms for Advanced Reactors via Multiscale, High-Throughput Characterization and Modeling | Brigham Young University | $1,000,000 | This project will use a parallelized thermal conductivity (k) measurement device coupled with multiscale models to accurately predict the thermal conductivity of TRISO fuel composites. This project overcomes the issue plaguing many "localized" microscale measurements, namely the inability to scale local measurements up to engineering scale properties. This will be done by using Bayesian inference techniques and finite element models to predict effective thermal conductivity. | Document | Fuels | FY2023 |
| Understanding Constituent Redistribution, Thermal Transport, and Fission Gas Behavior in U-Zr Annular Fuel Without a Sodium Bond | University of Florida | $999,462 | This project will investigate the reason for changed constituent redistribution in annular U-Zr fuel without a sodium bond and how it changes the fission gas behavior and thermal conductivity. This will be achieved using a combination of microstructure characterization and thermal conductivity measurements of irradiated U-Zr annular fuel and multiscale modeling and simulation using the MARMOT and BISON fuel performance codes. | Document | Fuels | FY2023 |
| Getting AnCers: Metallothermic Molten Salt Synthesis and Reaction Thermodynamics of Actinide Ceramic Fuels | Oregon State University | $1,000,000 | Synthesis of high quality actinide ceramics (AnCers) remains a costly challenge. A low-temperature, high-yield, short-duration reaction that directly synthesizes UN and UC could reduce the cost of these advanced fuels greatly. This proposal aims to demonstrate a method by which the costs of AnCers can be greatly reduced-metallothermic molten salt synthesis. Optimization and thermodynamics data will be obtained. | Document | Fuels | FY2023 |
| Integrated Stand-off Optical Sensors for Molten Salt Reactor Monitoring | University of Pittsburgh | $1,000,000 | This project intends to develop robust and stand-off optical sensors to perform real-time molten salt levels, flow, and impurity measurements of molten salts. | Document | Instrumentation and Controls | FY2023 |
| Optical Sensors for Impurity Measurement in Liquid Metal-cooled Fast Reactors | University of Michigan | $1,000,000 | This project will investigate whether a unique combination of two versatile optical techniques-laser-induced breakdown spectroscopy (LIBS) and two-photon absorption laser-induced fluorescence (TALIF)-could provide a sensitive, robust, and convenient method for in-situ, real-time detection of trace impurities ( | Document | Instrumentation and Controls | FY2023 |
| Cybersecurity in advanced reactor fleet by cyber-informed design, real-time anomaly detection, dynamic monitoring, and cost-effective mitigation strategies | University of Wisconsin-Madison | $1,000,000 | The goal of this research is to provide technical solutions to unique cybersecurity challenges in future microreactor fleet through cyber-informed design (C-ID), real-time anomaly detection, dynamic monitoring, and cost-effective mitigation strategies. The efforts will significantly improve the economics and effectiveness of cybersecurity risk management in future microreactor fleets. | Document | Instrumentation and Controls | FY2023 |
| Building Cyber-Resilient Architecture for Advanced Reactors via Integrated Operations and Network Digital Twin | Georgia Institute of Technology | $1,000,000 | The research will develop a secure-by-design architecture via integrating plant operation and network digital twins for advanced reactors. Automatic attack path and vulnerability analysis will be developed and used to assess and harden critical digital assets (CDA) against cyber risks prior to and during operation to identify vulnerabilities, attack pathways, and threat vectors. A CDA selection method will also be developed by combining vulnerability scores and assets importance. | Document | Instrumentation and Controls | FY2023 |
| Extending PRA and HRA legacy methods and tools with a cause-based model for comprehensive treatment of human error dependency | University of California, Los Angeles | $1,000,000 | This project aims at developing a solution to HRA dependency assessment in PRA from methodological and practical/computational perspectives within legacy PRA tools and methods. The solutions will include procedures for quantifying dependency when using PRA legacy tools, a method for modeling and quantifying dependency in HRA comprising a BN-causal model suitable for use with legacy PRA methods and tools, and the computational tools for its integration. | Document | Licensing and Safety | FY2023 |
| An Integrated Elemental and Isotopic Detector for Real-Time Molten Salt Monitoring | North Carolina State University | $1,000,000 | The overarching theme of the proposed research is to develop and demonstrate a real-time elemental and isotopic detector of molten salts for advanced reactors and fuel fabrication and recycling processes. The detector's longevity, limits, and latency will be tested in static uranium chloride salts, in pyroprocessing chloride salt, and on flowing fluoride salt with evolving actinide composition, respectively. | Document | Licensing and Safety | FY2023 |
| Development of a Thin-Layer Electrochemical Sensor for Molten Salt Reactors and Fuel Cycle Processes | Brigham Young University | $811,755 | A thin-layer electrochemical sensor capable of detecting uranium, plutonium and other species of interest in molten salts, at both high and low concentrations, will be developed for application in molten salt reactors and fuel cycle process units. This will provide a valuable tool for performing material control and accountancy measurements. | Document | Licensing and Safety | FY2023 |
| Risk-Informed Consequence-Driven Hybrid Cyber-Physical Protection System Security Optimization for Advanced Reactor Sites | Georgia Institute of Technology | $1,000,000 | This project aims to develop an expanded methodology for designing a novel cybersecurity-integrated physical protection system (PPS) framework for advanced reactor concepts that serves to reduce the operational costs for the life of a reactor against that of a traditional light water reactor PPS design, promoting efforts to credit safety features of advanced reactors through proposed amendments to current security regulations, while integrating health and economic consequence analyses. | Document | Licensing and Safety | FY2023 |
| A risk analysis framework for evaluating the safety, reliability, and economic implications of electrolysis for hydrogen production at NPPs | University of Maryland, College Park | $1,000,000 | The RAFELHyP project will develop a modular risk analysis framework that enables evaluating the safety, reliability, and economic implications of upcoming deployments of electrolyzers to produce hydrogen at nuclear power plants. The framework will be implemented to conduct an integrated safety, reliability, and economic analysis of multiple plant configurations to provide detailed recommendations for plant protective features and layouts. | Document | Licensing and Safety | FY2023 |
| Reduced Order Modeling of Heat and Fluid Flow: Multi-Scale Modeling of Advanced Reactors to Enable Faster Deployment | University of Illinois at Urbana-Champaign | $1,000,000 | Novel multi-scale algorithms for thermal-hydraulics (TH) simulations of advanced reactors will be developed. The methods will leverage recent advances in hardware and reduced order modeling approaches to enable TH simulations of vastly accelerated speed, while maintaining accuracy comparable to high-fidelity methods, such as large-eddy simulation. The methods will allow designers to perform parameter sweeps, develop closures, and enable high fidelity simulation of transients. | Document | Modeling and Simulation | FY2023 |
| Embedded Monte Carlo | Massachusetts Institute of Technology | $1,000,000 | Monte Carlo methods have long been considered the standard in terms of accuracy and have seen increased use in design of small nuclear systems; however, the uncertainty quantification (UQ) of the desired output is often relegated to later stages of the design process. This project seeks to embed nuclear data UQ in a single Monte Carlo simulation, such that each desired quantity will not only provide the mean value and statistical uncertainty, but also the related nuclear data uncertainty. | Document | Modeling and Simulation | FY2023 |
| A Low Order Transport Method Based on the Dynamic Truncation of the Integral Transport Matrix Method (ITMM) that Converges to the SN Solution with Increasing Cell Optical Thickness | North Carolina State University | $1,000,000 | A novel low-order transport operator capable of approximating Monte Carlo (MC) results within a variance range will be developed. This does not require MC reference solutions to calibrate the low-order model, so repeated solutions of the latter in-transient scenarios does not require repeated MC simulations. Truncation of the low-order operator is done dynamically for evolving configurations to ensure accuracy of the low-order solution. This will involve proof of principle on Cartesian meshes, then implementation in Griffin. | Document | Modeling and Simulation | FY2023 |
| CFD based Critical Heat Flux predictions for enhanced DNBR margin | Massachusetts Institute of Technology | $1,000,000 | This project seeks to demonstrate a robust high-fidelity CFD-based methodology to predict CHF behavior at varying quality conditions, enabling the development of advanced DNBR correlations with reduced uncertainty, and in support of upgraded plant economics. The availability of a virtual CHF methodology will allow greatly extending the database for DNBR correlations development and further support advancement in the design of high-performing nuclear fuel. | Document | Modeling and Simulation | FY2023 |
| Immersed Boundary Methods for Modeling of Complex Geometry: A Leap Forward in Multiscale Modeling using NekRS | University of Illinois at Urbana-Champaign | $1,000,000 | A major challenge to Computational Fluid Dynamics (CFD) modeling of complex geometries is the need to generate body-fitted meshes, which can occupy 80% of the CFD practitioner's time. Immersed boundary methods will be added in the NekRS CFD code, dramatically simplifying modeling of complex 3-D structures and facilitating a new paradigm for CFD-informed multiscale analysis. This will be demonstrated by informing SAM transient systems-level models with NekRS heat exchanger correlations for advanced reactors. | Document | Modeling and Simulation | FY2023 |
| Uncertainty Quantification of Model Extrapolation in Neural Network-informed Turbulent Closures for Plenum Mixing in HTGRs | Utah State University | $1,000,000 | This project will quantify the uncertainty in prediction of Neural Network-informed Turbulent Closures when they are operating in a model extrapolation state. Once the method is developed for canonical buoyant jets, the protocols will be applied to plenum mixing in HTGRs. | Document | Modeling and Simulation | FY2023 |
| Impact of moisture on corrosion of NiCr alloys in MgCl2-NaCl Salt Systems | University of Wisconsin-Madison | $999,983 | This project aims to gain a fundamental understanding of the impact of moisture and salt chemistry on corrosion of NiCr alloys in molten chloride salts. A novel approach coupling multiscale simulations and experiments will be designed to determine salt acidity, its dependence on salt composition (i.e., the NaCl to MgCl2 ratio), and its effects on the transport of H2O and Cr ions and the corrosion kinetics of NiCr alloys in chloride salt. | Document | Reactor Development and Plant Optimization | FY2023 |
| Transforming Microreactor Economics Through Hydride Moderator Enabled Neutron Economy | State University of New York, Stony Brook | $1,000,000 | Microreactors will potentially require the cost of electricity to be 10 MWD/kg at >3 kW/kg core specific power. These goals are best achieved through a well-thermalized spectrum. Neutron economy as a core material selection criterion to advance entrained hydride composite moderators will be used with the primary goal of significantly reducing fuel costs through novel microreactor designs. | Document | Reactor Development and Plant Optimization | FY2023 |
| Integrating Nuclear with ZLD Seawater Desalination and Mining | University of Wisconsin-Madison | $1,000,000 | An integrated nuclear system will be developed that would utilize electricity and waste heat to operate a desalination and mining process from adjacent seawater. The desalination approach targets zero-liquid discharge with multiple marketable minerals extracted. The ability of nuclear facilities to load follow is increasingly important, so a cold thermal storage system will be incorporated. The desalination and mineral extraction process will be experimentally validated at lab scale. | Document | Reactor Development and Plant Optimization | FY2023 |
| Reference Designs of Green Ammonia Plants Powered by Small Modular Reactors | Utah State University | $1,000,000 | The overarching goal of this project is to develop two reference designs for green ammonia plants. One design uses freshwater as the source for hydrogen, while the other design uses seawater (or brackish water) as the source. In both designs, a small modular reactor (SMR) is used as the primary energy source providing both electricity and steam for the plants. | Document | Reactor Development and Plant Optimization | FY2023 |
| Development of the Technical Bases to Support Flexible Siting of Microreactors based on Right-Sized Emergency Planning Zones | Pennsylvania State University | $1,000,000 | The objective of this project is to provide the technical basis to support the application of a right-sized Emergency Planning Zone (EPZ) size to support the deployment of a microreactor at the Penn State University Park campus. This research study will serve as a template to provide flexible siting in support of future microreactor deployments that may be placed closer to demand centers, thereby making them more economically competitive. | Document | Reactor Development and Plant Optimization | FY2023 |
| Bayesian Optimization for Automatic Reactor Design Optimization | Arizona State University | $1,000,000 | The objective of this project is to develop analytical tools based on Gaussian process modeling and Bayesian Optimization that facilitate reactor design optimization by modeling the responses from the physics simulator. Existing capabilities will be applied in an AI field and they will be adapted to address the key characteristics of nuclear reactor design problem. This project will automate the simulation-based design procedure, reduce the number of iterations, and minimize the design cycle time. | Document | Reactor Development and Plant Optimization | FY2023 |
| A Pathway for Implementation of Advanced Fuel Technologies in Light Water Small Modular Reactors | Texas A&M University | $1,000,000 | A comprehensive characterization of the performance of the Lightbridge Helical Cruciform advanced fuel design will be performed, which will generate unique sets of experimental data of friction factor, flow and heat transfer behavior under NuScale's LW-SMR simulated normal and off-normal conditions. The project will accelerate the deployment of advanced fuels for LW-SMR applications by leveraging the use of existing testing infrastructures. | Document | Reactor Development and Plant Optimization | FY2023 |
| Engaging New Mexican communities in developing an equitable and just approach to siting advanced reactor facilities | University of Michigan | $1,000,000 | This project will engage diverse New Mexican communities to develop an equitable approach for advanced reactor siting. The findings of this project will shed light on how technology developers and the DOE can explore and potentially site advanced reactors with the informed consent and engagement of host communities, regions, and states. The findings of this study will also more generally apply to the potential for equitably exploring both brownfield and greenfield sites for nuclear facilities. | Document | Reactor Development and Plant Optimization | FY2023 |
| Deciphering Irradiation Effects of YHx through In-situ Evaluation and Micromechanics for Microreactor Applications | University of New Mexico | $998,000 | This project addresses a critical gap in accelerated testing of YH evolution coupling multi-length scale mechanical testing with ion irradiation and advanced characterization to establish a baseline understanding of YH evolution under ion irradiation. Our approach will couple ion irradiation and gamma irradiation with small scale mechanical testing to decipher multi-scale impacts on phase stability to advance understanding of YH in a microreactor moderator application. | Document | Reactor Development and Plant Optimization | FY2023 |
| Active Learning Estimation and Optimization (ALEO) of Irradiation Experimental Design for Efficient Accelerated Fuel Qualification | University of Texas at San Antonio | $997,247 | This collaborative project creates novel AI/ML models and algorithms integrated with physical knowledge and expertise to explore more efficient ways to calculate irradiation temperatures and fuel specimen burnups for new fuel sample configurations of MiniFuel experiments proposed for irradiation in the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL). | Document | Reactor Development and Plant Optimization | FY2023 |
| Unraveling how mixing vane spacers affect cladding-to-coolant heat transfer phenomena in light water reactors | Massachusetts Institute of Technology | $500,000 | Experiments will be conducted to quantify the effect of mixing vane spacers on cladding-to-coolant heat transfer phenomena, namely single-phase forced convection, nucleate boiling, and CHF. The results of the experimental research will allow elucidating the physical phenomena triggered by the presence of mixing vane spacers. They will also allow assessing the performance of M-CFD tools developed within CASL and in use by the nuclear community. | Document | Strategic Needs Blue Sky | FY2023 |
| Quantum Computing Algorithms for Deterministic Neutron Transport | University of Michigan | $500,000 | This project will develop algorithms for solving the k-eigenvalue form of the neutron transport equation in a nuclear reactor physics context on a quantum computer. The asymptotic scaling of the algorithms will be analyzed. Investigation into implementation will be made by making resource estimates by synthesizing explicit circuits for the algorithms and be studied by emulation on a classical computer. | Document | Strategic Needs Blue Sky | FY2023 |
| Optimizing Application-Dependent Energy Group Structures for Multigroup Neutron Transport Models using Machine Learning | Colorado School of Mines | $500,000 | Machine Learning methods will be developed that will dramatically reduce both the computational run-time and manual effort needed to find multigroup energy structures that accurately capture the underlying physics of neutron reactions, while allowing multigroup simulations to run quickly without overwhelming available memory. | Document | Strategic Needs Blue Sky | FY2023 |
| Functionally-graded Cermet Coatings for Molten Salt Technologies by High Throughput Finite Element Modeling and Additive Manufacturing | Rensselaer Polytechnic Institute | $500,000 | This project proposes an integrated approach/methodology to design, manufacture and verify functionally-graded metal-ceramic composite coatings on structural alloys with desired interfacial properties, capabilities of mitigating residual stress and improved corrosion resistance for molten salt reactor applications. | Crosscutting Technologies | FY2022 | |
| An Innovative Monitoring Technology for the Reactor Vessel of Micro-HTGR | Texas A&M University | $800,000 | This project seeks to develop an innovative sensor technology for real-time monitoring of the thermo-mechanical stresses in the reactor vessel of micro-HTGR. The technology will be based on a sparse network of outer wall temperature measurements and plant operating conditions. An integrated software-hardware sensing system aimed at monitoring the health of the pressure vessel of gas micro-reactors will be implemented and tested. The proposed work will have a broad impact on sensing in other reactor designs. | Crosscutting Technologies | FY2022 | |
| High throughput mechanical testing of additively-manufactured materials | University of California, Berkeley | $500,000 | This project proposes fast and high throughput mechanical testing of AM produced materials. It will include the generation of automated tensile testing, hardness testing and microstructure assessment and data comparison to build data via machine learning. | Crosscutting Technologies | FY2022 | |
| Accelerated irradiation creep testing coupled with self-adaptive accelerated molecular dynamics simulations for scalability analysis | University of Michigan | $500,000 | The goal of the proposed work is to accelerate traditional irradiation creep using instrumented in-situ ion irradiation creep and long-time molecular dynamics simulations to accelerate traditional neutron irradiation creep testing. This goal will be accomplished by coupling a novel ion beam flux jump test using tapered creep specimens and self-adaptive accelerated molecular dynamics. The outcome is a rapid, low-cost accelerated method to determine the fundamental irradiation creep mechanisms. | Crosscutting Technologies | FY2022 | |
| Creation of a Pebble Database for Material Control and Accountancy in Pebble Bed Reactors | Virginia Commonwealth University | $399,969 | The primary goal of this proposed project is to develop a database of NDA signatures from a wide variety of used PBR pebbles. This database can be used for facility operations, safety, security, and safeguards (3S) to directly measure fission product content and indirectly 235U and plutonium content of each PBR pebble. This project has significant synergy with current 3S PBR research at ANL, BNL, and ORNL, all of whom are collaborators to this proposed project. | Crosscutting Technologies | FY2022 | |
| Integrated Marine Platform for Hydrogen and Ammonia Production | Massachusetts Institute of Technology | $800,000 | This study investigates the economic and environmental value of a floating integrated GW-scale green hydrogen/ammonia production facility powered by an advanced nuclear reactor. Floating Production Storage and Offloading units (FPSOs) are deployed worldwide in the oil and gas industry, and can be used for hydrogen and ammonia processing. Deployment of an advanced reactor on a floating platform offers several advantages, including the efficiencies of shipyard fabrication. | Crosscutting Technologies | FY2022 | |
| Quantifying Aerosol Deposition Mechanisms in Model Dry Cask Storage Systems | Clemson University | $800,000 | The objective of this work is to measure aerosol deposition and resuspension rates in laboratory models of dry cask storage systems to compare with and validate the DOE deposition model. The project team will conduct experiments to directly measure the deposition/resuspension rates of bulk aerosol in the system and to isolate and quantify individual aerosol deposition mechanisms, with a focus on those sensitive to variable humidity and surface temperature. | Fuel Cycle R&D | FY2022 | |
| Using Amide-Functionalized Electrodes to Elucidate Interfacial Actinide Redox Chemistry for Improved HALEU Supply | Florida International University | $400,000 | The goal is to decrease HALEU fuel cycle costs by examination of the redox behavior of U, Np, and Pu at the water-organic interface using amide functionalized electrodes, and in organic media after extraction with amides. Experiments with redox active interferences including additional actinides in different oxidation states will also be conducted. | Fuel Cycle R&D | FY2022 | |
| Advancing the technical readiness of FeCrAl alloys and ODS steels under extreme conditions for fast reactor fuel cladding | North Carolina State University | $800,000 | A key technology gap for advanced high-performance fuel applications is the current unavailability of materials that can withstand extremely high doses without significant degradation of cladding performance. The project team will perform in-situ thermo-mechanical experiments (tension, torsion, creep, and creep-fatigue and nanoindentation) on ion-irradiated (to 400 dpa) cladding materials (up to 700 C) along with microstructures using TEM and mesoscale phase field simulations. | Fuel Cycle R&D | FY2022 | |
| A molten salt community framework for predictive modeling of critical characteristics | Pennsylvania State University | $400,000 | This research aims to develop a molten salt community framework to address the needs in advanced fuel cycles, including understanding salts via new theory of liquids, predicting salt characteristics via simulations (DFT, MD, and CALPHAD by implementing advanced models), optimizing inversely molten salts, and verifying simulations by experiments. This project has outstanding value for US taxpayers, educates students, and delivers outreach opportunities for academia, industry, and the public. | Fuel Cycle R&D | FY2022 | |
| Understanding the Interfacial Structure of the Molten Chloride Salts by in-situ Electrocapillarity and Resonant Soft X-ray Scattering (RSoXS) | Pennsylvania State University | $400,000 | The objective of the proposed research is to investigate the interplay between the interfacial structure of the molten salts and their electrochemical corrosion properties in Molten Salt Reactors (MSRs). | Fuel Cycle R&D | FY2022 | |
| Clay Hydration, Drying, and Cracking in Nuclear Waste Repositories | Princeton University | $800,000 | This project will develop a new multiscale model of the thermal-hydrologic-mechanical-chemical (THMC) evolution of an engineered clay barrier in the near field of a nuclear waste repository, including initial hydration and eventual post-closure criticality. This new model will directly link micro-scale material properties to large-scale barrier performance, thus facilitating future design advances or modifications, and enable robust validation of large-scale simulation predictions. | Fuel Cycle R&D | FY2022 | |
| Physics-guided Smart Scaling Methodology for Accelerated Fuel Testing | Purdue University | $800,000 | This project proposes to employ novel informatics algorithms for mapping/scaling uncertainties from experimentally accessible scaled state to application/prototypical state, informed by an equivalent mapping obtained from high-fidelity multi-physics simulations for the fuel thermo-mechanical behavior, specifically, a rate theory-based model for thermal conductivity and fission gas behavior in the BISON code, and employing relevant HALDEN reactor and FAST experiments. | Fuel Cycle R&D | FY2022 | |
| Materials Accountancy During Disposal and Waste Processing of Molten Salt Reactor Fuel Salts | Texas A&M University | $399,997 | The objective of this work is to develop and validate a method for measuring and predicting hold-up to eliminate operational risks and expenses during disposal of salt-wetted MSR components. These objectives will be met by applying robust measurement/detection methods to realistic salt loop environments to validate their use in decommissioning MSRs. | Fuel Cycle R&D | FY2022 | |
| Advanced Screening Approaches for Accelerating Development of Separations Technologies | University of California, Berkeley | $400,000 | The goal of this project is to establish a unified selection criterion for chelating molecular structures to more efficiently address ligand applicability to metal ion separation problems, for current and future nuclear fuel cycles. By establishing this criterion, the team will seek to enable the accelerated, cost-effective discovery of new separation workflows, as well as their implementation beyond early radiotracer experiments. | Fuel Cycle R&D | FY2022 | |
| Advancing NMA of TRISO-fueled pebbles using fast and accurate gamma-ray spectroscopy | University of Colorado, Boulder | $385,307 | This proposal will provide new Nuclear Materials Analysis (NMA) capabilities for TRISO-fueled pebbles using gamma-ray spectroscopy, through a program of simulations of expected signatures from irradiated pebbles, resulting in a detailed measurement plan to monitor burnup and actinide content throughout the fuel cycle. These simulations will be used to develop requirements for NMA sensor technology and identify opportunities for focused technology development to meet these requirements. | Fuel Cycle R&D | FY2022 | |
| Development of Irradiation and Creep Resistant High-Cr Ferritic/Martensitic Steels via Magnetic Field Heat Treatment | University of Kentucky | $800,000 | The objective of this proposed study is to develop and test new generation of Ferritic/Martensitic (F/M) steels specifically designed for advanced reactors that will exceed the current limitations due to temperature and irradiation dose. To achieve this objective, a systematic study is proposed to employ an innovative tempering heat treatment under high external magnetic field (up to 9T) on F/M steel HT9 to engineer an optimized microstructure composed of refined carbides and martensite laths. | Fuel Cycle R&D | FY2022 | |
| Investigation into the processing parameters of phosphate-based dehalogenation for chloride-based waste salt | University of Nevada, Reno | $399,999 | This proposal will focus on several topics needed to advance the iron phosphate process: 1) Dehalogenation/vitrification processes using salt simulants to generate process flow sheets, 2) Reactions of crucible materials with phosphate products and byproducts, 3) Collection of glass property-composition data to develop models based on the glass-forming regions, 4) Development of a process for reacting recovered NH4Cl with metals that need to be fed into the system (U, Li, etc.). | Fuel Cycle R&D | FY2022 | |
| A Validated Framework for Seismic Risk Assessment of Spent Fuel Storage Facilities | University of Nevada, Reno | $799,883 | This is a collaborative research program with a primary objective of developing a validated numerical framework for seismic risk analysis of spent fuel storage facilities from the global cask behavior to the localized behavior of internal spent fuel assemblies. In building and validating this framework, advanced data analysis, data assimilation, and forward and inverse modeling techniques will be utilized. | Fuel Cycle R&D | FY2022 | |
| International Collaboration to Advance the Technical Readiness of High Uranium Density Fuels and Composites for Small Modular Reactors | University of Texas at San Antonio | $800,000 | An international team of high uranium density fuels (HDFs) experts advised by industry leaders in nuclear reactor innovation propose a US-UK collaboration to advance the technical readiness of UN, UB2, and their composites for fuel forms specific to small modular reactors (SMRs). The project will bridge the critical data gaps in HDF performance specific to the impact of common impurities and microstructural variations that originate at fabrication. | Fuel Cycle R&D | FY2022 | |
| Development of Advanced Control Rod Assembly for Improved Accident Tolerance and High Burnup Fuel Cycle | University of Wisconsin-Madison | $800,000 | Research will focus on the development of new materials' designs for control rod sheaths and neutron absorbers, coupled with neutronics analysis and thermo-mechanical modeling to improve accident tolerance and to achieve higher fuel burnup in PWRs. Functionality of the proposed designs consisting of Cr coated control rod sheaths of current and advanced alloys as well as novel neutron absorbers will be evaluated in prototypical reactor conditions and accident scenarios. | Fuel Cycle R&D | FY2022 | |
| Optical Basicity Determination of Molten Fluoride Salts and its Influence on Structural Material Corrosion | University of Wisconsin-Madison | $400,000 | The proposed research is aimed at developing ion probes to determine the optical basicity of molten fluoride salts and studying its influence on structural material corrosion. Combining with the molten salt structure study using X-ray absorption spectroscopy, the salt chemical constitution, the resulting optical basicity, and molten salt structure will be inextricably linked and their connections will be unveiled. | Fuel Cycle R&D | FY2022 | |
| Extending the HMF71 Benchmark Series for Graphite Reflector Thickness up to 18 Inches | University of Tennessee at Knoxville | $399,522 | The objective of this proposal is to extend the HEU-MET-FAST-071 (HMF-71) experiment benchmark series in ICSBEP by evaluating the historical (existing) experimental data for critical experiments with graphite reflector thickness from 3 inches up to 18 inches. | Nuclear Energy | FY2022 | |
| Fast and Rigorous Methods for Multiphysics SPn Transport in Advanced Reactors | University of Michigan | $600,000 | This project proposes to perform rigorous theoretical and numerical analysis of the Generalized SPn method and underlying cross section models to enable a fast and robust multiphysics low-order transport capability for advanced reactors. This includes 5 major tasks focused on the efficient discretization and solution of the GSPn equations, numerical analysis of XS models having multiphysics and depletion, analysis of equivalence factors, improved MC estimators, and several V&V applications of the methods. | NEAMS | FY2022 | |
| Development of Hydrogen Transport Models for High Temperature Metal Hydride Moderators | Colorado School of Mines | $800,000 | Understanding the transient behavior of metal hydride moderator materials at high temperatures is a key challenge to the design and deployment of future microreactors. This project will use neutron radiography techniques provide the necessary data for this understanding and demonstrate the development of time and temperature dependent hydrogen transport models using both commercial FEA software coupled to MCNP and coupled models developed in the MOOSE framework. | RCRD&D | FY2022 | |
| Characterizing fast reactor fuel failure mode through separate effect and prototypic tests | Oregon State University | $800,000 | The project consists of conducting separate effect fuel pin failure tests with surrogate fluid and prototypic test with sodium. The outcome of this study will generate an experimental database that will be used to develop mechanistic model and validate the CDAP module of the SAS4A/SASSYS-1 code. Ultimately the quality data can be used to benchmark other fuel codes developed for LMFR application, which are seeking validation for licensing purpose. | RCRD&D | FY2022 | |
| Science-based development of ASTM standard tests for graphite-based fuel pebbles | University of California, Berkeley | $700,000 | This project proposes the development of mechanical test procedures as well as wear and friction tests on Graphite fuel pebbles | RCRD&D | FY2022 | |
| Role of Heterogeneity in Manganese and Nickel Rich Precipitate Distribution on Hardening of Reactor Pressure Vessel Steels: Integrated Modeling and Experimental Characterization | University of Florida | $799,803 | The hypothesis of this work is that the different nucleation and coarsening kinetics of manganese and nickel rich precipitates (MNPs) compared to copper rich precipitates, and the heterogeneous distribution of manganese and nickel rich precipitates on or near dislocations, both lead to unique hardening behavior at high neutron fluence. The objective of this work is to understand hardening in reactor pressure vessel steels caused by MNPs via integrated multiscale modeling and experiments. | RCRD&D | FY2022 | |
| Integrated Thermal-Electric Energy Management of All-Electric Ship with Advanced Nuclear Reactors | University of Texas at Dallas | $400,000 | The overall objective of this research is to comprehensively model, design, and evaluate the use of advanced nuclear reactors in future nuclear-powered ships, to enhance the efficiency, reliability, and resilience of shipboard energy distribution systems. The novelty of the proposed approach lies in (i) integrated thermal-electric modeling of advanced nuclear-powered shipboard energy system, and (ii) novel solutions for total-ship energy management to improve energy efficiency and resiliency. | RCRD&D | FY2022 | |
| Open Architecture for Nuclear Cost Reduction | University of Wisconsin-Madison | $800,000 | Open architecture has potential to reduce advanced reactor (AR) costs, through exploiting modular design and construction, with common, openly available interfaces between modules. A comprehensive assessment of the challenges and opportunities of open architecture for ARs will be performed. Supported by a pilot study, actionable recommendations for the implementation or otherwise of open architecture for ARs will be developed. | RCRD&D | FY2022 | |
| Telescopic Control Rod for Significant Reduction in HTR Height and therefore Cost | University of Wisconsin-Madison | $800,000 | This project proposes a design for a small modular High Temperature Reactor (HTR) control rod that extends telescopically, consisting of ~5 concentric annuli that nest together above the core when withdrawn. This compact component substantially reduces the length of the depth of the silo. Modelling and experimental testing will be performed to develop the control rod to evaluate feasibility, plus perform a cost-benefit analysis, with a view to its inclusion in both pebble bed and prismatic HTR designs. | RCRD&D | FY2022 | |
| NEUP Project 21-24394: Computer vision and machine learning for microstructural qualification | Carnegie Mellon University | $497,518 | Quantifying and understanding microstructure is a key driver for performance-based materials qualification. In this proposal, well-curated data sets of microstructural images will be gathered and computer vision and machine learning will be applied to build quantitative deep learning frameworks to accelerate and enable qualification of nuclear materials based on microstructural features. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-24156: Experimental thermofluidic validation of TCR fuel elements using distributed temperature and flow sensing | Kansas State University | $798,250 | The overall goal of this project will be to test the performance of 3D printed Transformational Challenge Reactor core geometry parts using existing Helium flow loops and distributed temperature, and velocity sensing systems. Thermal transport capabilities of scaled 3D printed ceramic core will be evaluated experimentally and measurements will be used to qualify computational models. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-24636: Risk-informed Consequence-driven Physical Protection System Optimization for Microreactor Sites | Texas A&M University | $400,000 | This proposed project will utilize a risk-informed, consequence-driven analysis to develop an approach for "right-sizing" physical protection systems (PPS) for microreactors. The hypothesis presented for this proposal is that the explicit coupling of consequence modeling to PPS design will provide a similar benefit that can be applied prior to reactor construction. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-24131: Total Mass Accounting in Advanced Liquid Fueled Reactors | The Ohio State University | $400,000 | A total mass determination method for nuclear materials accounting (NMA) in liquid-fueled molten salt reactors will be validated with fuel-bearing salt, mixed with a + radioisotope of known activity, that will be irradiated to reproduce the practical NMA scenario in a molten salt loop. Irradiated fuel salt will be sampled and measured for its mass and activity. The mass-to-activity ratio will be used to calculate the unknown salt mass in the original container. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-24037: Design and intelligent optimization of the thermal storage and energy distribution for the TerraPower Molten Chloride Fast Reactor in an Integrated Energy System (IES) | University of Tennessee at Knoxville | $800,000 | The objective of this project is to explore the application of advanced reactors within Integrated Energy Systems, use extensive existing data from UIUC for model development and validation, and extend the predictions to larger grids and commercial applications. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-24522: Targeted Materials Characterization and Testing of Additively Manufactured Metals and Ceramics to Inform Print/Build Data Analytics | University of Texas at San Antonio | $800,000 | A collaborative program between the University of Texas at San Antonio and Boise State University is proposed to supply materials testing and characterization data sets to be leveraged by the TCR program to inform build/print data analytics. With the data provided by the proposing team, correlations among steam oxidation performance, micromechanical properties, chemical composition, local microstructure, and location specific print/build data will be achieved. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-24431: Location-specific material characterization of LPBF SS316L & IN718 TCR core structural materials | Utah State University | $800,000 | In this proposed work, we will experimentally characterize the spatial variability of the quasi-static (tensile), creep (strength and impression), and creep-fatigue properties as well as the underlying structures (microstructure and defect structures) for LPBF SS316L and IN718 components to be used as training data to the TCR program data-driven model. The resulting correlation will be used to drive the design process for an application as TCR core structural materials. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-23978: Rapid, Non-Radioactive Methods for Prediction and Quantification of Radiolytic Radical Decomposition Products in Nuclear Separations | Clemson University | $399,999 | High-throughput, non-radioactive, radical assays will be used to determine decomposition of monoamide separations complexants. Radical assay results will be correlated with classic radiolytic damage results to develop predictive models for screening complexant stability. These models will aid in single-stage separations complexant optimization, in the transition from lab-to industrial-scale nuclear waste separations and, ultimately, could yield field tests for radiolytic damage. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24350: Phosphate Mineral and Glass Waste Forms for Advanced Immobilization of Chloride and Fluoride-based Waste Streams | Clemson University | $600,000 | This proposal is intended to develop three waste form options for immobilizing the fluoride-and chloride-salt waste stream in highly durable and easily processable phosphate minerals and glasses, including phosphate apatite ceramic waste forms, phosphate glass waste forms, and phosphate glass-ceramic waste forms with apatite phase. Multiple monolithic waste form samples will be provided to DOE national laboratories for further testing. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24292: Passive multimodal tomography for dry storage casks imaging using passive neutron and gamma dosimetry and cosmic ray muons | Colorado School of Mines | $800,000 | A method for multimodal tomography of dry storage casks will be developed to determine fuel relocation and cladding failures using passive neutrons and gamma emissions in combination with cosmic ray muons. The use of multimodal imaging will allow 3-D reconstructions of the dry storage cask that would be unachievable with any single radiation source. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24374: Effects of Radiolysis on Pertechnetate under Solvent Extraction Conditions, including Tri-Butyl Phosphate | CUNY, Hunter College | $399,624 | The overarching objective of the proposed work is to assess the impact of radiolysis on pertechnetate speciation during tri-butylphosphate (TBP) solvent extractions from the molecular level to macroscale. The research in this project is designed to understand the interplay of radiolysis, degradation product formation, other important redox active metals, and oxidation states of technetium on its speciation and distribution coefficients in solvent extraction processes. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24183: Experimental investigation and development of models and correlations for cladding-to-coolant heat transfer phenomena in transient conditions in support of TREAT and the LWR fleet. | Massachusetts Institute of Technology | $800,000 | Thermal-hydraulics transient heat transfer phenomena of relevance for the safety and the operation of the TREAT and light water reactors will be investigated. The performance of accident tolerant fuel materials during a reactivity initiated accident scenario and post-critical heat flux and reflood scenarios will be elucidated, as well as the development of models and correlations to be integrated into computational tools for the design and safety analysis of nuclear systems. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24666: Wireless Multifunctional Ultrasonic Arrays with Interdigital and Airborne Transducers for Monitoring Leakage and Corrosion Conditions of Welded Dry Storage Canisters | Mississippi State University | $800,000 | This project aims to develop and validate wireless, multifunctional, ultrasonic sensor arrays that enable on-demand, quantitative interrogation and real-time monitoring of both the canister leakage indicators (helium, helium/air mixture, internal pressure, and temperature) and corrosion conditions (free and/or vapor water). The developed arrays will be fully functional, wirelessly powered and communicated, and compact. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24188: Uranium recovery from used nuclear fuel using metal sulfides | Northwestern University | $400,000 | An alternative and original method to recover uranium from spent fuel is proposed. This method will utilize a new type of regenerable sorbent materials with high selectivity in capturing uranium from complex mixtures in acidic solutions, such as those found in used nuclear fuel of high-assay low-enriched uranium. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24225: Characterizing Fuel Response and Quantifying Coolable Geometry of High-Burnup Fuel | Oregon State University | $800,000 | This study seeks to objectively determine, through empirical and numerical means, the actual impact of fuel dispersion in-core after fuel failure and whether high burnup dispersed fuel compromises coolable geometry and long-term cooling. The outcome of this study will yield an objective means of assessing two criteria (coolable geometry and long-term cooling) within the existing regulatory process to comprehensively understand whether it is feasible to increase burnup, while satisfying 10 CFR 50.46. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24288: Innovative Methods for Interrogation of DSC Internal Conditions | Oregon State University | $800,000 | The proposed work takes a two-pronged approach. The team will study techniques involving only external sensors and equipment, which could be deployed on existing dry storage canisters. In addition, small sensors located inside the canister that can be externally powered and read through the canister wall will also be investigated. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24439: Development of Novel Corrosion-Responsive Buffer Materials for Long-Term Immobilization of High-Level Nuclear Waste | Pennsylvania State University | $800,000 | The goal of this project is to develop a novel cementitious buffer material (CBM) for the safe disposal of spent nuclear fuel (SNF). The primary aim is to identify and characterize novel Mg-Al-P CBMs, complete with assessments of their repository stability as well as their transport and immobilization of radionuclides. The secondary aim is to use in-situ UT-EIS monitoring to understand the corrosive failure at the canister-CBM interface and provide long-term performance modeling of SNF packages. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24461: Estimation of low temperature cladding failures during an RIA transient | Pennsylvania State University | $800,000 | Researchers aim to create a multiphysics description of cladding response during a RIA, especially at high burnup, coupling reactor physics, thermal hydraulics and mechanics. The creation of a thermomechanical model in Bison will be the result of this project which can be used to evaluate the likelihood of low temperature cladding failures during a postulated RIA on a typical fuel rod (as these can lead to channel blockage), and thus identify the most important conditions to be studied at TREAT. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24460: Multiscale Modeling and Experiments for Investigating High Burnup LWR Fuel Rod Behavior Under Normal and Transient Conditions | Texas A&M University | $800,000 | The main objective of this work is to achieve a mechanistic understanding of and to develop a predictive model for the fuel rod behavior at high burn-up under both normal and transient conditions. Therefore, this study will provide the nuclear industry with validated, physics-based criteria to fuel fragmentation thresholds and rod mechanical integrity limits. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24388: Redox Chemistry of UO2 under Repository Relevant Conditions in the Presence of Zircaloy and Waste Canister Material | University of California, Irvine | $800,000 | This project will seek to improve understanding of spent nuclear fuel (SNF) corrosion. Hydrothermal experiments of SNF with cladding and waste canister material will give insights into the redox potential formed due to secondary phase formation as consequence of corrosion in a failed canister. The experimentally derived data about secondary phase formation will be utilized for phase relationship analysis to decipher the redox conditions and thus provide source term for performance assessment models of deep geologic repositories. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24006: High-fidelity modeling of fuel-to-coolant thermomechanical transport behaviors under transient conditions | University of Florida | $800,000 | The objective of the proposal is to develop a high-fidelity modeling tool that can capture some of the important phenomena in high burnup UO2 and ATF fuels during transient conditions. The BlueCRAB tool set will be improved and used to analyze TREAT loss of coolant accident experimental results. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24312: Accelerating the development of reliable and robust machine learning-based interatomic potentials for the prediction of molten salt structure and properties | University of Massachusetts Lowell | $400,000 | Machine learning-based interatomic potentials (MLIPs) used in molecular dynamics (MD) can accurately and efficiently predict molten salt properties. However many machine learning-based methods require large training sets, and can fail unpredictably. This project will overcome these challenges by developing a method for efficiently sampling diverse configurations from MD to train reliable and robust neural network potentials, and develop new models for predicting errors in MLIPs. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24697: Dual External Leak Sensing and Monitoring for Dry Storage Canister | University of Nebraska, Lincoln | $800,000 | Researchers aim to develop two complementary external sensing methods to evaluate the integrity of DSC through internal pressure monitoring and helium leakage detection. The proposed diffuse ultrasonic wave method will be able to measure biaxial strains in the canister wall with high sensitivity and minimum temperature effects. An innovative capacitance MEMS sensor will be developed for helium concentration measurement in air based on the extremely low permittivity of helium. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24449: Multi-modal Surface Acoustic Wave Sensing System for Pressure and Temperature monitoring of Spent Fuel Canisters | University of North Texas | $800,000 | University of North Texas (UNT) will collaborate with Oak Ridge National Laboratory (ORNL) and National Energy Technology Laboratory (NETL) to develop a multi-modal wireless passive SAW (Surface Acoustic Wave) sensor array, which are deployed on the outside surface of the canister, to monitor the strain of the canister and thus determine the inside pressure. In addition, the SAW strain sensor could also measure the surface temperature and potentially monitor helium gas leak. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24265: Fragmentation and Thermal Energy Transport of Cr-doped Fuels under Transient Conditions | University of Pittsburgh | $799,999 | This project will focus on multiple aspects of experimental testing and engineering-scale modeling in understanding thermal energy transport from high burnup, fractured/fragmented accident tolerant fuels, establishing a strong scientific basis to fill a critical knowledge data gap for modeling and simulation of transient fuel performance and safety, such as loss of coolant accident, for future integral testing and fuel licensing. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24310: Fusion of Distributed Fiber Optics, Acoustic NDE, and Physics-Based AI for Spent Fuel Monitoring | University of Pittsburgh | $800,000 | The proposal will leverage new concepts in the fusion between fiber optic distributed acoustic sensing and advanced acoustic nondestructive evaluation techniques with artificial intelligence enhanced classification frameworks to quantitatively characterize the state of dry cask storage containers for spent fuel monitoring, externally and non-invasively, without introducing additional risks of failure. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24261: Internal Wireless Sensors for Dry Cask Storage | University of South Carolina | $800,000 | The effort will test the reliability of wireless, internal sensors after exposure to drying and storage conditions. These sensors are used to internally monitor temperature, pressure, and dose. Radiation shielding will also be designed to protect sensors during long-term storage. The effort will develop piezoelectric techniques for miniaturization of optical emission spectroscopy for internal monitoring of gas composition during drying and long-term storage. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24533: Non-destructive Evaluation of Dry Storage Canisters Using Acoustic Sensing | University of Southern California | $800,000 | The objective of this project is to develop a robust non-destructive evaluation (NDE) technique based on acoustic sensing to detect impurity gases in a sealed (welded) dry storage canister (DSC) using only measurements collected on the external surface of the DSC. The method is based on the time-of-flight analysis of acoustic signals propagating through the fill gas of a DSC, which is influenced by the composition, density and temperature of the propagation medium. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-23984: Safety Implications of High Burnup Fuel for a 2-Year PWR Fuel Cycle | University of Tennessee at Knoxville | $800,000 | The objective of this project is to perform safety analysis of high burnup fuel for a Westinghouse 4-Loop Pressurized Water Reactor. The work aims to identify potential opportunities and gaps for high burnup fuel by utilizing both well-established and modern methodologies to model reactor physics, thermal-hydraulics, and plant system-level response that ultimately provide feedback to fuel performance analysis. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-23985: Fuel-to-Coolant Thermomechanical Behaviors Under Transient Conditions | University of Tennessee at Knoxville | $800,000 | This project will enhance the prediction of thermo-mechanical fuel-to-coolant heat transfer under transient conditions by using a coupled analysis and experiment approach. The effort is relevant to both high-burnup (> 62GWd/t) fuel applications and Accident Tolerant Fuel. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24070: Modeling high-burnup LWR fuel behavior under normal operating and transient conditions | University of Tennessee at Knoxville | $800,000 | This project aims to develop a high-burnup light water reactor fuel modeling capability to implement in the BISON code that would enable the accurate fuel rod behavior simulation during normal operation and design basis accidents, as wells as the identification of the rod life-limiting factors. Mechanistic engineering models will be developed for key phenomena, in particular, high burnup structure evolution, fuel fragmentation, and fission gas release. Traditional and accident tolerant fuels will be considered. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24033: Redox Chemistry in Nuclear Materials Storage Matrices under Ambient and Accelerated Aging Conditions | University of Washington | $800,000 | Deep geologic repositories must safely contain hazardous, high-activity nuclear wastes at geologic time-scales. However, such capability is centrally dependent on the element-specific redox chemistry within and at the interface of storage vessels. A comprehensive study of redox chemistry in cements used in long-term storage is proposed and emphasizes: 1) the actual consequences of accelerated aging modalities and 2) the novel use of newly available capabilities in advanced x-ray spectroscopies. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24063: Post-DNB Thermo-mechanical Behavior of Near-term ATF Designs in Simulated Transient Conditions | University of Wisconsin-Madison | $800,000 | The goals of the proposed research are to conduct coupled experimental and modeling investigations of thermo-mechanical performance of coated accident tolerant zirconium alloy claddings with simulated burnup doped fuels under thermal transients to predict complex thermal and mass transport phenomena of near-term Accident Tolerant Fuel designs in accident conditions. Experiments and modeling for understanding both cladding-coolant and fuel-coolant interactions will be performed. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24582: Machine-Learning-Accelerated Molecular Dynamics Approaches for Molten Salts | University of Wisconsin-Madison | $399,477 | New machine learning potential (MLP) approaches and new MLPs to enable rapid prediction of molten salt (FLiBe and Nal-MgCl2 with impurities) properties with near ab initio quantum mechanical accuracy will be developed. Uncertainty quantification with active learning and on-the-fly fitting will greatly accelerate MLP training. This work will support dramatically increased simulation speeds and associated data generation and understanding for molten salts. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24067: Development of Full Understanding of Mechanical-Chemical Coupling in Bentonite THMC processes | Virginia Polytechnic Institute and State University | $800,000 | The central hypothesis is that mechanical stress in an engineered barrier can lead to pressure solution of solid minerals, leading to significant changes in pore water chemistry, which affects bentonite stability, longevity of the waste pack, and dissolution and migration of nuclides. The overall objective of this project is to develop full understanding of the role of pressure solution on pore water chemistry, the implications to large-scale heterogeneity, and THMC processes. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24186: Regenerating Missing Experimental Parameters with Data-Assimilation Methods for MSRE Transient Benchmark Development and Evaluation | Virginia Commonwealth University | $400,000 | The proposed project will regenerate the undocumented basic data from available experimental data of the MSRE using advanced data-assimilation methods to facilitate the whole-loop modeling of the representative MSRE transients, and perform a thorough MSRE transient benchmark evaluation for the IRPhEP handbook. | Nuclear Energy | FY2021 | |
| NEUP Project 21-24630: Integral Benchmark Evaluation of Zero-Power Tests and Multi-Cycle Depletion Experimental Data of TVA WB1 Cycles 1-3 | North Carolina State University | $400,000 | This project proposes to develop an integral benchmark evaluation of available experimental data for zero-power tests and multi-cycle depletion for consistent and comprehensive validation of both novel high-fidelity and traditional multi-physics tools. The benchmark evaluation will be based on operational and measured data from the Pressurized Water Reactor Watts Bar Unit 1 released by Tennessee Valley Authority. | Nuclear Energy | FY2021 | |
| NEUP Project 21-23987: Separate and Multi-Physics Effects IRPhEP Benchmark Evaluation using SNAP Experiments | Georgia Institute of Technology | $400,000 | The proposed project will develop an International Reactor Physics Experiment Evaluation Project (IRPhEP) mulitphysics microreactor benchmark evaluation based on data from the Systems for Nuclear Auxiliary Power (SNAP) program. This work will include systematic assessments of the experimental data with meticulous compilation and documentation, and validation of specific NEAMS tools to model effects that are unique to microreactors technologies. | NEAMS | FY2021 | |
| NEUP Project 21-24194: Implementation of improved quasi-static, time-dependent, multi-physics methodology in Shift | Georgia Institute of Technology | $600,000 | A practical reference calculation route for time-dependent coupled Monte Carlo calculations, using Shift, will be developed. The proposed framework will be tailored to depletion and slowly varying transients, but with the flexibility to perform thermal-hydraulic time-dependent calculations with minimal computational overheads. This method relies on a hybrid-resolution stochastic approach in conjunction with a substep technique. | NEAMS | FY2021 | |
| NEUP Project 21-24078: Material transport model development and integration in the System Analysis Module (SAM) code | Rensselaer Polytechnic Institute | $400,000 | This project proposes to develop and implement models for System Analysis Module, which accurately characterize the sink, source, and interaction terms of key material species that are or may be present in various advanced reactor designs. | NEAMS | FY2021 | |
| NEUP Project 21-24195: Enhancing Yellowjacket for Modeling the Impact of Radiation and Stress on the Corrosion of Molten-Salt-Facing Structural Components | University of Florida | $692,088 | The objective of this project is to add the capability to model the impact of radiation and stress on corrosion to the Yellowjacket code, as well as to use Yellowjacket to create surrogate models that will be added to engineering-scale codes like Grizzly. We will also collect new experimental data for validation that quantifies the impact of stress and radiation on corrosion of 316 stainless steel in molten fluoride salts. | NEAMS | FY2021 | |
| NEUP Project 21-24405: Development of a High-fidelity Flow Boiling Database for Validation of High-void-fraction Flow Regime Models | University of Michigan | $800,000 | The primary objective of this proposed research is to develop a comprehensive, high-resolution, multiphase computational fluid dynamics validation-grade flow boiling data from rod bundle geometry simulating current light water reactor fuel designs by taking advantage of the instrumentation and facility developed by the research team. In addition, the applicability of the data through initial evaluations of selected test cases using Nek-2P boiling closure models will be studied and demonstrated for two-phase flow simulations. | NEAMS | FY2021 | |
| NEUP Project 21-24471: Technical Basis of Microstructure Criteria and Accelerated Testing for Qualifying Additively-manufactured 316H Stainless Steel for High-temperature Cyclic Service | Auburn University | $800,000 | This project seeks to reveal the fundamental relationship for AM 316H SS working at 500-750 C between additively-manufactured microstructures and creep/creep-fatigue properties through a multiscale experimental and modeling approach. The project also seeks to establish the technical basis for the microstructure criteria and accelerated testing method to support near-term nuclear qualification. | RCRD&D | FY2021 | |
| NEUP Project 21-24152: Direct heating of chemical catalysts for hydrogen and fertilizer production using Microreactors | Kansas State University | $799,202 | This proposal presents a novel integration approach to deliver process heat from microreactors by directly heating the catalyst particles from the primary heat transfer fluid in a moving packed bed heat exchanger (MPBHX). In this design, the tube side of the MPBHX can be a heat pipe or primary Helium coolant as in several microreactor designs. The shell side will be moving catalyst particles, which will enter the high temperature chemical reactor upon heating. | RCRD&D | FY2021 | |
| NEUP Project 21-24287: Investigating heat transfer in horizontally oriented HTGR under normal and PCC conditions | Kansas State University | $799,762 | Experimental research will be conducted to understand heat transfer inside the graphite matrix of horizontal microscale High Temperature Gas-cooled Reactors. Existing high temperature test facilities will be used to simulate normal operation and Pressurized Conduction Cooldown. The focus of these experiments is to generate benchmark data under forced and natural convection with coupled multi-mode heat transfer in scaled-down prismatic blocks. | RCRD&D | FY2021 | |
| NEUP Project 21-24104: Thermal Hydraulics Investigation of Horizontally Orientated Layout Micro HTGRs Under Normal Operation and PCC Conditions Using Integrated Advanced Measurement Techniques | Missouri University of Science and Technology | $800,000 | The proposed novel work will make a significant pioneering contribution to advance the knowledge and understanding of horizontal micro-high temperature gas cooled reactors. Quantification of metrics will pertain to convective heat transfer coefficients along the channel and gaps, comparative rates of convective and radiative heat transfer, location of peak temperature and its temporal variation, timescales for onset of natural convection, local gas velocity profiles, gas dispersion, crossflows, and temperature profiles over channel diameter and gap thickness. | RCRD&D | FY2021 | |
| NEUP Project 21-24004: An Open Source, Parallel, and Distributed Web-Based Probabilistic Risk Assessment Platform to Support Real Time Nuclear Power Plant Risk-Informed Operational Decisions | North Carolina State University | $800,000 | The main objective of the proposed work is to develop, demonstrate, and evaluate a probabilistic risk assessment (PRA) software platform needed to address the major challenges of the current legacy PRA tools. This includes better quantification speed, integration of multi-hazard models into traditional PRAs, and model modification/simplification and documentation automation. | RCRD&D | FY2021 | |
| NEUP Project 21-24228: Quantifying the Dynamic and Static Porosity/Microstructure Characteristics of Irradiated Graphite through Multi-technique Experiments and Mesoscale Modeling | North Carolina State University | $800,000 | This project proposes a joint experimental-computational approach to probe and quantify the porosity and microstructure characteristics of irradiated nuclear graphite grades and their influence on dimensional changes and turnaround behavior, as well as mechanical properties. The chief focus will be on quantifying both the static and dynamic porosity and crack characteristics in various graphitic phases through several experimental techniques. | RCRD&D | FY2021 | |
| NEUP Project 21-24247: Multi-scale Effects of Irradiation Damage on Nuclear Graphite Properties | Pennsylvania State University | $800,000 | Irradiation induces microstructural damage in graphite, causing both dimensional and property (stiffness, strength and creep) changes as a function of the displacement damage and temperature. The biggest gap remains is the fundamental deformation mechanisms behind the property changes. Researchers propose to eliminate this gap in knowledge with a comprehensive, multi-scale experimental framework exploiting in-situ transmission electron and X-ray computed tomography. | RCRD&D | FY2021 | |
| NEUP Project 21-23975: Development of Thermal Power Dispatch Simulation Tools for BWR Flexible Plant Operation and Generation | Rensselaer Polytechnic Institute | $800,000 | In the U.S. domestic light water reactor fleet, about one-third of operational nuclear power reactors are boiling water reactors (BWRs). Thermal power extraction technologies to be designed for BWRs will be different from those for pressurized water reactors due to differences in steam generation. This study proposes to investigate the thermal and electric power dispatch and required control algorithms for dynamic heat dispatch of up to 50% of the thermal energy from a BWR plant to a hydrogen plant. | RCRD&D | FY2021 | |
| NEUP Project 21-24111: Experimental Investigations of HTGR Fission Product Transport in Separate-effect Test Facilities Under Prototypical Conditions for Depressurization and Water-ingress Accidents | Texas A&M University | $800,000 | Experimental investigations will be performed for fission product (FP) lift-off, washoff, vaporization from plateout surfaces, and transport of FP at prototypical conditions representing depressurization and water-ingress accidents. Measurements will be performed on existing separate-effect facilities using intrusive and non-intrusive techniques to obtain shear stress, deposition velocity, thermal gradient, and gas impurity for advanced correlations. Modeling will be performed using system and computational fluid dynamics codes. | RCRD&D | FY2021 | |
| NEUP Project 21-24644: High-Resolution Measurements and Advanced Modeling for Design Optimization of Advanced Small Modular Reactor Steam Generators | Texas A&M University | $800,000 | Experiments and simulations will be performed to acquire multi-parameters of pressure drop, heat and mass transfer, and flow-induced vibration (FIV) effect for the design optimization of advanced small modular reactor steam generators (SMR SG). Measurements are performed on existing SMR SG facilities using intrusive/non-intrusive techniques to obtain velocity, temperature, pressure, heat flux, and FIV effects for various geo-dimensions, spacing, pitch angles. Simulations will be performed in StarCCM, Nek5000 and coupling with Diablo | RCRD&D | FY2021 | |
| NEUP Project 21-24332: A Virtual Reality Environment for Human Reliability Assessment in the Context of Physical Security Attacks | The Ohio State University | $800,000 | Recent studies have shown that the physical security workforce accounts for 20% of the entire workforce and, therefore, is responsible for significant operational and maintence costs. To reduce the security staffing, improve performance and reduce threats, modeling and simulation and models of attacker, defender and operator behavior could be employed. This proposal aims to model human behavior using a combination of known human reliability analyses models and experimental evidence from virtual reality experiments. | RCRD&D | FY2021 | |
| NEUP Project 21-24389: High Temperature Electromagnetic Acoustic (EMAT) Transducers for Structural Health Monitoring | University of Cincinnati | $800,000 | The aim of this project is to produce an electromagnetic acoustic transducer (EMAT) technology to enable ultrasonic structural health monitoring at the METL facility and similar high temperature assets. Ultrasonic nondestructive evaluation methods can be used for monitoring a range of damage mechanisms including thermal fatigue and corrosion. The project will seek to establish core design solutions that can be used as the basis of a range of EMAT designs for different applications. | RCRD&D | FY2021 | |
| NEUP Project 21-24380: Probabilistic Validation and Risk Importance Ranking Methodology for Automation Trustworthiness and Transparency in Nuclear Power Plants | University of Illinois at Urbana-Champaign | $800,000 | This project develops a methodology to improve trustworthiness and transparency of automation technologies in nuclear power plants. The proposed methodology will monitor risk emerging from automation processes and rank the criticality of automation factors influencing automation output, plant equipment, and system performance. The feasibility and practicality of the proposed methodology will be demonstrated with two case studies focusing on implementation of nuclear power plant automation technologies. | RCRD&D | FY2021 | |
| NEUP Project 21-24162: Self-powered wireless sensor system for health monitoring of liquid-sodium cooled fast reactors | University of Notre Dame | $800,000 | The goal of this project is to develop self-powered wireless multimodal sensors and instrumentation for health monitoring and diagnosing early-stage materials degradation for high-risk components in liquid-sodium cooled fast reactors. The synergistic and innovative integrations of the multimodal sensor array, wireless communication, and thermoelectric energy harvester have crosscutting benefit for a wide range of advanced reactors. | RCRD&D | FY2021 | |
| NEUP Project 21-24102: High temperature Molten salt reactor pump component development and testing | University of Wisconsin-Madison | $800,000 | This project will provide relevant key information on the tribology of bearing material and components (such as magnets, couplers, ceramic coated wire, and coatings) in high temperature molten salts that will be required in the design of reactor pumps. Investigation of in-service inspection and monitoring of the pump internals will also be addressed in an effort to reduce down time and operation and maintenance costs. | RCRD&D | FY2021 | |
| NEUP Project 21-24226: Cost Reduction of Advanced Integration Heat Exchanger Technology for Micro-Reactors | University of Wisconsin-Madison | $799,713 | Heat exchanger technology is a high-cost component of a micro-reactor system that is also critical to the overall reliability and performance. This project will develop the underlying advanced heat exchanger technology necessary to integrate a micro-reactor with any end-user application, as well as providing internal heat exchange. Economic optimization of the heat exchanger and experimental demonstration of the technology will be accomplished. | RCRD&D | FY2021 | |
| NEUP Project 21-24382: Advanced High-Fluence Low-Flux RPV Mechanical Property Models for Extended Life | University of Wisconsin-Madison | $799,717 | This project will further develop accurate models of the mechanical property changes under life-extension conditions in reactor pressure vessel (RPV) steels using reduced order Avrami models, cluster dynamics, and atomistic methods combined with massive comprehensive databases on irradiated steels. The work will provide models critical to extending the life of U.S. pressurized water reactors, as well as new fundamental insights into flux and fluence effects and sink and precipitate evolution in reactor pressure vessels and related steels. | RCRD&D | FY2021 | |
| NEUP Project 21-24394: Computer vision and machine learning for microstructural qualification | Carnegie Mellon University | $497,518 | Quantifying and understanding microstructure is a key driver for performance-based materials qualification. In this proposal, well-curated data sets of microstructural images will be gathered and computer vision and machine learning will be applied to build quantitative deep learning frameworks to accelerate and enable qualification of nuclear materials based on microstructural features. | Crosscutting Technologies | FY2020 | |
| NEUP Project 21-24156: Experimental thermofluidic validation of TCR fuel elements using distributed temperature and flow sensing | Kansas State University | $798,250 | The overall goal of this project will be to test the performance of 3D printed Transformational Challenge Reactor core geometry parts using existing Helium flow loops and distributed temperature, and velocity sensing systems. Thermal transport capabilities of scaled 3D printed ceramic core will be evaluated experimentally and measurements will be used to qualify computational models. | Crosscutting Technologies | FY2020 | |
| NEUP Project 21-24636: Risk-informed Consequence-driven Physical Protection System Optimization for Microreactor Sites | Texas A&M University | $400,000 | This proposed project will utilize a risk-informed, consequence-driven analysis to develop an approach for "right-sizing" physical protection systems (PPS) for microreactors. The hypothesis presented for this proposal is that the explicit coupling of consequence modeling to PPS design will provide a similar benefit that can be applied prior to reactor construction. | Crosscutting Technologies | FY2020 | |
| NEUP Project 21-24131: Total Mass Accounting in Advanced Liquid Fueled Reactors | The Ohio State University | $400,000 | A total mass determination method for nuclear materials accounting (NMA) in liquid-fueled molten salt reactors will be validated with fuel-bearing salt, mixed with a + radioisotope of known activity, that will be irradiated to reproduce the practical NMA scenario in a molten salt loop. Irradiated fuel salt will be sampled and measured for its mass and activity. The mass-to-activity ratio will be used to calculate the unknown salt mass in the original container. | Crosscutting Technologies | FY2020 | |
| NEUP Project 21-24037: Design and intelligent optimization of the thermal storage and energy distribution for the TerraPower Molten Chloride Fast Reactor in an Integrated Energy System (IES) | University of Tennessee at Knoxville | $800,000 | The objective of this project is to explore the application of advanced reactors within Integrated Energy Systems, use extensive existing data from UIUC for model development and validation, and extend the predictions to larger grids and commercial applications. | Crosscutting Technologies | FY2020 | |
| NEUP Project 21-24522: Targeted Materials Characterization and Testing of Additively Manufactured Metals and Ceramics to Inform Print/Build Data Analytics | University of Texas at San Antonio | $800,000 | A collaborative program between the University of Texas at San Antonio and Boise State University is proposed to supply materials testing and characterization data sets to be leveraged by the TCR program to inform build/print data analytics. With the data provided by the proposing team, correlations among steam oxidation performance, micromechanical properties, chemical composition, local microstructure, and location specific print/build data will be achieved. | Crosscutting Technologies | FY2020 | |
| NEUP Project 21-24431: Location-specific material characterization of LPBF SS316L & IN718 TCR core structural materials | Utah State University | $800,000 | In this proposed work, we will experimentally characterize the spatial variability of the quasi-static (tensile), creep (strength and impression), and creep-fatigue properties as well as the underlying structures (microstructure and defect structures) for LPBF SS316L and IN718 components to be used as training data to the TCR program data-driven model. The resulting correlation will be used to drive the design process for an application as TCR core structural materials. | Crosscutting Technologies | FY2020 | |
| NEUP Project 21-23978: Rapid, Non-Radioactive Methods for Prediction and Quantification of Radiolytic Radical Decomposition Products in Nuclear Separations | Clemson University | $399,999 | High-throughput, non-radioactive, radical assays will be used to determine decomposition of monoamide separations complexants. Radical assay results will be correlated with classic radiolytic damage results to develop predictive models for screening complexant stability. These models will aid in single-stage separations complexant optimization, in the transition from lab-to industrial-scale nuclear waste separations and, ultimately, could yield field tests for radiolytic damage. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24350: Phosphate Mineral and Glass Waste Forms for Advanced Immobilization of Chloride and Fluoride-based Waste Streams | Clemson University | $600,000 | This proposal is intended to develop three waste form options for immobilizing the fluoride-and chloride-salt waste stream in highly durable and easily processable phosphate minerals and glasses, including phosphate apatite ceramic waste forms, phosphate glass waste forms, and phosphate glass-ceramic waste forms with apatite phase. Multiple monolithic waste form samples will be provided to DOE national laboratories for further testing. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24292: Passive multimodal tomography for dry storage casks imaging using passive neutron and gamma dosimetry and cosmic ray muons | Colorado School of Mines | $800,000 | A method for multimodal tomography of dry storage casks will be developed to determine fuel relocation and cladding failures using passive neutrons and gamma emissions in combination with cosmic ray muons. The use of multimodal imaging will allow 3-D reconstructions of the dry storage cask that would be unachievable with any single radiation source. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24374: Effects of Radiolysis on Pertechnetate under Solvent Extraction Conditions, including Tri-Butyl Phosphate | CUNY, Hunter College | $399,624 | The overarching objective of the proposed work is to assess the impact of radiolysis on pertechnetate speciation during tri-butylphosphate (TBP) solvent extractions from the molecular level to macroscale. The research in this project is designed to understand the interplay of radiolysis, degradation product formation, other important redox active metals, and oxidation states of technetium on its speciation and distribution coefficients in solvent extraction processes. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24183: Experimental investigation and development of models and correlations for cladding-to-coolant heat transfer phenomena in transient conditions in support of TREAT and the LWR fleet. | Massachusetts Institute of Technology | $800,000 | Thermal-hydraulics transient heat transfer phenomena of relevance for the safety and the operation of the TREAT and light water reactors will be investigated. The performance of accident tolerant fuel materials during a reactivity initiated accident scenario and post-critical heat flux and reflood scenarios will be elucidated, as well as the development of models and correlations to be integrated into computational tools for the design and safety analysis of nuclear systems. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24666: Wireless Multifunctional Ultrasonic Arrays with Interdigital and Airborne Transducers for Monitoring Leakage and Corrosion Conditions of Welded Dry Storage Canisters | Mississippi State University | $800,000 | This project aims to develop and validate wireless, multifunctional, ultrasonic sensor arrays that enable on-demand, quantitative interrogation and real-time monitoring of both the canister leakage indicators (helium, helium/air mixture, internal pressure, and temperature) and corrosion conditions (free and/or vapor water). The developed arrays will be fully functional, wirelessly powered and communicated, and compact. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24188: Uranium recovery from used nuclear fuel using metal sulfides | Northwestern University | $400,000 | An alternative and original method to recover uranium from spent fuel is proposed. This method will utilize a new type of regenerable sorbent materials with high selectivity in capturing uranium from complex mixtures in acidic solutions, such as those found in used nuclear fuel of high-assay low-enriched uranium. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24225: Characterizing Fuel Response and Quantifying Coolable Geometry of High-Burnup Fuel | Oregon State University | $800,000 | This study seeks to objectively determine, through empirical and numerical means, the actual impact of fuel dispersion in-core after fuel failure and whether high burnup dispersed fuel compromises coolable geometry and long-term cooling. The outcome of this study will yield an objective means of assessing two criteria (coolable geometry and long-term cooling) within the existing regulatory process to comprehensively understand whether it is feasible to increase burnup, while satisfying 10 CFR 50.46. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24288: Innovative Methods for Interrogation of DSC Internal Conditions | Oregon State University | $800,000 | The proposed work takes a two-pronged approach. The team will study techniques involving only external sensors and equipment, which could be deployed on existing dry storage canisters. In addition, small sensors located inside the canister that can be externally powered and read through the canister wall will also be investigated. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24439: Development of Novel Corrosion-Responsive Buffer Materials for Long-Term Immobilization of High-Level Nuclear Waste | Pennsylvania State University | $800,000 | The goal of this project is to develop a novel cementitious buffer material (CBM) for the safe disposal of spent nuclear fuel (SNF). The primary aim is to identify and characterize novel Mg-Al-P CBMs, complete with assessments of their repository stability as well as their transport and immobilization of radionuclides. The secondary aim is to use in-situ UT-EIS monitoring to understand the corrosive failure at the canister-CBM interface and provide long-term performance modeling of SNF packages. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24461: Estimation of low temperature cladding failures during an RIA transient | Pennsylvania State University | $800,000 | Researchers aim to create a multiphysics description of cladding response during a RIA, especially at high burnup, coupling reactor physics, thermal hydraulics and mechanics. The creation of a thermomechanical model in Bison will be the result of this project which can be used to evaluate the likelihood of low temperature cladding failures during a postulated RIA on a typical fuel rod (as these can lead to channel blockage), and thus identify the most important conditions to be studied at TREAT. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24460: Multiscale Modeling and Experiments for Investigating High Burnup LWR Fuel Rod Behavior Under Normal and Transient Conditions | Texas A&M University | $800,000 | The main objective of this work is to achieve a mechanistic understanding of and to develop a predictive model for the fuel rod behavior at high burn-up under both normal and transient conditions. Therefore, this study will provide the nuclear industry with validated, physics-based criteria to fuel fragmentation thresholds and rod mechanical integrity limits. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24388: Redox Chemistry of UO2 under Repository Relevant Conditions in the Presence of Zircaloy and Waste Canister Material | University of California, Irvine | $800,000 | This project will seek to improve understanding of spent nuclear fuel (SNF) corrosion. Hydrothermal experiments of SNF with cladding and waste canister material will give insights into the redox potential formed due to secondary phase formation as consequence of corrosion in a failed canister. The experimentally derived data about secondary phase formation will be utilized for phase relationship analysis to decipher the redox conditions and thus provide source term for performance assessment models of deep geologic repositories. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24006: High-fidelity modeling of fuel-to-coolant thermomechanical transport behaviors under transient conditions | University of Florida | $800,000 | The objective of the proposal is to develop a high-fidelity modeling tool that can capture some of the important phenomena in high burnup UO2 and ATF fuels during transient conditions. The BlueCRAB tool set will be improved and used to analyze TREAT loss of coolant accident experimental results. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24312: Accelerating the development of reliable and robust machine learning-based interatomic potentials for the prediction of molten salt structure and properties | University of Massachusetts Lowell | $400,000 | Machine learning-based interatomic potentials (MLIPs) used in molecular dynamics (MD) can accurately and efficiently predict molten salt properties. However many machine learning-based methods require large training sets, and can fail unpredictably. This project will overcome these challenges by developing a method for efficiently sampling diverse configurations from MD to train reliable and robust neural network potentials, and develop new models for predicting errors in MLIPs. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24697: Dual External Leak Sensing and Monitoring for Dry Storage Canister | University of Nebraska, Lincoln | $800,000 | Researchers aim to develop two complementary external sensing methods to evaluate the integrity of DSC through internal pressure monitoring and helium leakage detection. The proposed diffuse ultrasonic wave method will be able to measure biaxial strains in the canister wall with high sensitivity and minimum temperature effects. An innovative capacitance MEMS sensor will be developed for helium concentration measurement in air based on the extremely low permittivity of helium. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24449: Multi-modal Surface Acoustic Wave Sensing System for Pressure and Temperature monitoring of Spent Fuel Canisters | University of North Texas | $800,000 | University of North Texas (UNT) will collaborate with Oak Ridge National Laboratory (ORNL) and National Energy Technology Laboratory (NETL) to develop a multi-modal wireless passive SAW (Surface Acoustic Wave) sensor array, which are deployed on the outside surface of the canister, to monitor the strain of the canister and thus determine the inside pressure. In addition, the SAW strain sensor could also measure the surface temperature and potentially monitor helium gas leak. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24265: Fragmentation and Thermal Energy Transport of Cr-doped Fuels under Transient Conditions | University of Pittsburgh | $799,999 | This project will focus on multiple aspects of experimental testing and engineering-scale modeling in understanding thermal energy transport from high burnup, fractured/fragmented accident tolerant fuels, establishing a strong scientific basis to fill a critical knowledge data gap for modeling and simulation of transient fuel performance and safety, such as loss of coolant accident, for future integral testing and fuel licensing. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24310: Fusion of Distributed Fiber Optics, Acoustic NDE, and Physics-Based AI for Spent Fuel Monitoring | University of Pittsburgh | $800,000 | The proposal will leverage new concepts in the fusion between fiber optic distributed acoustic sensing and advanced acoustic nondestructive evaluation techniques with artificial intelligence enhanced classification frameworks to quantitatively characterize the state of dry cask storage containers for spent fuel monitoring, externally and non-invasively, without introducing additional risks of failure. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24261: Internal Wireless Sensors for Dry Cask Storage | University of South Carolina | $800,000 | The effort will test the reliability of wireless, internal sensors after exposure to drying and storage conditions. These sensors are used to internally monitor temperature, pressure, and dose. Radiation shielding will also be designed to protect sensors during long-term storage. The effort will develop piezoelectric techniques for miniaturization of optical emission spectroscopy for internal monitoring of gas composition during drying and long-term storage. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24533: Non-destructive Evaluation of Dry Storage Canisters Using Acoustic Sensing | University of Southern California | $800,000 | The objective of this project is to develop a robust non-destructive evaluation (NDE) technique based on acoustic sensing to detect impurity gases in a sealed (welded) dry storage canister (DSC) using only measurements collected on the external surface of the DSC. The method is based on the time-of-flight analysis of acoustic signals propagating through the fill gas of a DSC, which is influenced by the composition, density and temperature of the propagation medium. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-23984: Safety Implications of High Burnup Fuel for a 2-Year PWR Fuel Cycle | University of Tennessee at Knoxville | $800,000 | The objective of this project is to perform safety analysis of high burnup fuel for a Westinghouse 4-Loop Pressurized Water Reactor. The work aims to identify potential opportunities and gaps for high burnup fuel by utilizing both well-established and modern methodologies to model reactor physics, thermal-hydraulics, and plant system-level response that ultimately provide feedback to fuel performance analysis. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-23985: Fuel-to-Coolant Thermomechanical Behaviors Under Transient Conditions | University of Tennessee at Knoxville | $800,000 | This project will enhance the prediction of thermo-mechanical fuel-to-coolant heat transfer under transient conditions by using a coupled analysis and experiment approach. The effort is relevant to both high-burnup (> 62GWd/t) fuel applications and Accident Tolerant Fuel. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24070: Modeling high-burnup LWR fuel behavior under normal operating and transient conditions | University of Tennessee at Knoxville | $800,000 | This project aims to develop a high-burnup light water reactor fuel modeling capability to implement in the BISON code that would enable the accurate fuel rod behavior simulation during normal operation and design basis accidents, as wells as the identification of the rod life-limiting factors. Mechanistic engineering models will be developed for key phenomena, in particular, high burnup structure evolution, fuel fragmentation, and fission gas release. Traditional and accident tolerant fuels will be considered. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24033: Redox Chemistry in Nuclear Materials Storage Matrices under Ambient and Accelerated Aging Conditions | University of Washington | $800,000 | Deep geologic repositories must safely contain hazardous, high-activity nuclear wastes at geologic time-scales. However, such capability is centrally dependent on the element-specific redox chemistry within and at the interface of storage vessels. A comprehensive study of redox chemistry in cements used in long-term storage is proposed and emphasizes: 1) the actual consequences of accelerated aging modalities and 2) the novel use of newly available capabilities in advanced x-ray spectroscopies. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24063: Post-DNB Thermo-mechanical Behavior of Near-term ATF Designs in Simulated Transient Conditions | University of Wisconsin-Madison | $800,000 | The goals of the proposed research are to conduct coupled experimental and modeling investigations of thermo-mechanical performance of coated accident tolerant zirconium alloy claddings with simulated burnup doped fuels under thermal transients to predict complex thermal and mass transport phenomena of near-term Accident Tolerant Fuel designs in accident conditions. Experiments and modeling for understanding both cladding-coolant and fuel-coolant interactions will be performed. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24582: Machine-Learning-Accelerated Molecular Dynamics Approaches for Molten Salts | University of Wisconsin-Madison | $399,477 | New machine learning potential (MLP) approaches and new MLPs to enable rapid prediction of molten salt (FLiBe and Nal-MgCl2 with impurities) properties with near ab initio quantum mechanical accuracy will be developed. Uncertainty quantification with active learning and on-the-fly fitting will greatly accelerate MLP training. This work will support dramatically increased simulation speeds and associated data generation and understanding for molten salts. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24067: Development of Full Understanding of Mechanical-Chemical Coupling in Bentonite THMC processes | Virginia Polytechnic Institute and State University | $800,000 | The central hypothesis is that mechanical stress in an engineered barrier can lead to pressure solution of solid minerals, leading to significant changes in pore water chemistry, which affects bentonite stability, longevity of the waste pack, and dissolution and migration of nuclides. The overall objective of this project is to develop full understanding of the role of pressure solution on pore water chemistry, the implications to large-scale heterogeneity, and THMC processes. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-23987: Separate and Multi-Physics Effects IRPhEP Benchmark Evaluation using SNAP Experiments | Georgia Institute of Technology | $400,000 | The proposed project will develop an International Reactor Physics Experiment Evaluation Project (IRPhEP) mulitphysics microreactor benchmark evaluation based on data from the Systems for Nuclear Auxiliary Power (SNAP) program. This work will include systematic assessments of the experimental data with meticulous compilation and documentation, and validation of specific NEAMS tools to model effects that are unique to microreactors technologies. | Nuclear Energy | FY2020 | |
| NEUP Project 21-24630: Integral Benchmark Evaluation of Zero-Power Tests and Multi-Cycle Depletion Experimental Data of TVA WB1 Cycles 1-3 | North Carolina State University | $400,000 | This project proposes to develop an integral benchmark evaluation of available experimental data for zero-power tests and multi-cycle depletion for consistent and comprehensive validation of both novel high-fidelity and traditional multi-physics tools. The benchmark evaluation will be based on operational and measured data from the Pressurized Water Reactor Watts Bar Unit 1 released by Tennessee Valley Authority. | Nuclear Energy | FY2020 | |
| NEUP Project 21-24186: Regenerating Missing Experimental Parameters with Data-Assimilation Methods for MSRE Transient Benchmark Development and Evaluation | Virginia Commonwealth University | $400,000 | The proposed project will regenerate the undocumented basic data from available experimental data of the MSRE using advanced data-assimilation methods to facilitate the whole-loop modeling of the representative MSRE transients, and perform a thorough MSRE transient benchmark evaluation for the IRPhEP handbook. | Nuclear Energy | FY2020 | |
| NEUP Project 21-24194: Implementation of improved quasi-static, time-dependent, multi-physics methodology in Shift | Georgia Institute of Technology | $600,000 | A practical reference calculation route for time-dependent coupled Monte Carlo calculations, using Shift, will be developed. The proposed framework will be tailored to depletion and slowly varying transients, but with the flexibility to perform thermal-hydraulic time-dependent calculations with minimal computational overheads. This method relies on a hybrid-resolution stochastic approach in conjunction with a substep technique. | NEAMS | FY2020 | |
| NEUP Project 21-24078: Material transport model development and integration in the System Analysis Module (SAM) code | Rensselaer Polytechnic Institute | $400,000 | This project proposes to develop and implement models for System Analysis Module, which accurately characterize the sink, source, and interaction terms of key material species that are or may be present in various advanced reactor designs. | NEAMS | FY2020 | |
| NEUP Project 21-24195: Enhancing Yellowjacket for Modeling the Impact of Radiation and Stress on the Corrosion of Molten-Salt-Facing Structural Components | University of Florida | $692,088 | The objective of this project is to add the capability to model the impact of radiation and stress on corrosion to the Yellowjacket code, as well as to use Yellowjacket to create surrogate models that will be added to engineering-scale codes like Grizzly. We will also collect new experimental data for validation that quantifies the impact of stress and radiation on corrosion of 316 stainless steel in molten fluoride salts. | NEAMS | FY2020 | |
| NEUP Project 21-24405: Development of a High-fidelity Flow Boiling Database for Validation of High-void-fraction Flow Regime Models | University of Michigan | $800,000 | The primary objective of this proposed research is to develop a comprehensive, high-resolution, multiphase computational fluid dynamics validation-grade flow boiling data from rod bundle geometry simulating current light water reactor fuel designs by taking advantage of the instrumentation and facility developed by the research team. In addition, the applicability of the data through initial evaluations of selected test cases using Nek-2P boiling closure models will be studied and demonstrated for two-phase flow simulations. | NEAMS | FY2020 | |
| NEUP Project 21-24471: Technical Basis of Microstructure Criteria and Accelerated Testing for Qualifying Additively-manufactured 316H Stainless Steel for High-temperature Cyclic Service | Auburn University | $800,000 | This project seeks to reveal the fundamental relationship for AM 316H SS working at 500-750 C between additively-manufactured microstructures and creep/creep-fatigue properties through a multiscale experimental and modeling approach. The project also seeks to establish the technical basis for the microstructure criteria and accelerated testing method to support near-term nuclear qualification. | RCRD&D | FY2020 | |
| NEUP Project 21-24152: Direct heating of chemical catalysts for hydrogen and fertilizer production using Microreactors | Kansas State University | $799,202 | This proposal presents a novel integration approach to deliver process heat from microreactors by directly heating the catalyst particles from the primary heat transfer fluid in a moving packed bed heat exchanger (MPBHX). In this design, the tube side of the MPBHX can be a heat pipe or primary Helium coolant as in several microreactor designs. The shell side will be moving catalyst particles, which will enter the high temperature chemical reactor upon heating. | RCRD&D | FY2020 | |
| NEUP Project 21-24287: Investigating heat transfer in horizontally oriented HTGR under normal and PCC conditions | Kansas State University | $799,762 | Experimental research will be conducted to understand heat transfer inside the graphite matrix of horizontal microscale High Temperature Gas-cooled Reactors. Existing high temperature test facilities will be used to simulate normal operation and Pressurized Conduction Cooldown. The focus of these experiments is to generate benchmark data under forced and natural convection with coupled multi-mode heat transfer in scaled-down prismatic blocks. | RCRD&D | FY2020 | |
| NEUP Project 21-24104: Thermal Hydraulics Investigation of Horizontally Orientated Layout Micro HTGRs Under Normal Operation and PCC Conditions Using Integrated Advanced Measurement Techniques | Missouri University of Science and Technology | $800,000 | The proposed novel work will make a significant pioneering contribution to advance the knowledge and understanding of horizontal micro-high temperature gas cooled reactors. Quantification of metrics will pertain to convective heat transfer coefficients along the channel and gaps, comparative rates of convective and radiative heat transfer, location of peak temperature and its temporal variation, timescales for onset of natural convection, local gas velocity profiles, gas dispersion, crossflows, and temperature profiles over channel diameter and gap thickness. | RCRD&D | FY2020 | |
| NEUP Project 21-24004: An Open Source, Parallel, and Distributed Web-Based Probabilistic Risk Assessment Platform to Support Real Time Nuclear Power Plant Risk-Informed Operational Decisions | North Carolina State University | $800,000 | The main objective of the proposed work is to develop, demonstrate, and evaluate a probabilistic risk assessment (PRA) software platform needed to address the major challenges of the current legacy PRA tools. This includes better quantification speed, integration of multi-hazard models into traditional PRAs, and model modification/simplification and documentation automation. | RCRD&D | FY2020 | |
| NEUP Project 21-24228: Quantifying the Dynamic and Static Porosity/Microstructure Characteristics of Irradiated Graphite through Multi-technique Experiments and Mesoscale Modeling | North Carolina State University | $800,000 | This project proposes a joint experimental-computational approach to probe and quantify the porosity and microstructure characteristics of irradiated nuclear graphite grades and their influence on dimensional changes and turnaround behavior, as well as mechanical properties. The chief focus will be on quantifying both the static and dynamic porosity and crack characteristics in various graphitic phases through several experimental techniques. | RCRD&D | FY2020 | |
| NEUP Project 21-24247: Multi-scale Effects of Irradiation Damage on Nuclear Graphite Properties | Pennsylvania State University | $800,000 | Irradiation induces microstructural damage in graphite, causing both dimensional and property (stiffness, strength and creep) changes as a function of the displacement damage and temperature. The biggest gap remains is the fundamental deformation mechanisms behind the property changes. Researchers propose to eliminate this gap in knowledge with a comprehensive, multi-scale experimental framework exploiting in-situ transmission electron and X-ray computed tomography. | RCRD&D | FY2020 | |
| NEUP Project 21-23975: Development of Thermal Power Dispatch Simulation Tools for BWR Flexible Plant Operation and Generation | Rensselaer Polytechnic Institute | $800,000 | In the U.S. domestic light water reactor fleet, about one-third of operational nuclear power reactors are boiling water reactors (BWRs). Thermal power extraction technologies to be designed for BWRs will be different from those for pressurized water reactors due to differences in steam generation. This study proposes to investigate the thermal and electric power dispatch and required control algorithms for dynamic heat dispatch of up to 50% of the thermal energy from a BWR plant to a hydrogen plant. | RCRD&D | FY2020 | |
| NEUP Project 21-24111: Experimental Investigations of HTGR Fission Product Transport in Separate-effect Test Facilities Under Prototypical Conditions for Depressurization and Water-ingress Accidents | Texas A&M University | $800,000 | Experimental investigations will be performed for fission product (FP) lift-off, washoff, vaporization from plateout surfaces, and transport of FP at prototypical conditions representing depressurization and water-ingress accidents. Measurements will be performed on existing separate-effect facilities using intrusive and non-intrusive techniques to obtain shear stress, deposition velocity, thermal gradient, and gas impurity for advanced correlations. Modeling will be performed using system and computational fluid dynamics codes. | RCRD&D | FY2020 | |
| NEUP Project 21-24644: High-Resolution Measurements and Advanced Modeling for Design Optimization of Advanced Small Modular Reactor Steam Generators | Texas A&M University | $800,000 | Experiments and simulations will be performed to acquire multi-parameters of pressure drop, heat and mass transfer, and flow-induced vibration (FIV) effect for the design optimization of advanced small modular reactor steam generators (SMR SG). Measurements are performed on existing SMR SG facilities using intrusive/non-intrusive techniques to obtain velocity, temperature, pressure, heat flux, and FIV effects for various geo-dimensions, spacing, pitch angles. Simulations will be performed in StarCCM, Nek5000 and coupling with Diablo | RCRD&D | FY2020 | |
| NEUP Project 21-24332: A Virtual Reality Environment for Human Reliability Assessment in the Context of Physical Security Attacks | The Ohio State University | $800,000 | Recent studies have shown that the physical security workforce accounts for 20% of the entire workforce and, therefore, is responsible for significant operational and maintence costs. To reduce the security staffing, improve performance and reduce threats, modeling and simulation and models of attacker, defender and operator behavior could be employed. This proposal aims to model human behavior using a combination of known human reliability analyses models and experimental evidence from virtual reality experiments. | RCRD&D | FY2020 | |
| NEUP Project 21-24389: High Temperature Electromagnetic Acoustic (EMAT) Transducers for Structural Health Monitoring | University of Cincinnati | $800,000 | The aim of this project is to produce an electromagnetic acoustic transducer (EMAT) technology to enable ultrasonic structural health monitoring at the METL facility and similar high temperature assets. Ultrasonic nondestructive evaluation methods can be used for monitoring a range of damage mechanisms including thermal fatigue and corrosion. The project will seek to establish core design solutions that can be used as the basis of a range of EMAT designs for different applications. | RCRD&D | FY2020 | |
| NEUP Project 21-24380: Probabilistic Validation and Risk Importance Ranking Methodology for Automation Trustworthiness and Transparency in Nuclear Power Plants | University of Illinois at Urbana-Champaign | $800,000 | This project develops a methodology to improve trustworthiness and transparency of automation technologies in nuclear power plants. The proposed methodology will monitor risk emerging from automation processes and rank the criticality of automation factors influencing automation output, plant equipment, and system performance. The feasibility and practicality of the proposed methodology will be demonstrated with two case studies focusing on implementation of nuclear power plant automation technologies. | RCRD&D | FY2020 | |
| NEUP Project 21-24162: Self-powered wireless sensor system for health monitoring of liquid-sodium cooled fast reactors | University of Notre Dame | $800,000 | The goal of this project is to develop self-powered wireless multimodal sensors and instrumentation for health monitoring and diagnosing early-stage materials degradation for high-risk components in liquid-sodium cooled fast reactors. The synergistic and innovative integrations of the multimodal sensor array, wireless communication, and thermoelectric energy harvester have crosscutting benefit for a wide range of advanced reactors. | RCRD&D | FY2020 | |
| NEUP Project 21-24102: High temperature Molten salt reactor pump component development and testing | University of Wisconsin-Madison | $800,000 | This project will provide relevant key information on the tribology of bearing material and components (such as magnets, couplers, ceramic coated wire, and coatings) in high temperature molten salts that will be required in the design of reactor pumps. Investigation of in-service inspection and monitoring of the pump internals will also be addressed in an effort to reduce down time and operation and maintenance costs. | RCRD&D | FY2020 | |
| NEUP Project 21-24226: Cost Reduction of Advanced Integration Heat Exchanger Technology for Micro-Reactors | University of Wisconsin-Madison | $799,713 | Heat exchanger technology is a high-cost component of a micro-reactor system that is also critical to the overall reliability and performance. This project will develop the underlying advanced heat exchanger technology necessary to integrate a micro-reactor with any end-user application, as well as providing internal heat exchange. Economic optimization of the heat exchanger and experimental demonstration of the technology will be accomplished. | RCRD&D | FY2020 | |
| NEUP Project 21-24382: Advanced High-Fluence Low-Flux RPV Mechanical Property Models for Extended Life | University of Wisconsin-Madison | $799,717 | This project will further develop accurate models of the mechanical property changes under life-extension conditions in reactor pressure vessel (RPV) steels using reduced order Avrami models, cluster dynamics, and atomistic methods combined with massive comprehensive databases on irradiated steels. The work will provide models critical to extending the life of U.S. pressurized water reactors, as well as new fundamental insights into flux and fluence effects and sink and precipitate evolution in reactor pressure vessels and related steels. | RCRD&D | FY2020 | |
| NEUP Project 19-16987: Novel miniature creep tester for virgin and neutron irradiated clad alloys with benchmarked multiscale modeling and simulations | North Carolina State University | $800,000 | This project will develop a miniature creep machine to collect rapid thermal creep and load relaxation data for two selected ferritic alloys under "as-received" and irradiated conditions. Fast and accurate measurements of creep deformation are essential for qualifying new alloys for long term use in current and next generation reactors. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-17150: Speciation and Behavior of Neptunium and Zirconium in Advanced Separation Process | Oregon State University | $800,000 | This project will further develop the understanding of nuclear fuel reprocessing using Co-Decontamination (CoDCon). Radiolytic degradation products of tributylphosphate, nitric acid, redox buffer, masking agent, and water greatly affect the redox speciation, complexation and partitioning of the recycled metals. Fundamental understanding of chemical speciation and partitioning of Neptunium and Zerconium under such conditions is required. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-17395: Modeling and Uncertainty Analysis of MSR Nuclear Material Accounting Methods for Nuclear Safeguards | Pennsylvania State University | $800,000 | This project will model and analyze the limits of detection for the diversion of nuclear materials from a molten salt reactor (MSR) fuel cycle. MSR depletion under a range of uranium and/or plutonium diversion to quantify the resulting differences in salt composition will be evaluated. Sensors will also be investigated to quantify fuel salt contents and correlate the outputs with the reactor models to predict diversion detection. Results will be coupled with robust uncertainty analysis to determine limits of detection. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-16583: Neutron Radiation Effect on Diffusion between Zr (and Zircaloy) and Cr for Accurate Lifetime Prediction of ATF | The Ohio State University | $499,997 | This project will perform systematic diffusion studies on both neutron-irradiated and unirradiated accident tolerant fuel samples to obtain precise diffusion coefficients. This will result in a precise evaluation of the pure neutron irradiation effect on diffusion in these systems and enable accurate life prediction of the accident tolerant fuels. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-17381: High Throughput Assessment of Creep Behavior of Advanced Nuclear Reactor Structural Alloys by Nano/microindentation | University of Minnesota, Twin Cities | $800,000 | This project will develop a high throughput assessment of creep behavior of advanced nuclear reactor structural alloys by nano/microindentation. Experimental datasets will inform polycrystalline deformation models to predict material response over a variety of creep conditions. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-16549: Thermal Conductivity Measurement of Irradiated Metallic Fuel Using TREAT | University of Pittsburgh | $500,000 | This project intends to provide accurate thermal conductivity and thermal diffusivity data with microstructure characterization of metallic (U-Pu-Zr) fuel as a function of burnup and attain fundamental understanding of the thermal conductivity of the irradiated fuel to inform and validate computational models. This will be accomplished using an innovative thermal wave technique in the Transient Reactor Test Facility at the Idaho National Laboratory, with the Minimal Activation Reusable Capsule Holder. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-17002: Remote Laser-based Nondestructive Evaluation for Post-Irradiation Examination of ATF Cladding | University of South Carolina | $800,000 | To enable advanced nondestructive characterization techniques for light water reactor fuels that can be applied to the cladding coating, a remote nondestructive evaluation post irradiation inspection approach will be developed. This technique will measure the cladding coating layer thickness and detect defects within the cladding such as corrosion, micro-cracking and delamination. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-17276: Radiation-Induced Swelling in Advanced Nuclear Fuel | University of Tennessee at Knoxville | $799,989 | The microstructural evolution of advanced fuel (uranium carbide and uranium nitride) under fission-fragment type radiation has not been studied and remains unclear. This project will utilize advanced synchrotron X-ray characterization using microgram samples to obtain detailed nanoscale information on radiation-induced volumetric swelling and microstrain. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-16848: Metal-Functionalized Membranes for Radioiodine Capture | University of Utah | $799,031 | This proposed research will investigate high-surface area (>300 m2/g) metal-functionalized membranes. These novel chemically durable and mechanically robust membranes are formed using an aqueous fabrication process, which results in an interconnected porosity that is highly controllable, providing hierarchical structures ranging from the nano-to micrometer-scales. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-17350: Development and Experimental Validation of Pitting and SCC Models for Welded Stainless Steel Dry Storage Containers Exposed to Atmospheric Environments | University of Virginia | $799,027 | The specific goals of this project are to: (a) validate the maximum pit size model for dry storage canister relevant corrosion conditions as well as quantifying the effects of limited cathodic current on stress corrosion cracking (SCC) kinetics, (b) demonstrate a means to quantitatively rank the risk of SCC based on measurable parameters, (c) perform probabilistic predictions of SCC growth, and (d) validate the model predictions. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-16879: Proactive Hybrid Nuclear with Load Forecasting | Brigham Young University | $799,933 | This project develops new capabilities of design and dispatch optimization of nuclear hybrid energy systems (NHES) in the "Risk Analysis Virtual Environment (RAVEN)" modelling software. Blended (physics-based and data-driven) machine learning will be applied to forecast demand and production of thermal and electrical loads. Two experimental case studies are proposed to test the software developments with a lab-scale thermal energy storage and with a large district energy system. As a final step, the software developments will be generalized to other NHES. | Nuclear Energy | FY2019 | |
| NEUP Project 19-17461: Development and Evaluation of Neutron Thermalization Integral Benchmarks for Advanced Reactor Applications | North Carolina State University | $400,000 | This project will develop integral benchmarks that aim to examine thermal neutron scattering data for graphite (ideal and nuclear), light water, and molten salt. The benchmark evaluations will be contributed to the International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhEP) database. | Nuclear Energy | FY2019 | |
| NEUP Project 19-16739: Improvements of Nuclear Data Evaluations for Lead Isotopes in Support of Next Generation Lead-Cooled Fast Systems | Rensselaer Polytechnic Institute | $400,000 | The objective of this project is to improve the accuracy of neutronics simulation of lead-based systems by improving the nuclear data of lead isotopes. The nuclear data for lead will be reevaluated with emphasis of the intermediate and fast energy regions that are required by reactor applications currently sought by several industrial entities. The deliverables of this project are new lead isotopes evaluations that will be candidates for inclusion in a future Evaluated Nuclear Data Library (ENDF) release. | Nuclear Energy | FY2019 | |
| NEUP Project 19-17219: Using Integral Benchmark Experiments to Improve Differential Nuclear Data Evaluations | University of New Mexico | $400,000 | This project will use the results of integral benchmark experiment to inform differential nuclear data evaluations and improve the predictive capability of modeling and simulation (M&S) tools. This goal will be accomplished by developing capabilities to assess the sensitivity of integral benchmark results to evaluated nuclear data parameters, and by using data assimilation tools to directly adjust the evaluated data parameters and improve the accuracy of M&S tools. | Nuclear Energy | FY2019 | |
| NEUP Project 19-16743: Paths Forward for Nuclear Energy: Using a Nationwide Post-Stratified Hierarchical Model to Facilitate Matching of New Nuclear Technologies to Receptive Host Communities | University of Oklahoma | $390,393 | This project will enable deployment of advanced nuclear technologies by developing a model, and an accompanying web-based tool that can be utilized by technology entrepreneurs, that identifies public support for siting new nuclear technologies at very local spatial scales across the US. The model will employ hierarchically structured, post stratified analysis of the largest US pooled-time series dataset on geocoded public support for nuclear technologies. | Nuclear Energy | FY2019 | |
| NEUP Project 19-16995: A Cyber-Attack Detection Platform for Cyber Security of Digital Instrumentation and Control Systems | University of Tennessee at Knoxville | $799,995 | The proposed research will develop a robust cyber-attack detection system (CADS) for monitoring digital instrumentation and control (I&C) systems. The project will develop a robust research tool for evaluating cyber defense of digital I&C systems and provide a framework for a cyber-attack detection system that provides continuous assurance of the security of digital I&C systems in nuclear power plants (NPPs). | Nuclear Energy | FY2019 | |
| NEUP Project 19-17327: Multi-Timescale Nuclear-Renewable Hybrid Energy Systems Operations to Improve Electricity System Resilience, Reliability, and Economic Efficiency | University of Texas at Dallas | $800,000 | The overarching objective of this project is to develop a multi-timescale nuclear-renewable hybrid energy systems (N-R HESs) operations framework to provide different types of grid products. The project will model and analyze the capabilities of N-R HESs to provide power grid services at different timescales ranging from seconds to days, such as day-ahead unit commitment, flexible ramping (5-45 minutes), regulation reserves (1-5 minutes), and frequency response (less than seconds). | Nuclear Energy | FY2019 | |
| NEUP Project 19-17192: The Design and Investigation of Novel Mechanical Filters for Molten Salt Reactors | Abilene Christian University | $762,246 | Researchers will develop a novel mechanical filtration system. The project will include the collection of filter media performance data and filter regeneration performance data for a novel sintered nickel-based filter prototype. The project will also provide a filter design that facilitates remote filter removal, cooling, replacement, and assay of fissile material hold-up in the filter media. | RCRD&D | FY2019 | |
| NEUP Project 19-16980: Determining the Effects of Neutron Irradiation on the Structural Integrity of Additively Manufactured Heat Exchangers for Very Small Modular Reactor Applications | Auburn University | $400,000 | Researchers will determine how to best use laser-powder bed fusion additive manufacturing methods for generating radiation-resistant channel/pore-embedded structures from Inconel (alloy 625 or 718) nickel-based superalloys for special purpose reactor (i.e. very small modular reactor) heat exchangers. | RCRD&D | FY2019 | |
| NEUP Project 19-17413: Validated, Multi-Scale Molecular Dynamics Simulations to Predict the Thermophysical Properties of Molten Salts Containing Fuel, Fission, and Corrosion Products | Brigham Young University | $798,291 | Researchers will use first principles molecular dynamics (FPMD) simulations on molten salts containing impurities including fuel, fission products, and corrosion products. These will be used to develop a classical molecular dynamics (CMD) potential. CMD will then be used to predict properties for a wide variety of salt compositions and temperatures, and physical property measurements will be performed to validate those predictions. Property correlations will be developed from this data. | RCRD&D | FY2019 | |
| NEUP Project 19-17183: Mixing of helium with air in reactor cavities following a pipe break in HTGRs | City College of New York | $800,000 | Researchers will conduct separate effects tests to obtain experimental validation data on mixing of helium and air in reactor building cavities during and after blowdown in HTGRs. Air and helium concentrations, and gas mixture velocity and temperature fields will be measured in simulated reactor cavities. An existing helium flow loop will be used as the source of high pressure/high temperature helium for injection into the cavities and different break configurations will be experimentally investigated. | RCRD&D | FY2019 | |
| NEUP Project 19-16391: GuArDIAN: General Active Sensing for conDItion AssessmeNt | Duke University | $800,000 | Researchers will develop a dependable, autonomous or semi-autonomous (i.e. low human involvement), and minimally disruptive framework for monitoring equipment and components in nuclear reactors. The project will develop GUARDIAN; a robust active sensing framework through the integration of model-based inference and mobile actuating/sensing robots. | RCRD&D | FY2019 | |
| NEUP Project 19-17251: Measuring Mechanical Properties of Select Layers and Layer Interfaces of TRISO Particles via Micromachining and In-Microscope Tensile Testing | Idaho State University | $799,815 | Researchers will characterize the strength of TRISO-coated particle layers and interfaces using FIB micro-machining and in-TEM tensile testing. Tensile test samples from coating layers of (1) unirradiated surrogate (fuel) TRISO particles, (2) unirradiated fueled TRISO particles and (3) irradiated fueled TRISO particles will be studied. Results of this project will both benefit and leverage the AGR Program. | RCRD&D | FY2019 | |
| NEUP Project 19-17185: Demonstrating Reactor Autonomous Control Framework using Graphite Exponential Pile | Massachusetts Institute of Technology | $400,000 | Researchers will demonstrate a detection-prediction-feedback framework for nuclear system autonomous control. It will adopt multiple detector channels to enable control feedback to spatially dependent perturbations. It will also utilize high-fidelity solutions trained surrogate models for real-time prediction and decision-making. In addition to the method development, the proposal will entail a first-of-a-kind engineering demonstration using the MIT Graphite Exponential Pile (MGEP). | RCRD&D | FY2019 | |
| NEUP Project 19-16754: Simultaneous Corrosion/Irradiation Testing in Lead and Lead-Bismuth Eutectic: The Radiation Decelerated Corrosion Hypothesis | Massachusetts Institute of Technology | $762,823 | Researchers will test candidate FeCrSi and F/M alloys in a new, simultaneous corrosion/radiation facility to try to identify an alloy that will satisfy all requirements for Lead Fast Reactor structural materials. Microstructural characterization, mechanical property testing, and corrosion tests, both during irradiation and following ion/He pre-conditioning, will assess how irradiation affects corrosion, potentially slowing it. | RCRD&D | FY2019 | |
| NEUP Project 19-17173: Ni-based ODS alloys for Molten Salt Reactors | North Carolina State University | $800,000 | The objective of this work is to (i) propose and develop a new Nickel (Ni) based Oxide Dispersion-Strengthened (ODS) alloy that can be used for structural applications in Molten Salt Reactor (MSR) and other nuclear reactor harsh environments, (ii) to demonstrate that its high temperature mechanical properties are adequate for MSR operating temperatures, (iii) to demonstrate its radiation damage resistance through ion irradiation testing and (iv) to demonstrate its improved corrosion resistance in MSR environment. | RCRD&D | FY2019 | |
| NEUP Project 19-17037: Investigation of HTGR Reactor Building Response to a Break in Primary Coolant Boundary | Purdue University | $799,832 | Researchers will perform a series of experiments to simulate HTGR reactor building response due to a break in the primary coolant boundary in a well-scaled test facility to obtain spatial distribution of oxygen concentration, perform analysis of the whole system response with 1-D thermal hydraulics codes and use CFD to make detailed localized predictions. The tests will be carried out with different locations and sizes of the breaks to create various vent and flow paths in the reactor cavity. | RCRD&D | FY2019 | |
| NEUP Project 19-17093: Integrating Multi-modal Microscopy Techniques and the MOSAIC Simulation Environment to Assess Changes in the Physical Properties and Chemical Durability of Concrete Following Radiation Exposure | University of California, Los Angeles | $800,000 | Researchers will develop unprecedented multi-modal imaging methodologies that integrate multiple microscopy techniques. The team will develop a generalizable protocol for quantifying the changes in physical properties and chemical durability of concrete and concrete constituents (minerals and aggregates) following radiation exposure. The imaging analyses will be input into the MOSAIC framework to reveal the nature and extent of degradation that is expected to result. The outcomes offer insights that are needed to enable and inform second license renewals. | RCRD&D | FY2019 | |
| NEUP Project 19-17167: Atomistically Informed and Experimentally Validated Model for Helium Bubble Growth in Welded Irradiated Metals | University of Florida | $797,861 | Researchers will construct a validated computational model for He bubble growth on grain boundaries in irradiated Fe-Ni-Cr microstructures, including intergranular fracture, as a function of material conditions and welding heat input. This model will be based on the phase-field methodology, leveraging numerical solvers in the MOOSE simulation platform, with critical inputs and validation provided by both atomic-level simulations and experiments. | RCRD&D | FY2019 | |
| NEUP Project 19-16909: Learning-based Computational Study of the Thermodynamic, Structural, and Dynamic Properties of Molten Salts at the Atomic and Electronic Scale and Experimental Validations | University of Illinois at Urbana-Champaign | $800,000 | Researchers will obtain the thermophysical, thermochemical, and transport properties, construct the phase diagrams, and build empirical physical models of molten salts that are relevant to Molten Salt Reactors (MSRs) with first-principles accuracy using molecular dynamics simulations driven by machine-learned high-dimensional neural network potentials combined with neutron/X-ray scattering and thermodynamic experimental validations. | RCRD&D | FY2019 | |
| NEUP Project 19-16298: I-PRA Decision-Making Algorithm and Computational Platform to Develop Safe and Cost-Effective Strategies for the Deployment of New Technologies | University of Illinois at Urbana-Champaign | $800,000 | Researchers will develop an integrated probabilistic risk assessment decision-making algorithm to support risk-and-cost-informed decision-making related to the deployment of new technologies. The project will enhance the financial analysis module and the challenging interface of social and technical systems to advance the algorithm. The project will conduct a case study for evaluating the safety impact and cost-effectiveness of FLEX strategies to support operational flexibility. | RCRD&D | FY2019 | |
| NEUP Project 19-16802: Evaluation of Semi-Autonomous Passive Control Systems for HTGR Type Special Purpose Reactors | University of Michigan | $400,000 | Researchers will investigate the use of variable flow controllers and a variable reflector as passive or semi-autonomous reactivity control mechanisms for multi-module HTGR type special purpose reactors. This applies to the commercially developed special purpose reactor concepts from HolosGen. The incorporation of these systems will reduce the movable parts count and enable more robust load follow capabilities over broader power ranges and local and global reactivity control. | RCRD&D | FY2019 | |
| NEUP Project 19-17467: Understanding the Speciation and Molecular Structure of Molten Salts Using Laboratory and Synchrotron based In Situ Experimental Techniques and Predictive Modeling | University of Nevada, Reno | $800,000 | Researchers will develop a methodology to accurately determine the structure and speciation of the molten salt electrolyte using laboratory-based spectroscopic techniques (Raman and UV-Vis-NIR) and synchrotron-based (scattering and absorption) techniques, in combination with computational modeling. | RCRD&D | FY2019 | |
| NEUP Project 19-17231: Prevention of Common Fault-Trigger Combinations for Qualification of Digital Instrumentation and Control Technology | University of Tennessee at Knoxville | $800,000 | Researchers will provide an effective design evaluation approach based on prevention of concurrent triggering conditions to eliminate common-cause failures (CCF) and enable qualification of digital I&C technology for application in nuclear plant modernization. The research involves classifying commonality among digital devices, categorizing faults and triggering conditions, determining fault-trigger relationships, and defining preventive design measures to resolve the potential for CCF. | RCRD&D | FY2019 | |
| NEUP Project 19-17087: Economic Risk-Informed Maintenance Planning and Asset Management | University of Tennessee at Knoxville | $800,000 | Researchers will provide a holistic framework for cost-minimizing risk-informed maintenance planning, including inspection. They will develop a two-tier framework that coarsely minimizes the total maintenance cost during the remaining normal operating cycle and uses the outputs of the first model to maximize the financial impact of these activities in the short term. | RCRD&D | FY2019 | |
| NEUP Project 19-16811: Liquid Metal-cooled Fast Reactor Instrumentation Technology Development | University of Wisconsin-Madison | $800,000 | Researchers will explore three different areas that will help to improve commercialization of SFRs and to aid in testing for the VTR. These include: 1. Advancement in understanding of low prandtl number heat transfer 2. Testing of compact heat exchangers for use with sodium 3. Development of in pool submersible flow meters. | RCRD&D | FY2019 | |
| NEUP Project 19-16954: Innovative In-Situ Analysis and Quantification of Corrosion and Erosion of 316 Stainless Steel in Molten Chloride Salt Flow Loops | University of Wisconsin-Madison | $800,000 | Researchers will use a thin-layer activation technique for the first time in molten salts, on 316H samples placed in natural convection and forced flow loops. The individual and synergistic effects of corrosion, irradiation and thermo-mechanical treatments will be evaluated in-situ to predict component service lifetimes and design limits. The effects of molten chloride flow velocity will also be assessed. | RCRD&D | FY2019 | |
| NEUP Project 19-17168: Fuel Salt Sampling and Enriching System Technology Development | Vanderbilt University | $799,989 | Researchers will combine insights from the Molten Salt Reactor Experiment with decades of advancements in applicable technologies into an enhanced Sampler Enricher (SE) concept to develop and test a flexible, reliable, and workable design. The prototype will then be tested in an existing salt loop. | RCRD&D | FY2019 | |
| NEUP Project 18-15345: Multiphysics Degradation Processes, and Their Mitigation, in Engineered and Geological Bariers: Experiments and Simulation | Duke University | $800,000.00 | This project will focus on filling the gaps in understanding of mechanisms of a series of degradation processes (thermal, hydric, geo-chemical, and transport processes phenomena) potentially affecting geo-materials used in repositories. The objectives of the work are to better recognize the conditions leading to preferential paths of radionuclide transport and rock weakening, and to build mathematical models and implement them into existing codes to predict material degradation and develop strategies to reduce the adverse consequences. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15043: Integration of Nuclear Material Accounting Data and Process Monitoring Data for Improvement on Detection Probability in Safeguarding Electrochemical Processing Facilities | Oregon State University | $800,000.00 | The goal of this project is to further studies on fusion of process monitoring (PM) data and nuclear material accounting (NMA) data. PM data, which includes monitoring by various types of equipment (radiation detectors, cameras, voltage, current sensors), can supplement NMA data to help improve safeguards. For aqueous-based reprocessing facilities, it is reported that PM, integrated with traditional NMA, has a high-detection probability for specific diversions. For electrochemical reprocessing, preliminary studies have shown that PM data can support traditional NMA by providing a basis to estimate some of the in-processing nuclear material inventories. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15148: Recovery of Rare-Earth Elements (Nd, Gd, Sm) in Oxide Wasteform Using Liquid Metals (Bi, Sn) | Pennsylvania State University | $800,000.00 | This project investigates a new approach for recovering rare-earth (RE) fission products (Nd, Gd, and Sm) from molten chlorine salts using liquid metal (Bi and Sn) electrodes. The research aids molten salt recycling by converting the RE products into chloride-free RE oxides, which could be incorporated into conventional glass/ceramic waste forms. Successful outcomes of the project include advanced separation of fission products from molten salts with better control of chemical selectivity and high-recovery yield. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15103: Microstructure-Based Benchmarking for Nano/Microscale Tension and Ductility Testing of Irradiated Steels | Purdue University | $800,000.00 | The objective of this project is to standardize methods for nano/micro-scale tensile and ductility testing of irradiated Fe-Cr steels, through microstructure-based benchmarking. The study will investigate key process parameters for TEM in situ tension and ductility testing. Coupling experimental studies with multiscale models, the research will identify the approaches that provide consistent deformation mechanisms between the nano/micro-scale and macro-scale tests, from which standard practices will be obtained. The primary project outcome will be a set of recommended guidelines for nano/microscale mechanical testing, which will lead to unprecedented reductions in the time and cost for qualifying materials for in-reactor service and to ensure consistency of methods and validity of results. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15559: Cold Spray Repair & Mitigation of Stress Corrosion Cracks in Spent Nuclear Fuel Dry Storage Canisters | Purdue University | $799,982.00 | This goal of this project is to demonstrate cold spray repair and mitigation of chloride-induced stress corrosion cracks (SCC) and pits in stainless steel dry storage canisters. The research will optimize the repair process and gain a scientifically informed understanding of SCC mechanisms. The outcome is to further develop cold spray as an attractive solution for the repair of existing SCC and mitigation of potential SCC necessary to ensure long-term integrity, security, and regulatory compliance of spent nuclear fuel storage. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15596: Capture of Organic Iodides from Vessel Off-Gas Streams | Syracuse University | $799,548.00 | This project will study the capture of radioactive organoiodides from off-gas streams produced during nuclear fuel reprocessing by conducting adsorption experiments using a selected silver adsorbents. Multifaceted simulation adsorption models will be developed to assist in the design of necessary capture systems for off-gas streams. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15585: Impact of Coupled Gas Migration and Thermo-hydro-mechanical Processes on the Performance of Repositories for High Level Nuclear Waste | Texas A&M University | $608,375.00 | The main goal of this project is to better understand the possible effect of gas migration (particularly through discontinuities) on the performance and long-term behavior of engineered barrier systems (EBS) envisaged for the isolation of high-level radioactive waste (HLW). Specific outcomes of this study will be an improved understanding of the role of gas migration and discontinuities in the performance of HLW disposals, with the underlying aim to improve design of EBS used for HLW. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15531: Repair and Mitigation of Chloride-Induced Pitting and Chloride-Induced Stress Corrosion Cracking in Used Nuclear Fuel Dry Cask Canister Materials | The Ohio State University | $800,000.00 | This project will evaluate and develop a set of tools to repair and mitigate chloride-induced pitting and stress corrosion cracking in stainless steel nuclear fuel canisters. Advanced processes, including low temperature friction stir welding and cold spray deposition, will be evaluated according to various criteria, such as corrosion performance. In addition, technologies that have not yet been evaluated for UNF applications, including vaporizing foil actuator welding and soldering will be assessed. The two most promising technologies will selected for further development and comprehensive study. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-14912: Bridging the Length Scales on Mechanical Property Evaluation | University of California, Berkeley | $800,000.00 | This project combines experimental and modeling methods to gain a comprehensive approach for addressing scaling effects on small-scale mechanical testing. Multiscale experiments, together with modeling on reactor-relevant and model alloys, will provide better understanding of appropriate scaling relationships. The study aims to gain fundamental understanding of plasticity interactions with specific strength-determining features, such as precipitates and grain boundaries. The goal of this work is to provide the basis to add small-scale mechanical testing in the toolbox for nuclear materials research. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-14911: Understanding of degradation of SiC/SiC materials in nuclear systems and development of mitigation strategies | University of California, Berkeley | $800,000.00 | This project investigates the best possible coatings to prevent SiCf/SiCm corrosion in LWR environments. The research features a computational and experimental rapid screening approach for numerous coating compositions. The work includes autoclave exposure of rapid screening coupons in prototypical environments in combination with thermodynamic modeling (CALPHAD) and Finite Element Methods (FEM). Small-scale mechanical testing, together with thermal cycling and FEM modeling, will provide guidance on the ideal coating system design. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15701: Time-dependent THMC Properties and Microstructural Evolution of Damage Rocks in Excavation Damage Zone | University of Colorado, Boulder | $799,978.00 | The proposed project focuses on the geomechanical aspects of modeling by addressing the time-dependent evolution of rock microstructure and its coupling with the THC processes that are of first-order importance to the stability and the isolation performance of repositories. The research will delineate an integrated experimental, theoretical and numerical strategy in assessing the evolution EDZ over time and its implication on the long-term migration of hazardous species. These results will enhance the confidence of the predicted long-term performance of repositories, which helps to move forward the goal of one-million-year isolation of high-level nuclear wastes. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15381: Multiaxial Failure Envelopes and Uncertainty Quantification of Nuclear-Grade SiCf/SiC Woven Ceramic Matrix Tubular Composites | University of Florida | $800,000.00 | This project proposes to develop a comprehensive experimental and computational approach for determining constitutive relations and multiaxial failure envelopes of nuclear-grade continuous silicon fiber (SiCf) and SiC matrix woven tubular composites. The result of this work can be adopted in industry for design refinement, optimization of performance under the desired operating conditions, and reliable prediction of failure under unforeseen accidental scenarios. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15496: Formation of Zeolites Responsible for Waste Glass Rate Acceleration: An Experimental and Computational Study for Understanding Thermodynamic and Kinetic Processes | University of Houston | $800,000.00 | Through experimental and computational studies, this project will expose the factors governing zeolite crystallization and their role in Stage III dissolution of radionuclide-containing glass waste forms generated in advanced nuclear fuel cycles. The overall goal of this project is to understand the formation of zeolite phases in order to develop process control methods to suppress Stage III dissolution. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-14998: Novel Processes for Capture of Radioactive Iodine Species from Vessel Off-Gas Streams | University of Idaho | $800,000.00 | The goal of this project is to develop a comprehensive understanding of the sorption system performance and effectiveness for capture of radioiodine species present in the off-gas streams from the used nuclear fuel (UNF) recycling operations, focusing particularly on the organic iodine species. The dynamic sorption experimentation and theoretical modeling will offer fundamental insights on the mechanism enabling the design and prediction the control system performance. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15261: Friction Stir Based Repair Welding of Dry Storage Canisters and Mitigation Strategies: Effect of Engineered Barrier Layer on Environmental Degradation | University of Idaho | $800,000.00 | The project goal is to apply friction stir based repair and mitigation technique for eliminating failure associated with pitting and stress corrosion cracking in dry storage canisters for spent fuels. The goal of these activities is to obtain a fundamental understanding of the processing-structure-properties correlations. This work will contribute to the development of a crack repair/mitigation strategy based on friction stir technology that can be efficiently implemented for spent fuel dry storage casks, which will enhance safety and reliability of these systems. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15263: X-ray Studies of Interfacial Molecular Complexes in ALSEP Back-Extraction | University of Illinois at Chicago | $800,000.00 | This project will use synchrotron X-rays to characterize the interfacial molecular complexes (of extractants and radiologically derived impurities, complexants, buffers, and metal ions) formed during the Actinide-Lanthanide Separation Process (ALSEP) back-extraction. This work addresses the critical knowledge gap of slow stripping kinetics in ALSEP, as well as the influence of radiolytic degradation products. The outcome of the project will be a molecular-level understanding of the role of different components in the interfacial mechanism of back-extraction in the ALSEP process, therefore leading to development of more efficient and faster metal stripping relevant to the separation of actinides from lanthanides in the nuclear fuel cycle. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15030: Mechanistic Understanding of Radiolytically Assisted Hydrothermal Corrosion of SiC in LWR Coolant Environments | University of Michigan | $800,000.00 | The objective of this project is to develop a mechanistic understanding of the hydrothermal corrosion behavior of monolithic SiC and SiC/SiC composites in LWR environment under the influence of water radiolysis products and radiation damage. Complementary atomistic simulations will be carried out to determine the rate controlling mechanisms for dissolution under different water chemistries and in the presence of radiation. Activation energies and kinetic rates will be calculated directly from these simulations and compared to experimentally fitted values. The dissolution rate constants determined and validated in this integrated experimental and modeling approach will allow predictions of long-term SiC corrosion behavior. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-14999: Probabilistic Failure Criterion of SiC/SiC Composites Under Multi-Axial Loading | University of Minnesota, Twin Cities | $800,000.00 | This project aims to develop a probabilistic failure criterion of SiC/SiC composites under multi-axial loading and to incorporate the criterion into a reliability analysis of the structural integrity of LWR SiC/SiC fuel cladding. This research will be anchored by a seamless integration of novel experimental and analytical tools, which will lead to a robust methodology for dependable analysis of SiC/SiC composite structures for LWR fuel cladding, as well as other nuclear applications. The resulting model will be experimentally validated and applied to analyze the reliability of LWR SiC/SiC fuel cladding. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15502: Reducing Uncertainty in Radionuclide Transport Prediction Using Multiple Environmental Tracers | University of Montana | $724,906.00 | In this project, direct modeling of multiple environmental tracers will be used to improve predictions of radionuclide transport in a shallow alluvial aquifer discharge. The research will take advantage of recent theoretical developments considering the use of environmental tracers, and advances in high-performance reactive flow and transport models, to obtain the maximum information on the transport system. The goal is to develop a new methodology to characterize natural reactive flow and transport systems, reduce predictive uncertainty in radionuclide transport simulations, determine the maximum information content of the tracer suite, and optimize future groundwater characterization efforts. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15578: Computational and Experimental Investigation of Thermal-Mechanical-Chemical Mechanisms of High-burnup Spent Nuclear Fuel (SNF) Processes at Elevated Temperatures and Degradation Behavior in Geologic Repositories | University of Nevada, Las Vegas | $800,000.00 | The overarching goal of this project is to use combined computational and experimental research and development activities to enhance understanding of the mechanisms and thermal-mechanical-chemical (TMC) parameters controlling the instant release fraction (IRF) and matrix dissolution of high-burnup (HB; burnup > 45 GWd/MTU) spent nuclear fuels (SNFs) and the subsequent formation, stability, and phase transformations of HB SNF alteration products under long-term storage and geological disposal conditions (e.g., high-temperature storage,-radiolysis). The results of this research will be used to enhance the mechanistic detail of process models to reduce uncertainty in, and improve the technical bases of, safety cases and performance assessment analyses. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15439: Radiolytic Dissolution Rate of Silicon Carbide | University of Notre Dame | $400,000.00 | This project seeks to develop a matrix of dissolution rates for high-purity SiC material, using intense electron beam irradiation, and to measure the products of dissolution (silicic acid and CO2 (or CO)) in the water downstream of the irradiation zone. The objective is to determine the rate of SiC dissolution and gather sufficient insight about its mechanism in LWRs, so that the use of SiC/SiC composite materials for accident tolerant fuel cladding can proceed with confidence. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15061: Development of an MC&A Toolbox for Liquid-fueled Molten Salt Reactors with Online Reprocessing | University of Tennessee at Knoxville | $799,207.00 | The purpose of this project is to develop a toolbox of swappable mass flow modules for liquid-fueled molten salt reactor (MSR) systems for the purposes of evaluating material control & accountancy measurement techniques. When combined together, these modules enable modeling of the time-dependent mass flows for a variety of MSR variants. The test platform will consist of a toolbox of independent process modules representing discrete physical units, each with its own self-contained physics responsive to the input mass flow, along with appropriate measurement models that can be coupled to key flow points. These dynamic physical signatures would allow testing of the viability and efficacy of potential accountancy techniques under the full range of reactor operating conditions. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15307: A Novel and Flexible Approach for Converting LWR UNF Fuel Into Forms That Can Be Used to Fuel a Variety of Gen-IV Reactors | University of Tennessee at Knoxville | $400,000.00 | This project will investigate the chemical decladding and the digestion of whole MOX-based fuel rods, using thionyl chloride and surrogate materials. Digesting entire LWR fuel assemblies results in product streams that include pure decontaminated ZrCl4; pure UCl4; and a stream containing TRU/FPs, as well as alloying metals (as chloride salts). The objectives of this project are to provide a new, highly efficient protocol for the transformation of used nuclear fuel into useful components and to effectively contain a concentrated stream of highly radioactive materials for appropriate handling. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15459: Reduced Diffusion and Enhanced Retention of Multiple Radionuclides from Pore Structure Studies of Barrier Materials for Enhanced Repository Performance | University of Texas at Arlington | $567,831.00 | The project seeks to better understand and quantify the pore structure (geometry and topology) and pore connectivity of porous media and its emergent effect on diffusion and retention of various radionuclides in barrier materials. The anticipated outcome of the project will be to more accurately evaluate the performance of geological repositories. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15649: Benchmarking Microscale Ductility Measurements | University of Utah | $776,669.00 | The objectives of this project are to establish best practices for obtaining tensile microscale ductility measurements and to validate methodologies for comparing them to macroscale ductility measurements. Anticipated outcomes of the project are: 1) measurement of grain and sub-grain localization processes micro and macroscales; 2) establishment of best practices for microtensile experimentation; 3) identification of statistically significant relationships between specimen geometry, microstructure variables and mechanical behavior; 4) modified phenomenological elongation-based ductility models to enable direct upscaling of ductility measurements from microscale to macroscopic. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15003: Advanced Coating and Surface Modification Technologies for SiC-SiC Composite for Hydrothermal Corrosion Protection in LWR | University of Wisconsin-Madison | $799,990.00 | This project focuses on the development of coatings and surface modification approaches for hydrothermal corrosion protection of SiC-SiC composite in normal LWR operation environments. Innovative surface treatment recipes will be explored using processes including, interfacial stitching to improve adhesion, multi-layered structures to improve ductility, and compositions and structures resulting from thermal treatments. The surface treatment concepts involve corrosion resistant metallic and ceramic materials, and are amenable to industrial scalability for the cladding application. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15332: Low-Force Solid-State Technologies for Mitigation of Stress Corrosion Cracking in Dry Storage Canisters | University of Wisconsin-Madison | $800,000.00 | This project will focus on evaluating and developing two technologies used for field mitigation and repair of stress corrosion cracking (SCC): 1) additive friction stir welding; and 2) cold spray deposition. The work involves developing low-force, low-heat input solid state technologies to lessen and repair SCC in stainless steel canisters for used nuclear fuel (UNF). This outcome of the study will inform feasibility of using the two technologies to conduct on-site field repairs. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-14913: The Role of Temperature on Non-Darcian Flows in Engineered Clay Barriers | Virginia Polytechnic Institute and State University | $800,000.00 | This project intends to accomplish three tasks: 1) to develop a predictive model to facilitate experimental data interpretation and provide mechanistic insights into the role of temperature on non-Darcian flows in low-permeability engineered clay barriers; 2) conduct experiments to unravel the role of temperature on the threshold gradient of non-Darcian flow in both saturated and unsaturated bentonite; and 3) use molecular dynamics (MD) simulation to improve fundamental understanding. The experimental data, associated with the MD simulation, will provide valuable information to improve fundamental understanding and scientific knowledge with respect to the temperature dependence of threshold gradient in non-Darcian flows, because very limited experimental data for saturated flow and no experimental data for unsaturated flow are available. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-14815: C-SiOC-SiC Coated Particle Fuels for Advanced Nuclear Reactors | Virginia Polytechnic Institute and State University | $400,000.00 | This project will study a new concept for nuclear fuel encapsulation using an amorphous SiOC plus carbon system as the inner coating and nanocrystalline SiC plus minor carbon as the outer coating for nuclear fuel kernel particles. The outcomes of this work are: 1) new directions and possible replacement guidance for current nuclear fuel materials in operation; 2) new fuel materials for future nuclear reactor material design and development; 3) nuclear composite microstructure evolution and performance degradation understanding; 4) screening tools to guide future nuclear fuel material activities; and 5) mechanisms of nuclear fuel material evolution and degradation and effective strategies to mitigate/reduce undesirable fuel behaviors. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15226: An Evaluated, Transient Experiment based on Simultaneous, 3-D Neutron-Flux and Temperature Measurements | Kansas State University | $399,972.00 | This project will evaluate existing and near-term experimental data for inclusion in the International Reactor Physics Experiment Evaluation Project (IRPhEP) handbook. The data to be evaluated include compositions from a recent fuel replacement as part of an LEU conversion, a number of critical, fresh-fuel configurations, fuel temperature measurements at fresh-fuel configurations, and records from nearly a decade of operation. The proposed work would lead to a first-of-a-kind evaluation of transient, spatially-dependent reaction rates. | Nuclear Energy | FY2018 | |
| NEUP Project CFA-18-15773: Evaluation of the Thermal Scattering Law for Advanced Reactor Neutron Moderators and Reflectors | North Carolina State University | $398,821.00 | The objective of this project is to narrow the nuclear data gap for advanced nuclear reactors that are driven by thermal neutrons. This includes concepts such as gas-cooled high-temperature reactors and molten salt or salt-cooled high temperature reactors. The generated data TSL libraries will be provided in EDNF File 7 format to the National Nuclear Data Center (NDDC) to immediately include in beta releases of the ENDF/B libraries and to consider for the future release of ENDF/B-VIII.1. | Nuclear Energy | FY2018 | |
| NEUP Project 18-15602: Modeling and Experimental Verification of Thermal Energy Storage Systems to Enable Load Following Capability for Nuclear Reactors | University of Idaho | $761,640.00 | This project purposes to integrate new thermal energy storage (TES) models, developed in Modelica, with ongoing nuclear-renewable hybrid energy systems (NRHES) modeling efforts, in order to evaluate economic potential and advantages of new process designs over baseload electricity production. The computational phase of this project includes developing mathematical and physics-based TES models, which could later be translated to Modelica and integrated with existing NRHES components. The testing and optimization would be conducted using RAVEN. A techno-economic analysis will be performed to evaluate the compatibility of the newly formed integration, as well as to quantify its feasibility and economic benefits. The experimental aspect is focused on the development of scaled TES systems, which serve as verification for the Modelica models and allow system testing upon being integrated with DETAIL. | Nuclear Energy | FY2018 | |
| NEUP Project 18-14963: Development of Nuclear Hybrid Energy Systems: Temperature Amplification through Chemical Heat Pumps for Industrial Applications | University of Idaho | $800,000.00 | The overall goal of this project is to develop and demonstrate, through modeling and experimental investigations, temperature amplification capabilities of a chemical heat pump (CHP) system that can be coupled to a conventional light water reactor or a near-term small modular reactor. The outcomes would include nuclear hybrid energy system architecture containing a CHP, experimental data on the CHP performance, and dynamic model of the system, validated through experimentation, which could be used for scale-up and design. | Nuclear Energy | FY2018 | |
| NEUP Project 18-15008: Development of Thermal Inelastic Scattering Covariance Data Capabilities with Demonstration of Light Water Evaluation | University of Michigan | $400,000.00 | The goal of this project is to produce a format for covariance data for inelastic thermal neutron scattering data for moderators in the ENDF format. To demonstrate the viability of this new format, an evaluation of the covariance data for thermal scattering in light water in this format will be produced, along with the capabilities to generate the files and test their efficacy. A capability for calculating sensitivity coefficients using multigroup methods to the fundamental physics parameters governing light-water scattering will be developed to facilitate identifying nuclear data needs related to thermal scattering. | Nuclear Energy | FY2018 | |
| NEUP Project 18-15056: Model-Based Diagnostics and Mitigation of Cyber Threats | University of Michigan | $800,000.00 | This project intends to develop a toolkit for modeling digital instrumentation and control (I&C) systems for nuclear power plants so that the consequences of cyber-attacks on I&C systems may conveniently be modeled using nuclear plant simulation software. The results of the toolkit-based models, the corresponding responses, and the performance of the diagnostic schemes will be tested on a virtual control room driven by a plant simulator. | Nuclear Energy | FY2018 | |
| NEUP Project 18-15055: NICSim: Nuclear Instrumentation and Control Simulation for Evaluating Response to Cyber-attacks | University of New Mexico | $799,945.00 | The objective of the project is to develop a Nuclear Instrumentation and Control Simulation (NICSim) platform with a novel emulytics capability to simulate control systems and components in nuclear power plants. The outcome of this work would be a first-in-class emulytics platform with an associated documentation and library of physical models of components that could be used by analysts and designers to assess the resilience and cybersecurity risks of different control system designs for a wide range of power plants. | Nuclear Energy | FY2018 | |
| NEUP Project 18-15324: Validation of Pressure Relaxation Coefficient in RELAP-7 Seven-Equation Model | George Washington University | $800,000.00 | This project aims to validate the Seven-Equation model in RELAP-7 by: 1) measuring velocity and pressure in each phase and the interface as well as return to equilibrium in fast transients with high-speed non-intrusive laser diagnostics in canonical experiments; 2) complementing experimental data with a multiscale computational approach, including a 3D proprietary direct numerical solver; and 3) validating RELAP-7 with a combination of experimental data and first-principle simulations. This combination would provide unique and complete datasets to validate RELAP-7 with high confidence and offer a new class of experimental and numerical tools. | NEAMS | FY2018 | |
| NEUP Project CFA-18-15104: Demonstration of Utilization of High-fidelity NEAMS Tools to Inform the Improved Use of Conventional Tools within the NEAMS Workbench on the NEA/OECD C5G7-TD Benchmark | North Carolina State University | $800,000.00 | The goal of this project is to demonstrate the utilization of high-fidelity Nuclear Energy Advanced Modeling and Simulation (NEAMS) tools (PROTEUS, Nek5000, and BISON) to inform the improved use of conventional tools (DIF-3D, CTF, and CTFFuel) within the NEAMS Workbench on the NEA/OECD C5G7-TD benchmark. This would result in more accurate predictions of safety parameters and margins, which is important for both safety and performance improvements of the nuclear power plants being currently operated and built. The developed Workbench-based framework will also assist end users to apply high-fidelity simulations to inform lower-order models for the design, analysis, and licensing of advanced nuclear systems. | NEAMS | FY2018 | |
| NEUP Project 18-14741: Demonstration of a Methodology for Direct Validation of MARMOT Irradiation-Induced Microstructural Evolution and Physical Property Models Using U-10Zr | Texas A&M University | $500,000.00 | The objective of this project is to demonstrate, for the first time, a methodology that enables the direct validation of microstructural evolution models for fuel in MARMOT, and the direct correlation of changes in physical properties with specific irradiation-induced microstructural features. Properly implementing this methodology will result in rapid development of MARMOT mesoscale models. | NEAMS | FY2018 | |
| NEUP Project 18-15520: Accurate and Efficient Parametric Model-Order Reduction for Turbulent Thermal Transport | University of Illinois at Urbana-Champaign | $800,000.00 | The project objective is to develop reduced-order models (ROMs) that will improve accuracy of LMR system-level analysis with low overhead. These new models will systematically mine high-fidelity DNS, LES, or uRANS simulations to construct low-order dynamical systems that can couple with a systems analysis code, such as the SAM code being developed under NEAMS. These simulations provide useful data and will be made available to the scientific community, and the overall effort will contribute to more efficient LMR conceptual design studies and licensing. | NEAMS | FY2018 | |
| NEUP Project 18-15484: A Novel High Fidelity Continuous-energy tTansport Tool for Efficient FHR Transient Calculations | Georgia Institute of Technology | $800,000.00 | The objective of the project is to develop a high-fidelity continuous energy (CE) transport tool for efficient transient calculations in fluoride salt-cooled high-temperature reactors with prismatic core/fuel assembly design. This will be accomplished by extending the high-fidelity 3-D continuous energy coarse mesh radiation transport (COMET) code with formidable computational speed to solve transient problems in FHRs with accurate thermal hydraulic feedback. The new capability would enable plant system codes to perform analyses necessary to address complex technical design, regulatory, reactor safety, and economic hurdles prior to construction. | RCRD&D | FY2018 | |
| NEUP Project 18-15093: Determination of Molecular Structure and Dynamics of Molten Salts by Advanced Neutron and X-ray Scattering Measurements and Computer Modeling | Massachusetts Institute of Technology | $800,000.00 | This project will seek detailed knowledge about molecular structure and dynamics of molten salts to inform the design of new molten-salt reactors. A combination of advanced neutron and x-ray scattering and ab initio molecular dynamics simulations will be used to model the ionic-cluster structure of the fluid and solubility of impurities. Machine learning will be applied to regress from simulations and experiments in order to develop the model and predict chemical potentials as a function of composition and temperature. | RCRD&D | FY2018 | |
| NEUP Project 18-15171: Oxidation Behavior of Silicon Carbide and Graphitic Materials | Missouri University of Science and Technology | $800,000.00 | The objectives of this project are to determine the oxidation behavior of silicon carbide and graphitic materials in oxygen and/or moisture, to accurately measure the kinetic parameters of oxidation, to ascertain the oxidation mechanisms in relation to the microstructures, to determine the effect of irradiation on oxidation behavior, and to provide data and input to the safety analysis of high-temperature gas reactors under air and moisture ingress accident conditions. | RCRD&D | FY2018 | |
| NEUP Project 18-15276: Coping Time and Cost Analysis of Accident Tolerant Plant Design based on Dynamic PRA Methodology | Rensselaer Polytechnic Institute | $800,000.00 | This project will evaluate the failure modes of accident tolerant fuel ATF candidates to understand the different failure characteristics. The research aims to obtain a response surface of coping time by investigating the various uncertainties of accident mitigation in PWR and BWR reactors. These outputs will aid the decision making process on the implementation of ATF and FLEX to existing LWR plants from the perspective of risk reduction and economic feasibility. | RCRD&D | FY2018 | |
| NEUP Project 18-15270: Innovative Use of Accident Tolerant Fuels (ATF) with the RCIC System to Enhance Passive Safety of Commercial LWRs | Texas A&M University | $748,000.00 | The overarching objectives of this project are to: 1) demonstrate new operational strategies with the combined use of Accident Tolerant Fuels (ATF) and the Reactor Core Isolation Cooling (RCIC) System to increase the passive safety capabilities of current Boiling Water Reactors (BWRs) in delaying or preventing core damage; and 2) pursue the delay of containment venting until after a 72-hour coping period through new BWR Suppression Pool mixing procedures. The research will use both simulation and experimental data to validate the objectives. The work has the potential to increase the ability of existing nuclear power plants to passively respond to beyond design basis events using existing equipment and without changes to the plants. | RCRD&D | FY2018 | |
| NEUP Project 18-15346: Big Data For Operation and Maintenance Cost Reduction | The Ohio State University | $800,000.00 | This project will develop a first-of-a-kind framework for integrating Big Data capability into the daily activities of our current fleet of nuclear power plants. This research will mainly focus on incorporating the wide range of data heterogeneities in nuclear power plants into an integrated Big Data Analytics capability. The primary end product of this work will be a Big Data framework that is capable of dealing with the large volume and heterogeneity of the data found in nuclear power plants to extract timely and valuable information on equipment performance and to enable optimization of plant operation and maintenance based on the extracted information. | RCRD&D | FY2018 | |
| NEUP Project 18-15065: in situ Measurement and Validation of Uranium Molten Salt Properties at Operationally Relevant Temperatures | University of Connecticut | $799,979.00 | This project proposes to use advanced spectroscopic and scattering methods to provide information at the atomic and molecular scale. The research will use synchrotron-based x-ray absorption fine structure (XAFS) spectroscopy and Raman spectroscopy, at operationally relevant temperatures, to measure the local and intermediate structure as well as speciation of chloride fuel salts (NaCl, ZrCl, UCl3) for fast-spectrum applications and fluoride fuel salts ( 7 LiF, UF4) primarily for thermal spectrum applications This approach is expected to generate theories and concepts that would allow models to predict behavior, and develop the means for in situ monitoring. | RCRD&D | FY2018 | |
| NEUP Project 18-15058: High-resolution Experiments for Extended LOFC and Steam Ingress Accidents in HTGRs | University of Michigan | $800,000.00 | The objective of this project is to better understand key phenomena in high-temperature gas-cooled reactors relevant to steam ingress and loss of forced circulation (LOFC) accidents. Specifically, the research will: 1) experimentally investigate, using an existing integral-effect test facility with some improvements, the steam-ingress accident caused by a postulated steam generator tube rupture initiating event; 2) carry out integral-effect tests for the extended LOFC accident to study the establishment of global natural circulation flow in the primary loop; 3) design, based on a scaling analysis, and construct a separate-effect test facility to study the complex helium flows in the core and hot plenum during the extended LOFC accident; and 4) perform detailed, high-resolution, separate-effects experiments using the results obtained as boundary/initial conditions. | RCRD&D | FY2018 | |
| NEUP Project 18-15471: Integral Experimental Investigation of Radioisotope Retention in Flowing Lead for the Mechanistic Source Term Evaluation of Lead Cooled Fast Reactor | University of New Mexico | $800,000.00 | The purpose of this project is to experimentally investigate the integral effects of radioisotope interactions with liquid lead to support the following technical goals: 1) evaluating the mechanistic source term of the Lead-cooled Fast Reactor (LFR); 2) developing a universal integral effect test methodology for liquid metal source term evaluations; and 3) establishing a basis for the comparison of radioisotope retention between lead and sodium. This aim of the research is to advance the LFR licensing pathway by establishing the phenomenological foundation of the interaction between fission products and liquid lead. | RCRD&D | FY2018 | |
| NEUP Project 18-15153: Understanding Molten Salt Chemistry Relevant to Advanced Molten Salt Reactors through Complementary Synthesis, Spectroscopy, and Modeling | University of Tennessee at Knoxville | $800,000.00 | The goal of the proposed research is to understand molten salt chemistry relevant to advanced molten salt reactors through complementary synthesis, spectroscopy, and modeling. Through complementary synthetic, spectroscopic, and computational efforts, the aim is to achieve atomistic and molecular-level understanding of liquid structure, coordination geometry, chemical bonding, and reactivity of novel molten salt melts relevant to advanced molten reactor designs. | RCRD&D | FY2018 | |
| NEUP Project 18-15111: Improving Nuclear Power Plant Efficiency Through Data Analytics | University of Tennessee at Knoxville | $799,727.00 | This project aims to develop and provide data analytics solutions to improve nuclear power plan economic efficiency by utilizing empirical models to integrate disparate data sources while providing uncertainty estimates to quantify risk and support decisions. The outcomes will enhance the technical and economic competitiveness by enabling advanced monitoring of critical assets, improving the operating capability of the existing fleet, and helping achieve enhancements in organizational effectiveness. Additionally, the research would provide an agile and modular data analytic framework that would have high commercialization value and supports the industry-wide drive towards digital innovation. | RCRD&D | FY2018 | |
| NEUP Project 18-14846: Development of Corrosion Resistant Coatings and Liners for Structural Materials for Liquid Fueled Molten Salts Reactors | University of Wisconsin-Madison | $800,000.00 | The goal of the proposed research is to develop corrosion-resistant coatings and liners for structural materials for use in fuel dissolved molten salt environment for future Molten Salt Reactors (MSRs). Innovative, but industrially scalable, surface cladding approaches are proposed to lead to promising surface and interfacial compositions. The processes themselves are commercial, and have high technology readiness levels, and consequently would facilitate the accelerated developments of MSRs. | RCRD&D | FY2018 | |
| NEUP Project 18-15280: Advanced Alloy Innovations for Structural Components of Molten Salt Reactors | University of Wisconsin-Madison | $796,792.00 | The goal of the proposed research is to develop and evaluate specific advanced metallic alloys for structural components in fluoride salt-cooled molten salt reactors (MSRs). The research will investigate four categories of metallic alloys: advanced Ni-based; radiation damage tolerant high entropy; refractory Mo-based, and compositionally-graded, designed for high-surface corrosion resistance and good bulk strength. Additionally, the propensity for radiation embrittlement, as well as weldability, of the alloys will be evaluated. | RCRD&D | FY2018 | |
| NEUP Project 18-14957: Big Data Analytics Solutions to Improve Nuclear Power Plant Efficiency: Online Monitoring, Visualization, Prognosis, and Maintenance Decision Making | University of Wisconsin-Madison | $797,820.00 | The overarching goal of this project is to significantly advance the ability to assess equipment condition and predict the remaining useful life to support optimal maintenance decision making in nuclear power plants. This research will work toward accomplishing and establishing a modern set of data-driven modeling, online monitoring, visualization, prognosis, and operation decision-making methodologies to address the significant opportunities and challenges arising from the emerging data-rich environment in nuclear plants. The potential impact of the work is significant and transformative and could deliver important advances in productivity with reduced unscheduled downtime and improved equipment performance. | RCRD&D | FY2018 | |
| NEUP Project 18-15097: Oxidation Study of High Temperature Gas-Cooled Reactor TRISO Fuels at Accidental Conditions | Virginia Polytechnic Institute and State University | $800,000.00 | This project is to study the oxidation behaviors of TRISO fuels during accidental air and water vapor ingress conditions. The work focuses on the oxidation and burn-off of the graphite fuel matrix and oxidation of the TRISO fuel SiC layer at high-temperature accidental states in the presence of air and/or water vapor. It will include both unirradiated and irradiated graphite fuel matrix and simulated fuel particles with the SiC layer. | RCRD&D | FY2018 |
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 | |
|---|---|---|---|---|---|---|
| Understanding PM-HIP Interparticle Evolution and its Influence on Fracture Toughness in Alumina-Forming Steels | Purdue University | $1,100,000 | This project aims to understand how interparticle evolution during hot isostatic pressing (HIP) influences fracture toughness of Al-bearing steels. The team will use a series of interrupted HIP experiments with phase field models to understand the formation mechanisms of interparticle defects during HIP of alumina-forming austenitic (AFA) stainless steels and FeCrAl steels, and the influence of these defects on fracture behavior. | Document | Advanced Manufacturing Technologies | FY2024 |
| Multiscale high-throughput experiment/modeling approach to understanding creep behavior in Additively Manufactured reactor steels | University of Minnesota, Twin Cities | $1,043,271 | This project proposes to develop a predictive capability for processing-microstructure-property correlations in additive manufactured microstructures utilizing a multiscale approach encompassing bulk creep tests, miniaturized tensile testing, and a high-throughput, indentation based, cost-effective method for elevated temperature mechanical mapping of additively manufactured 316H Stainless Steel, Grade 91, and Titanium-Zirconium-Molybdenum (TZM) alloys. | Document | Advanced Manufacturing Technologies | FY2024 |
| Hi-fidelity characterization of molten salt-graphite pore interactions through experiments and embedded modeling | North Carolina State University | $1,100,000 | We propose a suite of fuel salt (FLiBe + U) infiltration experiments (University of Michigan-UM) followed by X-ray computed tomography, XCT (NCSU), in-situ mechanical property evaluation with scanning electron microscopy (NCSU) and high fidelity data analytics and modeling (NCSU/Leeds) along with complimentary porosimetry measurements (ORNL) and XPS analysis at University of Manchester (UoM). Three graphite grades are selected in this project: NBG-18, IG-110 and POCO: ZXF-5Q. | Document | Advanced Nuclear Materials | FY2024 |
| Assessing molten salt corrosion resistance of stainless steel 316H in nuclear reactor environments | North Carolina State University | $1,100,000 | The proposed goal is to leverage a blend of innovative molten salt corrosion experiments and cutting-edge characterization techniques to advance our understanding of molten salt corrosion in both commercial and additively manufactured (AM) stainless steel (SS) 316H, particularly under radiation or stress environments. | Document | Advanced Nuclear Materials | FY2024 |
| Polymer-Derived C-SiC Coatings on Kernel Particles for Advanced Nuclear Reactors | University of Alabama at Birmingham | $1,100,000 | This program is to use a polymer-derived ceramic approach to develop C-SiC/ZrC coatings on ZrO2 kernel substitute particles. We aim to create new fuel encapsulation materials in replacement of the coatings on fuel kernel particles, including the TRISO layers, for advanced reactors, conduct ion irradiation testing of the new materials for nuclear performance evaluation, and carry out detailed microstructure and composition characterization to assess the C-SiC/ZrC coated fuel particle behaviors. | Document | Advanced Nuclear Materials | FY2024 |
| Sorbent regeneration, recycling, and transformation: A transformative approach to iodine capture and immobilization | University of Nevada, Reno | $1,000,000 | The project will focus on the development of materials and processes for regeneration and recycling of sorbents, and the transformation of iodine-loaded sorbents into waste forms. A combination of computational and experimental studies will be conducted to understand (a) how the components in a primary off-gas stream interact with the sorbent, (b) how this off-gas stream affects the regeneration lifetime, and (c) low-temperature binders and processing paths that leads to durable waste forms. | Document | Advanced Nuclear Materials | FY2024 |
| Developing place-based understandings of respectful community engagement for consent-based siting | University of Michigan | $1,100,000 | Through this project we seek to develop (1) guiding principles for respectful community engagement-to support consent-based siting-empirically rooted in the lived experiences of Native Communities; (2) metrics and indicators of consent; and (3) a generative AI tool to facilitate community-based storytelling of the past and imagining of the future to visualize how nuclear infrastructures have and could in the future alter community landscapes. | Document | Consent-based Siting for SNF Management | FY2024 |
| Informing Consent-Based Siting of a Consolidated Interim Storage Facility (CISF): Examining Public Engagement Through History and Evaluation of Prior & Current Outreach Results | Vanderbilt University | $1,000,000 | We will use two phases of research to assist NE in understanding factors that influence the quality and extent of public engagement needed to address different people and communities seeking to make decisions regarding the siting of a CISF. Supporting NE's the consent-based siting process we have developed an accelerated 2-year schedule, focusing on three geographic areas of the US: IL, TX & NM and the area served by the TVA/Duke Power Ñeach contain multiple SNF storage facilities. | Document | Consent-based Siting for SNF Management | FY2024 |
| Accident Tolerant Fuels to Support Power Uprates in LWRs | University of Wisconsin-Madison | $1,100,000 | This project will demonstrate that power uprates higher than the current state of operation can be reached using accident tolerant fuels in light water reactors while not exceeding reactor safety margins during normal operation and accidents. We will analyze it considering fuel enriched up to 10% and peak rod average burnup up to 75GWd/tU concerning reactor physics, thermal-hydraulics, reactor safety, and economics. Considerations will be made in consultation with the named industry advisory board. | Document | Existing Plant Optimization | FY2024 |
| Comparative study of three-dimensional microstructural imaging and thermal conductivity evolution of irradiated solid and annular U-Zr fuels | Massachusetts Institute of Technology | $1,000,000 | Uranium-zirconium (U-Zr) annular metallic fuel holds the promise to simultaneously increase sodium fast reactor (SFR) core uranium loading and reduce peak cladding temperatures, thus greatly improving fuel performance. However, key convolved fuel degradation mechanisms during irradiation at temperature threaten to hold back its real-world applicability, requiring more detailed understanding to both predict U-Zr fuel performance and suggest improvements. | Document | Fuels | FY2024 |
| Mechanistic study and modeling of fission gas release in UO2 and doped UO2 | Oregon State University | $1,000,000 | The objective of this project is to enhance the safety and performance of light water reactors and other advanced reactor designs by gaining a fundamental understanding of fast gas reactor mechanisms and developing mechanistic models for UO2 and doped UO2 fuels under HBU and transient conditions. | Document | Fuels | FY2024 |
| Anisotropic Thermal Properties of SiC-SiC Cladding: Method Development & Characterization | University of Pittsburgh | $1,000,000 | We propose to develop a high-temperature nondestructive thermal conductivity (k) measurement system coupled with validated multiscale models to accurately determine the anisotropic thermal conductivity of SiC-SiC composite cladding tubes. The multiscale measurement and modeling results benefit both DOE ATF programs as well as providing a fundamental understanding of how the microstructure of the composite leads to its anisotropic properties. | Document | Fuels | FY2024 |
| Understanding the Performance of SiC-SiCf Composite Cladding Architectures with Cr Coating in Normal Operating and Accident Conditions in LWRs and Advanced Reactors | University of Wisconsin-Madison | $1,000,000 | The project will focus on investigating the impact of Cr-coating on the SiC-SiCf composite cladding of various architectures under normal operating and accident conditions in light water reactors and advanced reactors for the safe and economic deployment of SiC cladding. Cr-coating will provide protection from high-temperature corrosion and better hermeticity under accident conditions. The performance of the claddings will be evaluated through the corrosion test, reflood test, burst test, and non-destructive evaluation(NDE). | Document | Fuels | FY2024 |
| Developing critical insights on the effects of Mo on a' precipitation and dislocation loop formation in FeCrAl alloys | University of Wisconsin-Madison | $1,000,000 | This project aims at developing a mechanistic understanding on the effects of Mo on a' precipitation and dislocation loop formation in FeCrAl alloys in thermal and irradiation conditions and turns it into a set of design principles guiding further optimization, by integrating atomistic simulations, CALPHAD modeling, thermal aging, proton irradiation, and advanced characterization. The material discoveries will be generalized to other solutes other than Mo. | Document | Fuels | FY2024 |
| Inference of flow conditions from in-core detector measurements for accelerating SMR licensing | Massachusetts Institute of Technology | $1,000,000 | Reactor modelling relies on the detailed description of reactor systems but often lacks the true as-built characteristics of a system. This proposal seeks to fill these geometrical data gaps using available detector data, predictive models and machine learning in order to provide better information to analysis tools and thus better prediction of future performance. | Document | Licensing, Safety, and Security | FY2024 |
| Taggants in Future Nuclear Fuels by Design as an Enabling Technology to Track Nuclear Materials | Rensselaer Polytechnic Institute | $1,000,000 | The overarching goal of this project is to develop an innovative materials accounting and control technology by adopting an approach of "safeguard by design" during fuel fabrication to fill nuclear control technology gaps in tracing and tracking nuclear fuels for advanced nuclear reactors. The project is based on a concept of "taggants in fuels" that can greatly increase forensic attributes, and enhance intrinsic proliferation resistance and MPACT effectiveness for advanced nuclear fuel cycles. | Document | Licensing, Safety, and Security | FY2024 |
| Non-Destructive Plutonium Assay in Pyroprocessing Bulk Materials with a 3D Boron-Coated-Straw Detector Array | University of Illinois at Urbana-Champaign | $1,100,000 | The objective of the proposed project is to develop and demonstrate a 3D boron-coated-straw detector array (3D-BCSDA) with high efficiency and spatial resolution. This detection system will be specifically designed to accurately assess the fissile mass in bulk nuclear material during pyroprocessing operations, thereby improving the precision and reliability of accountability measurements during separation. | Document | Licensing, Safety, and Security | FY2024 |
| Improving the computational efficiency and usability of dynamic PRA with reinforcement learning | University of Maryland, College Park | $1,064,400 | The overall objective of the proposed research is to improve the efficiency and usability of dynamic probabilistic risk assessment (PRA). Specifically, the first objective is to develop a new algorithm for dynamic PRA analysis that can significantly increase the computational efficiency. The second objective is to develop a question-answering system to streamline the process of risk-informed decision-making based on results obtained from the dynamic PRA analysis using the new algorithm. | Document | Licensing, Safety, and Security | FY2024 |
| Development of a Benchmark Model for the Near Real-Time Radionuclide Composition Measurement System using Microcalorimetry for Advanced Reactors | Virginia Commonwealth University | $1,100,000 | The primary goal of this proposed project is to develop high fidelity Monte Carlo radiation transport models of a microcalorimetry detector informed by fuel depletion models of a molten salt reactor and a pebble bed reactor to quantify the current and future capabilities of this detector technology to characterize and assay used fuel from these reactors in near real-time. | Document | Licensing, Safety, and Security | FY2024 |
| Concurrent Surrogate Model Development with Uncertainty Quantification in the MOOSE Framework Using Physics-Informed Gaussian-Process Machine Learning | University of Florida | $999,999 | The objective of this project is to develop a general capability for concurrent generation and use of physics-informed Gaussian process (GP)-based surrogate models to facilitate multiscale and multiphysics modeling. We will implement this new capability as part of the Multiphysics Object-Oriented Simulation Environment (MOOSE) so that every application based on the MOOSE framework will have access to it. | Document | Modeling and Simulation | FY2024 |
| Unstructured Adaptive Mesh Algorithms for Monte Carlo Transport | University of Illinois at Urbana-Champaign | $1,098,000 | We propose to develop the fundamental methods and techniques for unstructured adaptive mesh refinement with Monte Carlo tallies. This work enables a transformative leap forward in speed, accuracy, and robustness to enhance the contribution of high-fidelity radiation transport to advanced simulation. Adaptive refinement is deployed on a challenging multiphysics simulation, cascading heat pipe failure, to study acceleration and stabilization properties. | Document | Modeling and Simulation | FY2024 |
| Feasibility Study of Micro-Nuclear Reactor Thermal Output for Air Rotary Kilns in the High-Temperature Manufacturing of Portland Cement Clinker | Pennsylvania State University | $998,793 | This project aims to design and test a micro-nuclear reactor for high-temperature portland cement clinker production, a process responsible for 6%-8% of global CO2 emissions. Leveraging advanced reactors' heat output, the project explores TRISO-based nuclear microreactor core modifications and new working fluids for heat pipes. The research addresses uncertainties in micro-nuclear reactor deployment for clinker production and investigates high-efficiency heat exchanger designs. | Document | Non-Traditional and Non-electric Applications | FY2024 |
| Redox potential, ionic speciation, and separation and recovery challenges from molten salts containing actinides and fission products | Massachusetts Institute of Technology | $999,999 | Establishing an efficient, safe, secure, and economical Molten-Salt Reactor (MSR) fuel cycle is imperative for MSR implementation. Molten salt fuel recycling technology requires predictive knowledge of the chemical and physical behavior of lanthanide and actinide ions with different oxidation states dissolved in solvent salts. A combination of off-gas and X-ray measurements with machine-learning simulations will be used to produce predictive modeling of separation and recovery conditions. | Document | Nuclear Fuel Recycle Technologies | FY2024 |
| Pre-Treatment and Bulk Separation of Used Fuels with Carbonate-Peroxide Solutions | Pennsylvania State University | $1,000,000 | To use carbonate-peroxide chemistries to develop a pre-processing method for used uranium-based fuels that enables the subsequent use and optimization of current solvent extraction reprocessing schemes. Using simple precipitation, this innovative method provides an initial, bulk separation of uranium from fission products and actinides. | Document | Nuclear Fuel Recycle Technologies | FY2024 |
| Optimization of Fueling Strategies and Material Surveillance through Real-time Pebble Tracking in Pebble Bed Reactors | University of Illinois at Urbana-Champaign | $1,100,000 | Flexible operation of the energy grid of the future introduces uncertainty in determining the optimal operating conditions of Pebble Bed Reactors. The proposed work will help to address these challenges and enable more economical operation by providing the tools to determine of optimal fuel reloading strategy through pebble identification and tracking. | Document | Reactor Development and Plant Optimization | FY2024 |
| Effects of Tritium-Graphite Interactions on Safety Transients in Graphite-Moderated Nuclear Reactors. | University of Illinois at Urbana-Champaign | $1,000,000 | MSRs, FHRs, and HTGRs have tritium production rates 10 to 10,000 times larger than LWRs. Objective of this project is to:-Quantify the concentration of tritium in graphite in new generation FHRs and HTGRs as a function of time and operational conditions-Assess the impact of the tritium content in graphite on reactor physics during normal operations and safety transients-Quantify tritium release rates and release kinetics during reactor transients inducing temperature increases | Document | Reactor Development and Plant Optimization | FY2024 |
| Experimental Study and Computational Modeling of P-LOFC and D-LOFC Accidents in the Fast Modular Reactor Consisting of Silicon Carbide Composite Rods | University of Michigan | $1,100,000 | The primary objectives of this proposed research are to better understand NC flow phenomena and heat transfer under both D-LOFC and P-LOFC accidents in the FMR, produce experimental data in a well-scaled integral-effects test facility for the two accidents, and develop and validate predictive CFD models for NC flow phenomena in both accidents. | Document | Reactor Development and Plant Optimization | FY2024 |
| Sodium heat pipes; design and failure mode assessment for micro-reactor applications | University of Wisconsin-Madison | $1,000,000 | The present proposal aims to experimentally investigate the thermal-hydraulics performance of liquid sodium heat pipes applied to microreactors, with a focus on exploring different design parameters, effects of different parameters on operating performance and understanding the evolution and impact of different failure modes. | Document | Reactor Development and Plant Optimization | FY2024 |
| Interfacial Interactions between Graphite and Molten Fluoride Fuel Salt | Virginia Polytechnic Institute and State University | $1,000,000 | NaF-KF-UF4 fuel salt will be selected to study graphite-salt interactions and impact of the existence of fission products (FPs) and corrosion products on the interactions at different temperatures and pressures. Fundamental mechanisms of graphite-salt interaction and degradation will be understood. | Document | Reactor Development and Plant Optimization | FY2024 |
| AI to Guide Sorption Data Acquisition and Assimilation into Uncertainty Quantifications for the Nuclear Waste Disposal Performance Assessment | Massachusetts Institute of Technology | $800,000 | The objective of this project is to develop machine learning (ML) and AI toolsets to effectively expand the global sorption database-the datasets collected by multiple institutions around the world-and to assimilate these datasets into the uncertainty quantification (UQ) in the performance assessment (PA) of nuclear waste repositories. | Document | Spent Fuel, Waste Science & Technology and Integrated Waste Management System | FY2024 |
| Local resonance-based linear and nonlinear NDE techniques for repaired DSC wall structures | University of Illinois at Urbana-Champaign | $1,000,000 | The proposed work plan will develop nondestructive examination (NDE) methods that develop and evaluate linear and nonlinear resonant ultrasound spectroscopy methods (such as NRUS, NIRAS, etc.) to cold spray (CS) repaired dry shielded canister (DSC) wall structures. With the support of our partners from Pacific Northwest National Laboratory (PNNL) and Oak Ridge National Laboratory (ORNL), we will perform technology development and validation on plain and cold spray-repaired DSC wall specimens. | Document | Spent Fuel, Waste Science & Technology and Integrated Waste Management System | FY2024 |
| Thermodynamic Models for Multivalent Actinide Solubility and Speciation as a Function of Temperature and Ionic Strength | University of Notre Dame | $1,000,000 | This proposed project will quantify the solubility and speciation of Np and Pu under temperatures, ionic strengths, and pH values that are relevant to the generic repository concept. The major deliverable will be full thermodynamic descriptions of the studied systems, which will lead to improved radionuclide transport models and support the development of a sound technical basis for the geologic disposal of spent nuclear fuel and other actinide-bearing wastes. | Document | Spent Fuel, Waste Science & Technology and Integrated Waste Management System | FY2024 |
| Advancing Fundamental Molten Salt Modeling using Ultrafast Spectroscopy | North Carolina State University | $600,000 | The overarching goal of the proposed research is to advance our fundamental understanding of molten salts by combining ultrafast spectroscopic experiments with high fidelity atomistic simulations. The proposed research will introduce a new experimental technique to the study of molten salts that will directly measure ion kinetics, specifically, terahertz time-domain spectroscopy (THz-TDS), which will further validate AIMD as a predictive modeling tool. | Document | Strategic Needs Blue Sky | FY2024 |
| Hydrodynamics of Two-Phase Flow Under the Geometric Effects of Pipe Orientation and U-bends | Purdue University | $600,000 | Most two-phase flow analyses have been performed in straight vertical-upward pipes. However, nuclear reactor systems include piping with different geometric components, such as elbows or U-bends, as well as changes in flow orientations. The proposed work performs experiments in a scaled test facility existing at the institution's lab to investigate the effects of flow orientations and geometries relevant to nuclear reactor systems on the hydrodynamics of two-phase flow. | Document | Strategic Needs Blue Sky | FY2024 |
| Interface-Resolved Experimental and Numerical Studies of Two-Phase Flow for Nuclear Engineering Applications | Virginia Polytechnic Institute and State University | $500,000 | The project aims at advancing the interface-resolved simulation capabilities for the two-phase flows found in various nuclear engineering applications. We will develop a comprehensive, high-resolution, interface-resolved database emphasizing bubble dynamics and bubble interaction mechanisms. The data will be used to validate the sub-grid models implemented in an interface-resolved simulation tool to improve simulation accuracy by developing physics-based coalescence models. | Document | Strategic Needs Blue Sky | FY2024 |
| Mechanism Driven Evaluations of Sequential and Simultaneous Irradiation-Creep-Fatigue Testing | University of Michigan | $1,000,000 | This project addresses a critical need for irradiation and creep-fatigue testing by carrying out a systematic, mechanistic-driven benchmarking for irradiation creep, irradiation fatigue and creep-fatigue tests under various environments. | Document | Advanced Nuclear Materials | FY2023 |
| Mechanisms-based Acceleration of Materials Qualifications for Creep-Fatigue Performance in Advanced Nuclear Systems | University of Illinois at Urbana-Champaign | $1,000,000 | The goal of this research is to fully understand, quantify and model creep-fatigue 'damage' as a function of loading patterns, temperature and microstructural evolution. Using this experimental information over a large range of relevant stress levels and temperatures, a mechanisms-based creep-fatigue analysis approach will be demonstrated which will properly qualify high temperature alloys for extended service in advanced nuclear systems where creep-fatigue is currently a major design limitation. | Document | Advanced Nuclear Materials | FY2023 |
| Subwavelength Ultrasonic Imaging for Rapid Qualification of Additively Manufactured Nuclear Structures and Components | University of Michigan | $1,000,000 | The objective of this project is to develop a transformational capability for rapid nondestructive quality assessment of actual nuclear additively manufactured structures and components through advanced ultrasonic imaging with subwavelength resolution. The resolution of conventional ultrasonic systems is limited by diffraction on the order of the wavelength. In this project, the goal is to break the diffraction limits of ultrasonic imaging by implementing a negative-index lens. | Document | Advanced Nuclear Materials | FY2023 |
| MXene as Sorbent Materials for Off-gas Radioiodine Capture and Immobilization | Clemson University | $1,000,000 | The overarching goal of this project is to develop efficient and stable new sorbent materials, for off-gas radioiodine capture and immobilization, that are based on MXenes with two-dimensional transition metal carbides/nitrides. The exploratory research will focus on three main objectives: 1) Design and synthesis of MXenes as radioiodine sorbent and support materials, 2) Quantification of iodine sorption capacity of MXenes in different forms, 3) Synthesis and characterization of consolidated waste forms. | Document | Advanced Nuclear Materials | FY2023 |
| Fundamental understanding of grain boundary cracking in LWR environments | University of California, Los Angeles | $1,000,000 | The objective of this project is to understand the details of stress corrosion cracking (SCC) and irradiation assisted stress corrosion cracking (IASCC) by targeted experiments and modeling efforts. A comprehensive model will be produced, which will predict the conditions under which these failure modes occur and when the materials may see onsets of the failure mode. This work will directly impact the nuclear industry by refining predictive models of component lifetime. | Document | Advanced Nuclear Materials | FY2023 |
| Facile manufacturing of fiber-reinforced-SiC/SiC composite using aerodynamic fiber deposition (AFD) and metal assisted polymer impregnation and pyrolysis processes (MAPIP) | University of Pittsburgh | $999,886 | SiC/SiC ceramic matrix composites (CMCs) are promising candidate materials for the cladding of accident tolerant fuels. Superior material properties of SiC/SiC CMC, however, come at a high manufacturing cost. The objective of the proposed research is to apply aerodynamic fiber deposition (AFD) and metal assisted polymer impregnation and pyrolysis (MAPIP) to develop a new facile manufacturing approach of SiC/SiC CMC. | Document | Advanced Nuclear Materials | FY2023 |
| High Concentration Monoamide Separations: Phase Modifiers and Transuranic Chemistry | Colorado School of Mines | $999,900 | Extraction of actinides from used nuclear fuel with high concentrations of monoamide extractants is a promising strategy to intensify separation processes; however key issues remain to be understood and resolved. This project will examine three questions: 1) Can phase modifiers mitigate issues with organic phase viscosity? 2) Can the chemistry of neptunium be controlled to ensure complete separation? 3) Do high concentrations of monoamides affect the oxidation states of important metals and can that be exploited? | Document | Fuel Cycle Technologies | FY2023 |
| Multiple Uranium Complexes in Chloride Fast Reactor Molten Salt Properties | University of Connecticut | $1,000,000 | Multivalent transition metal ions in a melt can exhibit multiple coordination states that affect molten salt properties. This project will use a new high-energy resolution fluorescence detection (HERFD) spectroscopy to overcome issues associated with measuring coordination numbers of multiple complexes, along with Raman spectroscopy and advanced simulations to accurately predict properties of molten salts with multiple uranium complexes. | Document | Fuel Cycle Technologies | FY2023 |
| Validation of Geochemical Reactive Transport Long-Term predictions Using Natural Cements and Ancient Cements Analogues | Vanderbilt University | $950,000 | This project will validate long-term performance predictions of rock/cement interfaces based on characterization of natural analogues, ancient cements and interfaces with rock formations, and demonstrate applicability of the established testing and simulation workflow with argillite rock (representative of potential U.S. repository systems). This project addresses the research gap of long-term validation and uncertainty assessment associated with cement barrier performance and multi-physics models. | Document | Fuel Cycle Technologies | FY2023 |
| Predicting Pitting and Stress Corrosion Cracking of Dry Cask Storage Canisters via High Throughput Testing, Multiscale Characterization, and 3D Computer Vision based Machine Learning | The Ohio State University | $1,000,000 | This project consists of a US-UK collaborative research program focusing on the nucleation and growth of pits and stress corrosion cracking of stainless steel 304 (a canister material used for dry cask storage of spent nuclear fuels) by leveraging multi-scale characterization techniques, 2D/3D computer vision, and machine learning approaches. The study will enable the understanding and prediction of how and when pitting corrosion can nucleate, grow, and transition into stress corrosion cracking. | Document | Fuel Cycle Technologies | FY2023 |
| Multiscale Residual Stress Tailoring of Spent Fuel Canister CISCC Resistance | Purdue University | $1,000,000 | The objective of this project is to understand the role of residual stress in chloride-induced stress corrosion cracking (CISCC) of austenitic steel, then tailor CISCC initiation and propagation through engineered multiscale residual stress distributions. Microscopic and macroscopic residual stresses will be systematically varied, then a novel sequence of advanced, site-specific, correlative characterization techniques will be applied to directly link residual stress, pitting, and crack propagation. | Document | Fuel Cycle Technologies | FY2023 |
| Illuminating Emerging Supply Chain and Waste Management Challenges | University of Illinois at Urbana-Champaign | $1,000,000 | Regional constraints on domestic fuel supply and greater variation in demand from advanced reactors has led to a shift in the U.S. fuel cycle, and modeling tools must reflect this. In this work, Cyclus will be updated to better reflect new and emergent regional supply constraints, spatial and temporal fluctuations in material needs, and those impacts on the back-end of the fuel cycle will be quantified. This work will allow for flexible, reproducible analysis to inform stakeholder decision-making. | Document | Fuel Cycle Technologies | FY2023 |
| Determination of Local Structure and Phase Stability of Uranium Species in Molten Halide Salts: Linking Microscopic Structure with Macroscopic Thermodynamics | Arizona State University | $1,000,000 | The goal of this project is to determine the local structures (valence state, coordination configuration and medium-range structure) and thermodynamic stability of uranium species in molten chloride and fluoride salts at high temperatures using a combination of experimental and modeling methods. The obtained results will allow for revelation of the structure-stability relations of the studied systems and development of acid-base scales to determine the solubility of uranium in molten halide salts. | Document | Fuel Cycle Technologies | FY2023 |
| Thermal-Hydraulics Assessment of SiC Compared to Other ATF Cladding Materials and its Performance to Mitigate CRUD | University of Wisconsin-Madison | $1,000,000 | This project aims to experimentally investigate the thermal-hydraulics performance of SiC compared to the Cr-coated zircaloys and APMT ATF cladding materials under accident scenarios, including both DNB and dryout conditions. The project is divided into five tasks that will advance the understanding of the operation and optimization of heat pipes for advanced nuclear reactors. | Document | Fuels | FY2023 |
| Physics-Informed Artificial Intelligence for Non-Destructive Evaluation of Ceramic Composite Cladding by Creating Digital Fingerprints | University of Florida | $1,000,000 | The objective of this project is to spatially map the material composition, structure, and defect distribution of SiCf-SiCm composite tubes from ultrasonic wavefields measured from the materials and the defects within them. Specifically, this project will delve into the unique ultrasonic fingerprints (i.e., dispersion relations and mode shapes) of the SiCf-SiCm composites using physics-informed machine learning to assess the quality of the manufactured tubes based on their spatial-spectral ultrasonic characteristics. | Document | Fuels | FY2023 |
| Improving Reliability of Novel TRISO Fuel Forms for Advanced Reactors via Multiscale, High-Throughput Characterization and Modeling | Brigham Young University | $1,000,000 | This project will use a parallelized thermal conductivity (k) measurement device coupled with multiscale models to accurately predict the thermal conductivity of TRISO fuel composites. This project overcomes the issue plaguing many "localized" microscale measurements, namely the inability to scale local measurements up to engineering scale properties. This will be done by using Bayesian inference techniques and finite element models to predict effective thermal conductivity. | Document | Fuels | FY2023 |
| Understanding Constituent Redistribution, Thermal Transport, and Fission Gas Behavior in U-Zr Annular Fuel Without a Sodium Bond | University of Florida | $999,462 | This project will investigate the reason for changed constituent redistribution in annular U-Zr fuel without a sodium bond and how it changes the fission gas behavior and thermal conductivity. This will be achieved using a combination of microstructure characterization and thermal conductivity measurements of irradiated U-Zr annular fuel and multiscale modeling and simulation using the MARMOT and BISON fuel performance codes. | Document | Fuels | FY2023 |
| Getting AnCers: Metallothermic Molten Salt Synthesis and Reaction Thermodynamics of Actinide Ceramic Fuels | Oregon State University | $1,000,000 | Synthesis of high quality actinide ceramics (AnCers) remains a costly challenge. A low-temperature, high-yield, short-duration reaction that directly synthesizes UN and UC could reduce the cost of these advanced fuels greatly. This proposal aims to demonstrate a method by which the costs of AnCers can be greatly reduced-metallothermic molten salt synthesis. Optimization and thermodynamics data will be obtained. | Document | Fuels | FY2023 |
| Integrated Stand-off Optical Sensors for Molten Salt Reactor Monitoring | University of Pittsburgh | $1,000,000 | This project intends to develop robust and stand-off optical sensors to perform real-time molten salt levels, flow, and impurity measurements of molten salts. | Document | Instrumentation and Controls | FY2023 |
| Optical Sensors for Impurity Measurement in Liquid Metal-cooled Fast Reactors | University of Michigan | $1,000,000 | This project will investigate whether a unique combination of two versatile optical techniques-laser-induced breakdown spectroscopy (LIBS) and two-photon absorption laser-induced fluorescence (TALIF)-could provide a sensitive, robust, and convenient method for in-situ, real-time detection of trace impurities ( | Document | Instrumentation and Controls | FY2023 |
| Cybersecurity in advanced reactor fleet by cyber-informed design, real-time anomaly detection, dynamic monitoring, and cost-effective mitigation strategies | University of Wisconsin-Madison | $1,000,000 | The goal of this research is to provide technical solutions to unique cybersecurity challenges in future microreactor fleet through cyber-informed design (C-ID), real-time anomaly detection, dynamic monitoring, and cost-effective mitigation strategies. The efforts will significantly improve the economics and effectiveness of cybersecurity risk management in future microreactor fleets. | Document | Instrumentation and Controls | FY2023 |
| Building Cyber-Resilient Architecture for Advanced Reactors via Integrated Operations and Network Digital Twin | Georgia Institute of Technology | $1,000,000 | The research will develop a secure-by-design architecture via integrating plant operation and network digital twins for advanced reactors. Automatic attack path and vulnerability analysis will be developed and used to assess and harden critical digital assets (CDA) against cyber risks prior to and during operation to identify vulnerabilities, attack pathways, and threat vectors. A CDA selection method will also be developed by combining vulnerability scores and assets importance. | Document | Instrumentation and Controls | FY2023 |
| Extending PRA and HRA legacy methods and tools with a cause-based model for comprehensive treatment of human error dependency | University of California, Los Angeles | $1,000,000 | This project aims at developing a solution to HRA dependency assessment in PRA from methodological and practical/computational perspectives within legacy PRA tools and methods. The solutions will include procedures for quantifying dependency when using PRA legacy tools, a method for modeling and quantifying dependency in HRA comprising a BN-causal model suitable for use with legacy PRA methods and tools, and the computational tools for its integration. | Document | Licensing and Safety | FY2023 |
| An Integrated Elemental and Isotopic Detector for Real-Time Molten Salt Monitoring | North Carolina State University | $1,000,000 | The overarching theme of the proposed research is to develop and demonstrate a real-time elemental and isotopic detector of molten salts for advanced reactors and fuel fabrication and recycling processes. The detector's longevity, limits, and latency will be tested in static uranium chloride salts, in pyroprocessing chloride salt, and on flowing fluoride salt with evolving actinide composition, respectively. | Document | Licensing and Safety | FY2023 |
| Development of a Thin-Layer Electrochemical Sensor for Molten Salt Reactors and Fuel Cycle Processes | Brigham Young University | $811,755 | A thin-layer electrochemical sensor capable of detecting uranium, plutonium and other species of interest in molten salts, at both high and low concentrations, will be developed for application in molten salt reactors and fuel cycle process units. This will provide a valuable tool for performing material control and accountancy measurements. | Document | Licensing and Safety | FY2023 |
| Risk-Informed Consequence-Driven Hybrid Cyber-Physical Protection System Security Optimization for Advanced Reactor Sites | Georgia Institute of Technology | $1,000,000 | This project aims to develop an expanded methodology for designing a novel cybersecurity-integrated physical protection system (PPS) framework for advanced reactor concepts that serves to reduce the operational costs for the life of a reactor against that of a traditional light water reactor PPS design, promoting efforts to credit safety features of advanced reactors through proposed amendments to current security regulations, while integrating health and economic consequence analyses. | Document | Licensing and Safety | FY2023 |
| A risk analysis framework for evaluating the safety, reliability, and economic implications of electrolysis for hydrogen production at NPPs | University of Maryland, College Park | $1,000,000 | The RAFELHyP project will develop a modular risk analysis framework that enables evaluating the safety, reliability, and economic implications of upcoming deployments of electrolyzers to produce hydrogen at nuclear power plants. The framework will be implemented to conduct an integrated safety, reliability, and economic analysis of multiple plant configurations to provide detailed recommendations for plant protective features and layouts. | Document | Licensing and Safety | FY2023 |
| Reduced Order Modeling of Heat and Fluid Flow: Multi-Scale Modeling of Advanced Reactors to Enable Faster Deployment | University of Illinois at Urbana-Champaign | $1,000,000 | Novel multi-scale algorithms for thermal-hydraulics (TH) simulations of advanced reactors will be developed. The methods will leverage recent advances in hardware and reduced order modeling approaches to enable TH simulations of vastly accelerated speed, while maintaining accuracy comparable to high-fidelity methods, such as large-eddy simulation. The methods will allow designers to perform parameter sweeps, develop closures, and enable high fidelity simulation of transients. | Document | Modeling and Simulation | FY2023 |
| Embedded Monte Carlo | Massachusetts Institute of Technology | $1,000,000 | Monte Carlo methods have long been considered the standard in terms of accuracy and have seen increased use in design of small nuclear systems; however, the uncertainty quantification (UQ) of the desired output is often relegated to later stages of the design process. This project seeks to embed nuclear data UQ in a single Monte Carlo simulation, such that each desired quantity will not only provide the mean value and statistical uncertainty, but also the related nuclear data uncertainty. | Document | Modeling and Simulation | FY2023 |
| A Low Order Transport Method Based on the Dynamic Truncation of the Integral Transport Matrix Method (ITMM) that Converges to the SN Solution with Increasing Cell Optical Thickness | North Carolina State University | $1,000,000 | A novel low-order transport operator capable of approximating Monte Carlo (MC) results within a variance range will be developed. This does not require MC reference solutions to calibrate the low-order model, so repeated solutions of the latter in-transient scenarios does not require repeated MC simulations. Truncation of the low-order operator is done dynamically for evolving configurations to ensure accuracy of the low-order solution. This will involve proof of principle on Cartesian meshes, then implementation in Griffin. | Document | Modeling and Simulation | FY2023 |
| CFD based Critical Heat Flux predictions for enhanced DNBR margin | Massachusetts Institute of Technology | $1,000,000 | This project seeks to demonstrate a robust high-fidelity CFD-based methodology to predict CHF behavior at varying quality conditions, enabling the development of advanced DNBR correlations with reduced uncertainty, and in support of upgraded plant economics. The availability of a virtual CHF methodology will allow greatly extending the database for DNBR correlations development and further support advancement in the design of high-performing nuclear fuel. | Document | Modeling and Simulation | FY2023 |
| Immersed Boundary Methods for Modeling of Complex Geometry: A Leap Forward in Multiscale Modeling using NekRS | University of Illinois at Urbana-Champaign | $1,000,000 | A major challenge to Computational Fluid Dynamics (CFD) modeling of complex geometries is the need to generate body-fitted meshes, which can occupy 80% of the CFD practitioner's time. Immersed boundary methods will be added in the NekRS CFD code, dramatically simplifying modeling of complex 3-D structures and facilitating a new paradigm for CFD-informed multiscale analysis. This will be demonstrated by informing SAM transient systems-level models with NekRS heat exchanger correlations for advanced reactors. | Document | Modeling and Simulation | FY2023 |
| Uncertainty Quantification of Model Extrapolation in Neural Network-informed Turbulent Closures for Plenum Mixing in HTGRs | Utah State University | $1,000,000 | This project will quantify the uncertainty in prediction of Neural Network-informed Turbulent Closures when they are operating in a model extrapolation state. Once the method is developed for canonical buoyant jets, the protocols will be applied to plenum mixing in HTGRs. | Document | Modeling and Simulation | FY2023 |
| Impact of moisture on corrosion of NiCr alloys in MgCl2-NaCl Salt Systems | University of Wisconsin-Madison | $999,983 | This project aims to gain a fundamental understanding of the impact of moisture and salt chemistry on corrosion of NiCr alloys in molten chloride salts. A novel approach coupling multiscale simulations and experiments will be designed to determine salt acidity, its dependence on salt composition (i.e., the NaCl to MgCl2 ratio), and its effects on the transport of H2O and Cr ions and the corrosion kinetics of NiCr alloys in chloride salt. | Document | Reactor Development and Plant Optimization | FY2023 |
| Transforming Microreactor Economics Through Hydride Moderator Enabled Neutron Economy | State University of New York, Stony Brook | $1,000,000 | Microreactors will potentially require the cost of electricity to be 10 MWD/kg at >3 kW/kg core specific power. These goals are best achieved through a well-thermalized spectrum. Neutron economy as a core material selection criterion to advance entrained hydride composite moderators will be used with the primary goal of significantly reducing fuel costs through novel microreactor designs. | Document | Reactor Development and Plant Optimization | FY2023 |
| Integrating Nuclear with ZLD Seawater Desalination and Mining | University of Wisconsin-Madison | $1,000,000 | An integrated nuclear system will be developed that would utilize electricity and waste heat to operate a desalination and mining process from adjacent seawater. The desalination approach targets zero-liquid discharge with multiple marketable minerals extracted. The ability of nuclear facilities to load follow is increasingly important, so a cold thermal storage system will be incorporated. The desalination and mineral extraction process will be experimentally validated at lab scale. | Document | Reactor Development and Plant Optimization | FY2023 |
| Reference Designs of Green Ammonia Plants Powered by Small Modular Reactors | Utah State University | $1,000,000 | The overarching goal of this project is to develop two reference designs for green ammonia plants. One design uses freshwater as the source for hydrogen, while the other design uses seawater (or brackish water) as the source. In both designs, a small modular reactor (SMR) is used as the primary energy source providing both electricity and steam for the plants. | Document | Reactor Development and Plant Optimization | FY2023 |
| Development of the Technical Bases to Support Flexible Siting of Microreactors based on Right-Sized Emergency Planning Zones | Pennsylvania State University | $1,000,000 | The objective of this project is to provide the technical basis to support the application of a right-sized Emergency Planning Zone (EPZ) size to support the deployment of a microreactor at the Penn State University Park campus. This research study will serve as a template to provide flexible siting in support of future microreactor deployments that may be placed closer to demand centers, thereby making them more economically competitive. | Document | Reactor Development and Plant Optimization | FY2023 |
| Bayesian Optimization for Automatic Reactor Design Optimization | Arizona State University | $1,000,000 | The objective of this project is to develop analytical tools based on Gaussian process modeling and Bayesian Optimization that facilitate reactor design optimization by modeling the responses from the physics simulator. Existing capabilities will be applied in an AI field and they will be adapted to address the key characteristics of nuclear reactor design problem. This project will automate the simulation-based design procedure, reduce the number of iterations, and minimize the design cycle time. | Document | Reactor Development and Plant Optimization | FY2023 |
| A Pathway for Implementation of Advanced Fuel Technologies in Light Water Small Modular Reactors | Texas A&M University | $1,000,000 | A comprehensive characterization of the performance of the Lightbridge Helical Cruciform advanced fuel design will be performed, which will generate unique sets of experimental data of friction factor, flow and heat transfer behavior under NuScale's LW-SMR simulated normal and off-normal conditions. The project will accelerate the deployment of advanced fuels for LW-SMR applications by leveraging the use of existing testing infrastructures. | Document | Reactor Development and Plant Optimization | FY2023 |
| Engaging New Mexican communities in developing an equitable and just approach to siting advanced reactor facilities | University of Michigan | $1,000,000 | This project will engage diverse New Mexican communities to develop an equitable approach for advanced reactor siting. The findings of this project will shed light on how technology developers and the DOE can explore and potentially site advanced reactors with the informed consent and engagement of host communities, regions, and states. The findings of this study will also more generally apply to the potential for equitably exploring both brownfield and greenfield sites for nuclear facilities. | Document | Reactor Development and Plant Optimization | FY2023 |
| Deciphering Irradiation Effects of YHx through In-situ Evaluation and Micromechanics for Microreactor Applications | University of New Mexico | $998,000 | This project addresses a critical gap in accelerated testing of YH evolution coupling multi-length scale mechanical testing with ion irradiation and advanced characterization to establish a baseline understanding of YH evolution under ion irradiation. Our approach will couple ion irradiation and gamma irradiation with small scale mechanical testing to decipher multi-scale impacts on phase stability to advance understanding of YH in a microreactor moderator application. | Document | Reactor Development and Plant Optimization | FY2023 |
| Active Learning Estimation and Optimization (ALEO) of Irradiation Experimental Design for Efficient Accelerated Fuel Qualification | University of Texas at San Antonio | $997,247 | This collaborative project creates novel AI/ML models and algorithms integrated with physical knowledge and expertise to explore more efficient ways to calculate irradiation temperatures and fuel specimen burnups for new fuel sample configurations of MiniFuel experiments proposed for irradiation in the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL). | Document | Reactor Development and Plant Optimization | FY2023 |
| Unraveling how mixing vane spacers affect cladding-to-coolant heat transfer phenomena in light water reactors | Massachusetts Institute of Technology | $500,000 | Experiments will be conducted to quantify the effect of mixing vane spacers on cladding-to-coolant heat transfer phenomena, namely single-phase forced convection, nucleate boiling, and CHF. The results of the experimental research will allow elucidating the physical phenomena triggered by the presence of mixing vane spacers. They will also allow assessing the performance of M-CFD tools developed within CASL and in use by the nuclear community. | Document | Strategic Needs Blue Sky | FY2023 |
| Quantum Computing Algorithms for Deterministic Neutron Transport | University of Michigan | $500,000 | This project will develop algorithms for solving the k-eigenvalue form of the neutron transport equation in a nuclear reactor physics context on a quantum computer. The asymptotic scaling of the algorithms will be analyzed. Investigation into implementation will be made by making resource estimates by synthesizing explicit circuits for the algorithms and be studied by emulation on a classical computer. | Document | Strategic Needs Blue Sky | FY2023 |
| Optimizing Application-Dependent Energy Group Structures for Multigroup Neutron Transport Models using Machine Learning | Colorado School of Mines | $500,000 | Machine Learning methods will be developed that will dramatically reduce both the computational run-time and manual effort needed to find multigroup energy structures that accurately capture the underlying physics of neutron reactions, while allowing multigroup simulations to run quickly without overwhelming available memory. | Document | Strategic Needs Blue Sky | FY2023 |
| Functionally-graded Cermet Coatings for Molten Salt Technologies by High Throughput Finite Element Modeling and Additive Manufacturing | Rensselaer Polytechnic Institute | $500,000 | This project proposes an integrated approach/methodology to design, manufacture and verify functionally-graded metal-ceramic composite coatings on structural alloys with desired interfacial properties, capabilities of mitigating residual stress and improved corrosion resistance for molten salt reactor applications. | Crosscutting Technologies | FY2022 | |
| An Innovative Monitoring Technology for the Reactor Vessel of Micro-HTGR | Texas A&M University | $800,000 | This project seeks to develop an innovative sensor technology for real-time monitoring of the thermo-mechanical stresses in the reactor vessel of micro-HTGR. The technology will be based on a sparse network of outer wall temperature measurements and plant operating conditions. An integrated software-hardware sensing system aimed at monitoring the health of the pressure vessel of gas micro-reactors will be implemented and tested. The proposed work will have a broad impact on sensing in other reactor designs. | Crosscutting Technologies | FY2022 | |
| High throughput mechanical testing of additively-manufactured materials | University of California, Berkeley | $500,000 | This project proposes fast and high throughput mechanical testing of AM produced materials. It will include the generation of automated tensile testing, hardness testing and microstructure assessment and data comparison to build data via machine learning. | Crosscutting Technologies | FY2022 | |
| Accelerated irradiation creep testing coupled with self-adaptive accelerated molecular dynamics simulations for scalability analysis | University of Michigan | $500,000 | The goal of the proposed work is to accelerate traditional irradiation creep using instrumented in-situ ion irradiation creep and long-time molecular dynamics simulations to accelerate traditional neutron irradiation creep testing. This goal will be accomplished by coupling a novel ion beam flux jump test using tapered creep specimens and self-adaptive accelerated molecular dynamics. The outcome is a rapid, low-cost accelerated method to determine the fundamental irradiation creep mechanisms. | Crosscutting Technologies | FY2022 | |
| Creation of a Pebble Database for Material Control and Accountancy in Pebble Bed Reactors | Virginia Commonwealth University | $399,969 | The primary goal of this proposed project is to develop a database of NDA signatures from a wide variety of used PBR pebbles. This database can be used for facility operations, safety, security, and safeguards (3S) to directly measure fission product content and indirectly 235U and plutonium content of each PBR pebble. This project has significant synergy with current 3S PBR research at ANL, BNL, and ORNL, all of whom are collaborators to this proposed project. | Crosscutting Technologies | FY2022 | |
| Integrated Marine Platform for Hydrogen and Ammonia Production | Massachusetts Institute of Technology | $800,000 | This study investigates the economic and environmental value of a floating integrated GW-scale green hydrogen/ammonia production facility powered by an advanced nuclear reactor. Floating Production Storage and Offloading units (FPSOs) are deployed worldwide in the oil and gas industry, and can be used for hydrogen and ammonia processing. Deployment of an advanced reactor on a floating platform offers several advantages, including the efficiencies of shipyard fabrication. | Crosscutting Technologies | FY2022 | |
| Quantifying Aerosol Deposition Mechanisms in Model Dry Cask Storage Systems | Clemson University | $800,000 | The objective of this work is to measure aerosol deposition and resuspension rates in laboratory models of dry cask storage systems to compare with and validate the DOE deposition model. The project team will conduct experiments to directly measure the deposition/resuspension rates of bulk aerosol in the system and to isolate and quantify individual aerosol deposition mechanisms, with a focus on those sensitive to variable humidity and surface temperature. | Fuel Cycle R&D | FY2022 | |
| Using Amide-Functionalized Electrodes to Elucidate Interfacial Actinide Redox Chemistry for Improved HALEU Supply | Florida International University | $400,000 | The goal is to decrease HALEU fuel cycle costs by examination of the redox behavior of U, Np, and Pu at the water-organic interface using amide functionalized electrodes, and in organic media after extraction with amides. Experiments with redox active interferences including additional actinides in different oxidation states will also be conducted. | Fuel Cycle R&D | FY2022 | |
| Advancing the technical readiness of FeCrAl alloys and ODS steels under extreme conditions for fast reactor fuel cladding | North Carolina State University | $800,000 | A key technology gap for advanced high-performance fuel applications is the current unavailability of materials that can withstand extremely high doses without significant degradation of cladding performance. The project team will perform in-situ thermo-mechanical experiments (tension, torsion, creep, and creep-fatigue and nanoindentation) on ion-irradiated (to 400 dpa) cladding materials (up to 700 C) along with microstructures using TEM and mesoscale phase field simulations. | Fuel Cycle R&D | FY2022 | |
| A molten salt community framework for predictive modeling of critical characteristics | Pennsylvania State University | $400,000 | This research aims to develop a molten salt community framework to address the needs in advanced fuel cycles, including understanding salts via new theory of liquids, predicting salt characteristics via simulations (DFT, MD, and CALPHAD by implementing advanced models), optimizing inversely molten salts, and verifying simulations by experiments. This project has outstanding value for US taxpayers, educates students, and delivers outreach opportunities for academia, industry, and the public. | Fuel Cycle R&D | FY2022 | |
| Understanding the Interfacial Structure of the Molten Chloride Salts by in-situ Electrocapillarity and Resonant Soft X-ray Scattering (RSoXS) | Pennsylvania State University | $400,000 | The objective of the proposed research is to investigate the interplay between the interfacial structure of the molten salts and their electrochemical corrosion properties in Molten Salt Reactors (MSRs). | Fuel Cycle R&D | FY2022 | |
| Clay Hydration, Drying, and Cracking in Nuclear Waste Repositories | Princeton University | $800,000 | This project will develop a new multiscale model of the thermal-hydrologic-mechanical-chemical (THMC) evolution of an engineered clay barrier in the near field of a nuclear waste repository, including initial hydration and eventual post-closure criticality. This new model will directly link micro-scale material properties to large-scale barrier performance, thus facilitating future design advances or modifications, and enable robust validation of large-scale simulation predictions. | Fuel Cycle R&D | FY2022 | |
| Physics-guided Smart Scaling Methodology for Accelerated Fuel Testing | Purdue University | $800,000 | This project proposes to employ novel informatics algorithms for mapping/scaling uncertainties from experimentally accessible scaled state to application/prototypical state, informed by an equivalent mapping obtained from high-fidelity multi-physics simulations for the fuel thermo-mechanical behavior, specifically, a rate theory-based model for thermal conductivity and fission gas behavior in the BISON code, and employing relevant HALDEN reactor and FAST experiments. | Fuel Cycle R&D | FY2022 | |
| Materials Accountancy During Disposal and Waste Processing of Molten Salt Reactor Fuel Salts | Texas A&M University | $399,997 | The objective of this work is to develop and validate a method for measuring and predicting hold-up to eliminate operational risks and expenses during disposal of salt-wetted MSR components. These objectives will be met by applying robust measurement/detection methods to realistic salt loop environments to validate their use in decommissioning MSRs. | Fuel Cycle R&D | FY2022 | |
| Advanced Screening Approaches for Accelerating Development of Separations Technologies | University of California, Berkeley | $400,000 | The goal of this project is to establish a unified selection criterion for chelating molecular structures to more efficiently address ligand applicability to metal ion separation problems, for current and future nuclear fuel cycles. By establishing this criterion, the team will seek to enable the accelerated, cost-effective discovery of new separation workflows, as well as their implementation beyond early radiotracer experiments. | Fuel Cycle R&D | FY2022 | |
| Advancing NMA of TRISO-fueled pebbles using fast and accurate gamma-ray spectroscopy | University of Colorado, Boulder | $385,307 | This proposal will provide new Nuclear Materials Analysis (NMA) capabilities for TRISO-fueled pebbles using gamma-ray spectroscopy, through a program of simulations of expected signatures from irradiated pebbles, resulting in a detailed measurement plan to monitor burnup and actinide content throughout the fuel cycle. These simulations will be used to develop requirements for NMA sensor technology and identify opportunities for focused technology development to meet these requirements. | Fuel Cycle R&D | FY2022 | |
| Development of Irradiation and Creep Resistant High-Cr Ferritic/Martensitic Steels via Magnetic Field Heat Treatment | University of Kentucky | $800,000 | The objective of this proposed study is to develop and test new generation of Ferritic/Martensitic (F/M) steels specifically designed for advanced reactors that will exceed the current limitations due to temperature and irradiation dose. To achieve this objective, a systematic study is proposed to employ an innovative tempering heat treatment under high external magnetic field (up to 9T) on F/M steel HT9 to engineer an optimized microstructure composed of refined carbides and martensite laths. | Fuel Cycle R&D | FY2022 | |
| Investigation into the processing parameters of phosphate-based dehalogenation for chloride-based waste salt | University of Nevada, Reno | $399,999 | This proposal will focus on several topics needed to advance the iron phosphate process: 1) Dehalogenation/vitrification processes using salt simulants to generate process flow sheets, 2) Reactions of crucible materials with phosphate products and byproducts, 3) Collection of glass property-composition data to develop models based on the glass-forming regions, 4) Development of a process for reacting recovered NH4Cl with metals that need to be fed into the system (U, Li, etc.). | Fuel Cycle R&D | FY2022 | |
| A Validated Framework for Seismic Risk Assessment of Spent Fuel Storage Facilities | University of Nevada, Reno | $799,883 | This is a collaborative research program with a primary objective of developing a validated numerical framework for seismic risk analysis of spent fuel storage facilities from the global cask behavior to the localized behavior of internal spent fuel assemblies. In building and validating this framework, advanced data analysis, data assimilation, and forward and inverse modeling techniques will be utilized. | Fuel Cycle R&D | FY2022 | |
| International Collaboration to Advance the Technical Readiness of High Uranium Density Fuels and Composites for Small Modular Reactors | University of Texas at San Antonio | $800,000 | An international team of high uranium density fuels (HDFs) experts advised by industry leaders in nuclear reactor innovation propose a US-UK collaboration to advance the technical readiness of UN, UB2, and their composites for fuel forms specific to small modular reactors (SMRs). The project will bridge the critical data gaps in HDF performance specific to the impact of common impurities and microstructural variations that originate at fabrication. | Fuel Cycle R&D | FY2022 | |
| Development of Advanced Control Rod Assembly for Improved Accident Tolerance and High Burnup Fuel Cycle | University of Wisconsin-Madison | $800,000 | Research will focus on the development of new materials' designs for control rod sheaths and neutron absorbers, coupled with neutronics analysis and thermo-mechanical modeling to improve accident tolerance and to achieve higher fuel burnup in PWRs. Functionality of the proposed designs consisting of Cr coated control rod sheaths of current and advanced alloys as well as novel neutron absorbers will be evaluated in prototypical reactor conditions and accident scenarios. | Fuel Cycle R&D | FY2022 | |
| Optical Basicity Determination of Molten Fluoride Salts and its Influence on Structural Material Corrosion | University of Wisconsin-Madison | $400,000 | The proposed research is aimed at developing ion probes to determine the optical basicity of molten fluoride salts and studying its influence on structural material corrosion. Combining with the molten salt structure study using X-ray absorption spectroscopy, the salt chemical constitution, the resulting optical basicity, and molten salt structure will be inextricably linked and their connections will be unveiled. | Fuel Cycle R&D | FY2022 | |
| Extending the HMF71 Benchmark Series for Graphite Reflector Thickness up to 18 Inches | University of Tennessee at Knoxville | $399,522 | The objective of this proposal is to extend the HEU-MET-FAST-071 (HMF-71) experiment benchmark series in ICSBEP by evaluating the historical (existing) experimental data for critical experiments with graphite reflector thickness from 3 inches up to 18 inches. | Nuclear Energy | FY2022 | |
| Fast and Rigorous Methods for Multiphysics SPn Transport in Advanced Reactors | University of Michigan | $600,000 | This project proposes to perform rigorous theoretical and numerical analysis of the Generalized SPn method and underlying cross section models to enable a fast and robust multiphysics low-order transport capability for advanced reactors. This includes 5 major tasks focused on the efficient discretization and solution of the GSPn equations, numerical analysis of XS models having multiphysics and depletion, analysis of equivalence factors, improved MC estimators, and several V&V applications of the methods. | NEAMS | FY2022 | |
| Development of Hydrogen Transport Models for High Temperature Metal Hydride Moderators | Colorado School of Mines | $800,000 | Understanding the transient behavior of metal hydride moderator materials at high temperatures is a key challenge to the design and deployment of future microreactors. This project will use neutron radiography techniques provide the necessary data for this understanding and demonstrate the development of time and temperature dependent hydrogen transport models using both commercial FEA software coupled to MCNP and coupled models developed in the MOOSE framework. | RCRD&D | FY2022 | |
| Characterizing fast reactor fuel failure mode through separate effect and prototypic tests | Oregon State University | $800,000 | The project consists of conducting separate effect fuel pin failure tests with surrogate fluid and prototypic test with sodium. The outcome of this study will generate an experimental database that will be used to develop mechanistic model and validate the CDAP module of the SAS4A/SASSYS-1 code. Ultimately the quality data can be used to benchmark other fuel codes developed for LMFR application, which are seeking validation for licensing purpose. | RCRD&D | FY2022 | |
| Science-based development of ASTM standard tests for graphite-based fuel pebbles | University of California, Berkeley | $700,000 | This project proposes the development of mechanical test procedures as well as wear and friction tests on Graphite fuel pebbles | RCRD&D | FY2022 | |
| Role of Heterogeneity in Manganese and Nickel Rich Precipitate Distribution on Hardening of Reactor Pressure Vessel Steels: Integrated Modeling and Experimental Characterization | University of Florida | $799,803 | The hypothesis of this work is that the different nucleation and coarsening kinetics of manganese and nickel rich precipitates (MNPs) compared to copper rich precipitates, and the heterogeneous distribution of manganese and nickel rich precipitates on or near dislocations, both lead to unique hardening behavior at high neutron fluence. The objective of this work is to understand hardening in reactor pressure vessel steels caused by MNPs via integrated multiscale modeling and experiments. | RCRD&D | FY2022 | |
| Integrated Thermal-Electric Energy Management of All-Electric Ship with Advanced Nuclear Reactors | University of Texas at Dallas | $400,000 | The overall objective of this research is to comprehensively model, design, and evaluate the use of advanced nuclear reactors in future nuclear-powered ships, to enhance the efficiency, reliability, and resilience of shipboard energy distribution systems. The novelty of the proposed approach lies in (i) integrated thermal-electric modeling of advanced nuclear-powered shipboard energy system, and (ii) novel solutions for total-ship energy management to improve energy efficiency and resiliency. | RCRD&D | FY2022 | |
| Open Architecture for Nuclear Cost Reduction | University of Wisconsin-Madison | $800,000 | Open architecture has potential to reduce advanced reactor (AR) costs, through exploiting modular design and construction, with common, openly available interfaces between modules. A comprehensive assessment of the challenges and opportunities of open architecture for ARs will be performed. Supported by a pilot study, actionable recommendations for the implementation or otherwise of open architecture for ARs will be developed. | RCRD&D | FY2022 | |
| Telescopic Control Rod for Significant Reduction in HTR Height and therefore Cost | University of Wisconsin-Madison | $800,000 | This project proposes a design for a small modular High Temperature Reactor (HTR) control rod that extends telescopically, consisting of ~5 concentric annuli that nest together above the core when withdrawn. This compact component substantially reduces the length of the depth of the silo. Modelling and experimental testing will be performed to develop the control rod to evaluate feasibility, plus perform a cost-benefit analysis, with a view to its inclusion in both pebble bed and prismatic HTR designs. | RCRD&D | FY2022 | |
| NEUP Project 21-24394: Computer vision and machine learning for microstructural qualification | Carnegie Mellon University | $497,518 | Quantifying and understanding microstructure is a key driver for performance-based materials qualification. In this proposal, well-curated data sets of microstructural images will be gathered and computer vision and machine learning will be applied to build quantitative deep learning frameworks to accelerate and enable qualification of nuclear materials based on microstructural features. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-24156: Experimental thermofluidic validation of TCR fuel elements using distributed temperature and flow sensing | Kansas State University | $798,250 | The overall goal of this project will be to test the performance of 3D printed Transformational Challenge Reactor core geometry parts using existing Helium flow loops and distributed temperature, and velocity sensing systems. Thermal transport capabilities of scaled 3D printed ceramic core will be evaluated experimentally and measurements will be used to qualify computational models. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-24636: Risk-informed Consequence-driven Physical Protection System Optimization for Microreactor Sites | Texas A&M University | $400,000 | This proposed project will utilize a risk-informed, consequence-driven analysis to develop an approach for "right-sizing" physical protection systems (PPS) for microreactors. The hypothesis presented for this proposal is that the explicit coupling of consequence modeling to PPS design will provide a similar benefit that can be applied prior to reactor construction. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-24131: Total Mass Accounting in Advanced Liquid Fueled Reactors | The Ohio State University | $400,000 | A total mass determination method for nuclear materials accounting (NMA) in liquid-fueled molten salt reactors will be validated with fuel-bearing salt, mixed with a + radioisotope of known activity, that will be irradiated to reproduce the practical NMA scenario in a molten salt loop. Irradiated fuel salt will be sampled and measured for its mass and activity. The mass-to-activity ratio will be used to calculate the unknown salt mass in the original container. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-24037: Design and intelligent optimization of the thermal storage and energy distribution for the TerraPower Molten Chloride Fast Reactor in an Integrated Energy System (IES) | University of Tennessee at Knoxville | $800,000 | The objective of this project is to explore the application of advanced reactors within Integrated Energy Systems, use extensive existing data from UIUC for model development and validation, and extend the predictions to larger grids and commercial applications. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-24522: Targeted Materials Characterization and Testing of Additively Manufactured Metals and Ceramics to Inform Print/Build Data Analytics | University of Texas at San Antonio | $800,000 | A collaborative program between the University of Texas at San Antonio and Boise State University is proposed to supply materials testing and characterization data sets to be leveraged by the TCR program to inform build/print data analytics. With the data provided by the proposing team, correlations among steam oxidation performance, micromechanical properties, chemical composition, local microstructure, and location specific print/build data will be achieved. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-24431: Location-specific material characterization of LPBF SS316L & IN718 TCR core structural materials | Utah State University | $800,000 | In this proposed work, we will experimentally characterize the spatial variability of the quasi-static (tensile), creep (strength and impression), and creep-fatigue properties as well as the underlying structures (microstructure and defect structures) for LPBF SS316L and IN718 components to be used as training data to the TCR program data-driven model. The resulting correlation will be used to drive the design process for an application as TCR core structural materials. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-23978: Rapid, Non-Radioactive Methods for Prediction and Quantification of Radiolytic Radical Decomposition Products in Nuclear Separations | Clemson University | $399,999 | High-throughput, non-radioactive, radical assays will be used to determine decomposition of monoamide separations complexants. Radical assay results will be correlated with classic radiolytic damage results to develop predictive models for screening complexant stability. These models will aid in single-stage separations complexant optimization, in the transition from lab-to industrial-scale nuclear waste separations and, ultimately, could yield field tests for radiolytic damage. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24350: Phosphate Mineral and Glass Waste Forms for Advanced Immobilization of Chloride and Fluoride-based Waste Streams | Clemson University | $600,000 | This proposal is intended to develop three waste form options for immobilizing the fluoride-and chloride-salt waste stream in highly durable and easily processable phosphate minerals and glasses, including phosphate apatite ceramic waste forms, phosphate glass waste forms, and phosphate glass-ceramic waste forms with apatite phase. Multiple monolithic waste form samples will be provided to DOE national laboratories for further testing. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24292: Passive multimodal tomography for dry storage casks imaging using passive neutron and gamma dosimetry and cosmic ray muons | Colorado School of Mines | $800,000 | A method for multimodal tomography of dry storage casks will be developed to determine fuel relocation and cladding failures using passive neutrons and gamma emissions in combination with cosmic ray muons. The use of multimodal imaging will allow 3-D reconstructions of the dry storage cask that would be unachievable with any single radiation source. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24374: Effects of Radiolysis on Pertechnetate under Solvent Extraction Conditions, including Tri-Butyl Phosphate | CUNY, Hunter College | $399,624 | The overarching objective of the proposed work is to assess the impact of radiolysis on pertechnetate speciation during tri-butylphosphate (TBP) solvent extractions from the molecular level to macroscale. The research in this project is designed to understand the interplay of radiolysis, degradation product formation, other important redox active metals, and oxidation states of technetium on its speciation and distribution coefficients in solvent extraction processes. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24183: Experimental investigation and development of models and correlations for cladding-to-coolant heat transfer phenomena in transient conditions in support of TREAT and the LWR fleet. | Massachusetts Institute of Technology | $800,000 | Thermal-hydraulics transient heat transfer phenomena of relevance for the safety and the operation of the TREAT and light water reactors will be investigated. The performance of accident tolerant fuel materials during a reactivity initiated accident scenario and post-critical heat flux and reflood scenarios will be elucidated, as well as the development of models and correlations to be integrated into computational tools for the design and safety analysis of nuclear systems. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24666: Wireless Multifunctional Ultrasonic Arrays with Interdigital and Airborne Transducers for Monitoring Leakage and Corrosion Conditions of Welded Dry Storage Canisters | Mississippi State University | $800,000 | This project aims to develop and validate wireless, multifunctional, ultrasonic sensor arrays that enable on-demand, quantitative interrogation and real-time monitoring of both the canister leakage indicators (helium, helium/air mixture, internal pressure, and temperature) and corrosion conditions (free and/or vapor water). The developed arrays will be fully functional, wirelessly powered and communicated, and compact. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24188: Uranium recovery from used nuclear fuel using metal sulfides | Northwestern University | $400,000 | An alternative and original method to recover uranium from spent fuel is proposed. This method will utilize a new type of regenerable sorbent materials with high selectivity in capturing uranium from complex mixtures in acidic solutions, such as those found in used nuclear fuel of high-assay low-enriched uranium. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24225: Characterizing Fuel Response and Quantifying Coolable Geometry of High-Burnup Fuel | Oregon State University | $800,000 | This study seeks to objectively determine, through empirical and numerical means, the actual impact of fuel dispersion in-core after fuel failure and whether high burnup dispersed fuel compromises coolable geometry and long-term cooling. The outcome of this study will yield an objective means of assessing two criteria (coolable geometry and long-term cooling) within the existing regulatory process to comprehensively understand whether it is feasible to increase burnup, while satisfying 10 CFR 50.46. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24288: Innovative Methods for Interrogation of DSC Internal Conditions | Oregon State University | $800,000 | The proposed work takes a two-pronged approach. The team will study techniques involving only external sensors and equipment, which could be deployed on existing dry storage canisters. In addition, small sensors located inside the canister that can be externally powered and read through the canister wall will also be investigated. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24439: Development of Novel Corrosion-Responsive Buffer Materials for Long-Term Immobilization of High-Level Nuclear Waste | Pennsylvania State University | $800,000 | The goal of this project is to develop a novel cementitious buffer material (CBM) for the safe disposal of spent nuclear fuel (SNF). The primary aim is to identify and characterize novel Mg-Al-P CBMs, complete with assessments of their repository stability as well as their transport and immobilization of radionuclides. The secondary aim is to use in-situ UT-EIS monitoring to understand the corrosive failure at the canister-CBM interface and provide long-term performance modeling of SNF packages. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24461: Estimation of low temperature cladding failures during an RIA transient | Pennsylvania State University | $800,000 | Researchers aim to create a multiphysics description of cladding response during a RIA, especially at high burnup, coupling reactor physics, thermal hydraulics and mechanics. The creation of a thermomechanical model in Bison will be the result of this project which can be used to evaluate the likelihood of low temperature cladding failures during a postulated RIA on a typical fuel rod (as these can lead to channel blockage), and thus identify the most important conditions to be studied at TREAT. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24460: Multiscale Modeling and Experiments for Investigating High Burnup LWR Fuel Rod Behavior Under Normal and Transient Conditions | Texas A&M University | $800,000 | The main objective of this work is to achieve a mechanistic understanding of and to develop a predictive model for the fuel rod behavior at high burn-up under both normal and transient conditions. Therefore, this study will provide the nuclear industry with validated, physics-based criteria to fuel fragmentation thresholds and rod mechanical integrity limits. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24388: Redox Chemistry of UO2 under Repository Relevant Conditions in the Presence of Zircaloy and Waste Canister Material | University of California, Irvine | $800,000 | This project will seek to improve understanding of spent nuclear fuel (SNF) corrosion. Hydrothermal experiments of SNF with cladding and waste canister material will give insights into the redox potential formed due to secondary phase formation as consequence of corrosion in a failed canister. The experimentally derived data about secondary phase formation will be utilized for phase relationship analysis to decipher the redox conditions and thus provide source term for performance assessment models of deep geologic repositories. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24006: High-fidelity modeling of fuel-to-coolant thermomechanical transport behaviors under transient conditions | University of Florida | $800,000 | The objective of the proposal is to develop a high-fidelity modeling tool that can capture some of the important phenomena in high burnup UO2 and ATF fuels during transient conditions. The BlueCRAB tool set will be improved and used to analyze TREAT loss of coolant accident experimental results. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24312: Accelerating the development of reliable and robust machine learning-based interatomic potentials for the prediction of molten salt structure and properties | University of Massachusetts Lowell | $400,000 | Machine learning-based interatomic potentials (MLIPs) used in molecular dynamics (MD) can accurately and efficiently predict molten salt properties. However many machine learning-based methods require large training sets, and can fail unpredictably. This project will overcome these challenges by developing a method for efficiently sampling diverse configurations from MD to train reliable and robust neural network potentials, and develop new models for predicting errors in MLIPs. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24697: Dual External Leak Sensing and Monitoring for Dry Storage Canister | University of Nebraska, Lincoln | $800,000 | Researchers aim to develop two complementary external sensing methods to evaluate the integrity of DSC through internal pressure monitoring and helium leakage detection. The proposed diffuse ultrasonic wave method will be able to measure biaxial strains in the canister wall with high sensitivity and minimum temperature effects. An innovative capacitance MEMS sensor will be developed for helium concentration measurement in air based on the extremely low permittivity of helium. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24449: Multi-modal Surface Acoustic Wave Sensing System for Pressure and Temperature monitoring of Spent Fuel Canisters | University of North Texas | $800,000 | University of North Texas (UNT) will collaborate with Oak Ridge National Laboratory (ORNL) and National Energy Technology Laboratory (NETL) to develop a multi-modal wireless passive SAW (Surface Acoustic Wave) sensor array, which are deployed on the outside surface of the canister, to monitor the strain of the canister and thus determine the inside pressure. In addition, the SAW strain sensor could also measure the surface temperature and potentially monitor helium gas leak. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24265: Fragmentation and Thermal Energy Transport of Cr-doped Fuels under Transient Conditions | University of Pittsburgh | $799,999 | This project will focus on multiple aspects of experimental testing and engineering-scale modeling in understanding thermal energy transport from high burnup, fractured/fragmented accident tolerant fuels, establishing a strong scientific basis to fill a critical knowledge data gap for modeling and simulation of transient fuel performance and safety, such as loss of coolant accident, for future integral testing and fuel licensing. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24310: Fusion of Distributed Fiber Optics, Acoustic NDE, and Physics-Based AI for Spent Fuel Monitoring | University of Pittsburgh | $800,000 | The proposal will leverage new concepts in the fusion between fiber optic distributed acoustic sensing and advanced acoustic nondestructive evaluation techniques with artificial intelligence enhanced classification frameworks to quantitatively characterize the state of dry cask storage containers for spent fuel monitoring, externally and non-invasively, without introducing additional risks of failure. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24261: Internal Wireless Sensors for Dry Cask Storage | University of South Carolina | $800,000 | The effort will test the reliability of wireless, internal sensors after exposure to drying and storage conditions. These sensors are used to internally monitor temperature, pressure, and dose. Radiation shielding will also be designed to protect sensors during long-term storage. The effort will develop piezoelectric techniques for miniaturization of optical emission spectroscopy for internal monitoring of gas composition during drying and long-term storage. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24533: Non-destructive Evaluation of Dry Storage Canisters Using Acoustic Sensing | University of Southern California | $800,000 | The objective of this project is to develop a robust non-destructive evaluation (NDE) technique based on acoustic sensing to detect impurity gases in a sealed (welded) dry storage canister (DSC) using only measurements collected on the external surface of the DSC. The method is based on the time-of-flight analysis of acoustic signals propagating through the fill gas of a DSC, which is influenced by the composition, density and temperature of the propagation medium. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-23984: Safety Implications of High Burnup Fuel for a 2-Year PWR Fuel Cycle | University of Tennessee at Knoxville | $800,000 | The objective of this project is to perform safety analysis of high burnup fuel for a Westinghouse 4-Loop Pressurized Water Reactor. The work aims to identify potential opportunities and gaps for high burnup fuel by utilizing both well-established and modern methodologies to model reactor physics, thermal-hydraulics, and plant system-level response that ultimately provide feedback to fuel performance analysis. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-23985: Fuel-to-Coolant Thermomechanical Behaviors Under Transient Conditions | University of Tennessee at Knoxville | $800,000 | This project will enhance the prediction of thermo-mechanical fuel-to-coolant heat transfer under transient conditions by using a coupled analysis and experiment approach. The effort is relevant to both high-burnup (> 62GWd/t) fuel applications and Accident Tolerant Fuel. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24070: Modeling high-burnup LWR fuel behavior under normal operating and transient conditions | University of Tennessee at Knoxville | $800,000 | This project aims to develop a high-burnup light water reactor fuel modeling capability to implement in the BISON code that would enable the accurate fuel rod behavior simulation during normal operation and design basis accidents, as wells as the identification of the rod life-limiting factors. Mechanistic engineering models will be developed for key phenomena, in particular, high burnup structure evolution, fuel fragmentation, and fission gas release. Traditional and accident tolerant fuels will be considered. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24033: Redox Chemistry in Nuclear Materials Storage Matrices under Ambient and Accelerated Aging Conditions | University of Washington | $800,000 | Deep geologic repositories must safely contain hazardous, high-activity nuclear wastes at geologic time-scales. However, such capability is centrally dependent on the element-specific redox chemistry within and at the interface of storage vessels. A comprehensive study of redox chemistry in cements used in long-term storage is proposed and emphasizes: 1) the actual consequences of accelerated aging modalities and 2) the novel use of newly available capabilities in advanced x-ray spectroscopies. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24063: Post-DNB Thermo-mechanical Behavior of Near-term ATF Designs in Simulated Transient Conditions | University of Wisconsin-Madison | $800,000 | The goals of the proposed research are to conduct coupled experimental and modeling investigations of thermo-mechanical performance of coated accident tolerant zirconium alloy claddings with simulated burnup doped fuels under thermal transients to predict complex thermal and mass transport phenomena of near-term Accident Tolerant Fuel designs in accident conditions. Experiments and modeling for understanding both cladding-coolant and fuel-coolant interactions will be performed. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24582: Machine-Learning-Accelerated Molecular Dynamics Approaches for Molten Salts | University of Wisconsin-Madison | $399,477 | New machine learning potential (MLP) approaches and new MLPs to enable rapid prediction of molten salt (FLiBe and Nal-MgCl2 with impurities) properties with near ab initio quantum mechanical accuracy will be developed. Uncertainty quantification with active learning and on-the-fly fitting will greatly accelerate MLP training. This work will support dramatically increased simulation speeds and associated data generation and understanding for molten salts. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24067: Development of Full Understanding of Mechanical-Chemical Coupling in Bentonite THMC processes | Virginia Polytechnic Institute and State University | $800,000 | The central hypothesis is that mechanical stress in an engineered barrier can lead to pressure solution of solid minerals, leading to significant changes in pore water chemistry, which affects bentonite stability, longevity of the waste pack, and dissolution and migration of nuclides. The overall objective of this project is to develop full understanding of the role of pressure solution on pore water chemistry, the implications to large-scale heterogeneity, and THMC processes. | Fuel Cycle R&D | FY2021 | |
| NEUP Project 21-24186: Regenerating Missing Experimental Parameters with Data-Assimilation Methods for MSRE Transient Benchmark Development and Evaluation | Virginia Commonwealth University | $400,000 | The proposed project will regenerate the undocumented basic data from available experimental data of the MSRE using advanced data-assimilation methods to facilitate the whole-loop modeling of the representative MSRE transients, and perform a thorough MSRE transient benchmark evaluation for the IRPhEP handbook. | Nuclear Energy | FY2021 | |
| NEUP Project 21-24630: Integral Benchmark Evaluation of Zero-Power Tests and Multi-Cycle Depletion Experimental Data of TVA WB1 Cycles 1-3 | North Carolina State University | $400,000 | This project proposes to develop an integral benchmark evaluation of available experimental data for zero-power tests and multi-cycle depletion for consistent and comprehensive validation of both novel high-fidelity and traditional multi-physics tools. The benchmark evaluation will be based on operational and measured data from the Pressurized Water Reactor Watts Bar Unit 1 released by Tennessee Valley Authority. | Nuclear Energy | FY2021 | |
| NEUP Project 21-23987: Separate and Multi-Physics Effects IRPhEP Benchmark Evaluation using SNAP Experiments | Georgia Institute of Technology | $400,000 | The proposed project will develop an International Reactor Physics Experiment Evaluation Project (IRPhEP) mulitphysics microreactor benchmark evaluation based on data from the Systems for Nuclear Auxiliary Power (SNAP) program. This work will include systematic assessments of the experimental data with meticulous compilation and documentation, and validation of specific NEAMS tools to model effects that are unique to microreactors technologies. | NEAMS | FY2021 | |
| NEUP Project 21-24194: Implementation of improved quasi-static, time-dependent, multi-physics methodology in Shift | Georgia Institute of Technology | $600,000 | A practical reference calculation route for time-dependent coupled Monte Carlo calculations, using Shift, will be developed. The proposed framework will be tailored to depletion and slowly varying transients, but with the flexibility to perform thermal-hydraulic time-dependent calculations with minimal computational overheads. This method relies on a hybrid-resolution stochastic approach in conjunction with a substep technique. | NEAMS | FY2021 | |
| NEUP Project 21-24078: Material transport model development and integration in the System Analysis Module (SAM) code | Rensselaer Polytechnic Institute | $400,000 | This project proposes to develop and implement models for System Analysis Module, which accurately characterize the sink, source, and interaction terms of key material species that are or may be present in various advanced reactor designs. | NEAMS | FY2021 | |
| NEUP Project 21-24195: Enhancing Yellowjacket for Modeling the Impact of Radiation and Stress on the Corrosion of Molten-Salt-Facing Structural Components | University of Florida | $692,088 | The objective of this project is to add the capability to model the impact of radiation and stress on corrosion to the Yellowjacket code, as well as to use Yellowjacket to create surrogate models that will be added to engineering-scale codes like Grizzly. We will also collect new experimental data for validation that quantifies the impact of stress and radiation on corrosion of 316 stainless steel in molten fluoride salts. | NEAMS | FY2021 | |
| NEUP Project 21-24405: Development of a High-fidelity Flow Boiling Database for Validation of High-void-fraction Flow Regime Models | University of Michigan | $800,000 | The primary objective of this proposed research is to develop a comprehensive, high-resolution, multiphase computational fluid dynamics validation-grade flow boiling data from rod bundle geometry simulating current light water reactor fuel designs by taking advantage of the instrumentation and facility developed by the research team. In addition, the applicability of the data through initial evaluations of selected test cases using Nek-2P boiling closure models will be studied and demonstrated for two-phase flow simulations. | NEAMS | FY2021 | |
| NEUP Project 21-24471: Technical Basis of Microstructure Criteria and Accelerated Testing for Qualifying Additively-manufactured 316H Stainless Steel for High-temperature Cyclic Service | Auburn University | $800,000 | This project seeks to reveal the fundamental relationship for AM 316H SS working at 500-750 C between additively-manufactured microstructures and creep/creep-fatigue properties through a multiscale experimental and modeling approach. The project also seeks to establish the technical basis for the microstructure criteria and accelerated testing method to support near-term nuclear qualification. | RCRD&D | FY2021 | |
| NEUP Project 21-24152: Direct heating of chemical catalysts for hydrogen and fertilizer production using Microreactors | Kansas State University | $799,202 | This proposal presents a novel integration approach to deliver process heat from microreactors by directly heating the catalyst particles from the primary heat transfer fluid in a moving packed bed heat exchanger (MPBHX). In this design, the tube side of the MPBHX can be a heat pipe or primary Helium coolant as in several microreactor designs. The shell side will be moving catalyst particles, which will enter the high temperature chemical reactor upon heating. | RCRD&D | FY2021 | |
| NEUP Project 21-24287: Investigating heat transfer in horizontally oriented HTGR under normal and PCC conditions | Kansas State University | $799,762 | Experimental research will be conducted to understand heat transfer inside the graphite matrix of horizontal microscale High Temperature Gas-cooled Reactors. Existing high temperature test facilities will be used to simulate normal operation and Pressurized Conduction Cooldown. The focus of these experiments is to generate benchmark data under forced and natural convection with coupled multi-mode heat transfer in scaled-down prismatic blocks. | RCRD&D | FY2021 | |
| NEUP Project 21-24104: Thermal Hydraulics Investigation of Horizontally Orientated Layout Micro HTGRs Under Normal Operation and PCC Conditions Using Integrated Advanced Measurement Techniques | Missouri University of Science and Technology | $800,000 | The proposed novel work will make a significant pioneering contribution to advance the knowledge and understanding of horizontal micro-high temperature gas cooled reactors. Quantification of metrics will pertain to convective heat transfer coefficients along the channel and gaps, comparative rates of convective and radiative heat transfer, location of peak temperature and its temporal variation, timescales for onset of natural convection, local gas velocity profiles, gas dispersion, crossflows, and temperature profiles over channel diameter and gap thickness. | RCRD&D | FY2021 | |
| NEUP Project 21-24004: An Open Source, Parallel, and Distributed Web-Based Probabilistic Risk Assessment Platform to Support Real Time Nuclear Power Plant Risk-Informed Operational Decisions | North Carolina State University | $800,000 | The main objective of the proposed work is to develop, demonstrate, and evaluate a probabilistic risk assessment (PRA) software platform needed to address the major challenges of the current legacy PRA tools. This includes better quantification speed, integration of multi-hazard models into traditional PRAs, and model modification/simplification and documentation automation. | RCRD&D | FY2021 | |
| NEUP Project 21-24228: Quantifying the Dynamic and Static Porosity/Microstructure Characteristics of Irradiated Graphite through Multi-technique Experiments and Mesoscale Modeling | North Carolina State University | $800,000 | This project proposes a joint experimental-computational approach to probe and quantify the porosity and microstructure characteristics of irradiated nuclear graphite grades and their influence on dimensional changes and turnaround behavior, as well as mechanical properties. The chief focus will be on quantifying both the static and dynamic porosity and crack characteristics in various graphitic phases through several experimental techniques. | RCRD&D | FY2021 | |
| NEUP Project 21-24247: Multi-scale Effects of Irradiation Damage on Nuclear Graphite Properties | Pennsylvania State University | $800,000 | Irradiation induces microstructural damage in graphite, causing both dimensional and property (stiffness, strength and creep) changes as a function of the displacement damage and temperature. The biggest gap remains is the fundamental deformation mechanisms behind the property changes. Researchers propose to eliminate this gap in knowledge with a comprehensive, multi-scale experimental framework exploiting in-situ transmission electron and X-ray computed tomography. | RCRD&D | FY2021 | |
| NEUP Project 21-23975: Development of Thermal Power Dispatch Simulation Tools for BWR Flexible Plant Operation and Generation | Rensselaer Polytechnic Institute | $800,000 | In the U.S. domestic light water reactor fleet, about one-third of operational nuclear power reactors are boiling water reactors (BWRs). Thermal power extraction technologies to be designed for BWRs will be different from those for pressurized water reactors due to differences in steam generation. This study proposes to investigate the thermal and electric power dispatch and required control algorithms for dynamic heat dispatch of up to 50% of the thermal energy from a BWR plant to a hydrogen plant. | RCRD&D | FY2021 | |
| NEUP Project 21-24111: Experimental Investigations of HTGR Fission Product Transport in Separate-effect Test Facilities Under Prototypical Conditions for Depressurization and Water-ingress Accidents | Texas A&M University | $800,000 | Experimental investigations will be performed for fission product (FP) lift-off, washoff, vaporization from plateout surfaces, and transport of FP at prototypical conditions representing depressurization and water-ingress accidents. Measurements will be performed on existing separate-effect facilities using intrusive and non-intrusive techniques to obtain shear stress, deposition velocity, thermal gradient, and gas impurity for advanced correlations. Modeling will be performed using system and computational fluid dynamics codes. | RCRD&D | FY2021 | |
| NEUP Project 21-24644: High-Resolution Measurements and Advanced Modeling for Design Optimization of Advanced Small Modular Reactor Steam Generators | Texas A&M University | $800,000 | Experiments and simulations will be performed to acquire multi-parameters of pressure drop, heat and mass transfer, and flow-induced vibration (FIV) effect for the design optimization of advanced small modular reactor steam generators (SMR SG). Measurements are performed on existing SMR SG facilities using intrusive/non-intrusive techniques to obtain velocity, temperature, pressure, heat flux, and FIV effects for various geo-dimensions, spacing, pitch angles. Simulations will be performed in StarCCM, Nek5000 and coupling with Diablo | RCRD&D | FY2021 | |
| NEUP Project 21-24332: A Virtual Reality Environment for Human Reliability Assessment in the Context of Physical Security Attacks | The Ohio State University | $800,000 | Recent studies have shown that the physical security workforce accounts for 20% of the entire workforce and, therefore, is responsible for significant operational and maintence costs. To reduce the security staffing, improve performance and reduce threats, modeling and simulation and models of attacker, defender and operator behavior could be employed. This proposal aims to model human behavior using a combination of known human reliability analyses models and experimental evidence from virtual reality experiments. | RCRD&D | FY2021 | |
| NEUP Project 21-24389: High Temperature Electromagnetic Acoustic (EMAT) Transducers for Structural Health Monitoring | University of Cincinnati | $800,000 | The aim of this project is to produce an electromagnetic acoustic transducer (EMAT) technology to enable ultrasonic structural health monitoring at the METL facility and similar high temperature assets. Ultrasonic nondestructive evaluation methods can be used for monitoring a range of damage mechanisms including thermal fatigue and corrosion. The project will seek to establish core design solutions that can be used as the basis of a range of EMAT designs for different applications. | RCRD&D | FY2021 | |
| NEUP Project 21-24380: Probabilistic Validation and Risk Importance Ranking Methodology for Automation Trustworthiness and Transparency in Nuclear Power Plants | University of Illinois at Urbana-Champaign | $800,000 | This project develops a methodology to improve trustworthiness and transparency of automation technologies in nuclear power plants. The proposed methodology will monitor risk emerging from automation processes and rank the criticality of automation factors influencing automation output, plant equipment, and system performance. The feasibility and practicality of the proposed methodology will be demonstrated with two case studies focusing on implementation of nuclear power plant automation technologies. | RCRD&D | FY2021 | |
| NEUP Project 21-24162: Self-powered wireless sensor system for health monitoring of liquid-sodium cooled fast reactors | University of Notre Dame | $800,000 | The goal of this project is to develop self-powered wireless multimodal sensors and instrumentation for health monitoring and diagnosing early-stage materials degradation for high-risk components in liquid-sodium cooled fast reactors. The synergistic and innovative integrations of the multimodal sensor array, wireless communication, and thermoelectric energy harvester have crosscutting benefit for a wide range of advanced reactors. | RCRD&D | FY2021 | |
| NEUP Project 21-24102: High temperature Molten salt reactor pump component development and testing | University of Wisconsin-Madison | $800,000 | This project will provide relevant key information on the tribology of bearing material and components (such as magnets, couplers, ceramic coated wire, and coatings) in high temperature molten salts that will be required in the design of reactor pumps. Investigation of in-service inspection and monitoring of the pump internals will also be addressed in an effort to reduce down time and operation and maintenance costs. | RCRD&D | FY2021 | |
| NEUP Project 21-24226: Cost Reduction of Advanced Integration Heat Exchanger Technology for Micro-Reactors | University of Wisconsin-Madison | $799,713 | Heat exchanger technology is a high-cost component of a micro-reactor system that is also critical to the overall reliability and performance. This project will develop the underlying advanced heat exchanger technology necessary to integrate a micro-reactor with any end-user application, as well as providing internal heat exchange. Economic optimization of the heat exchanger and experimental demonstration of the technology will be accomplished. | RCRD&D | FY2021 | |
| NEUP Project 21-24382: Advanced High-Fluence Low-Flux RPV Mechanical Property Models for Extended Life | University of Wisconsin-Madison | $799,717 | This project will further develop accurate models of the mechanical property changes under life-extension conditions in reactor pressure vessel (RPV) steels using reduced order Avrami models, cluster dynamics, and atomistic methods combined with massive comprehensive databases on irradiated steels. The work will provide models critical to extending the life of U.S. pressurized water reactors, as well as new fundamental insights into flux and fluence effects and sink and precipitate evolution in reactor pressure vessels and related steels. | RCRD&D | FY2021 | |
| NEUP Project 21-24394: Computer vision and machine learning for microstructural qualification | Carnegie Mellon University | $497,518 | Quantifying and understanding microstructure is a key driver for performance-based materials qualification. In this proposal, well-curated data sets of microstructural images will be gathered and computer vision and machine learning will be applied to build quantitative deep learning frameworks to accelerate and enable qualification of nuclear materials based on microstructural features. | Crosscutting Technologies | FY2020 | |
| NEUP Project 21-24156: Experimental thermofluidic validation of TCR fuel elements using distributed temperature and flow sensing | Kansas State University | $798,250 | The overall goal of this project will be to test the performance of 3D printed Transformational Challenge Reactor core geometry parts using existing Helium flow loops and distributed temperature, and velocity sensing systems. Thermal transport capabilities of scaled 3D printed ceramic core will be evaluated experimentally and measurements will be used to qualify computational models. | Crosscutting Technologies | FY2020 | |
| NEUP Project 21-24636: Risk-informed Consequence-driven Physical Protection System Optimization for Microreactor Sites | Texas A&M University | $400,000 | This proposed project will utilize a risk-informed, consequence-driven analysis to develop an approach for "right-sizing" physical protection systems (PPS) for microreactors. The hypothesis presented for this proposal is that the explicit coupling of consequence modeling to PPS design will provide a similar benefit that can be applied prior to reactor construction. | Crosscutting Technologies | FY2020 | |
| NEUP Project 21-24131: Total Mass Accounting in Advanced Liquid Fueled Reactors | The Ohio State University | $400,000 | A total mass determination method for nuclear materials accounting (NMA) in liquid-fueled molten salt reactors will be validated with fuel-bearing salt, mixed with a + radioisotope of known activity, that will be irradiated to reproduce the practical NMA scenario in a molten salt loop. Irradiated fuel salt will be sampled and measured for its mass and activity. The mass-to-activity ratio will be used to calculate the unknown salt mass in the original container. | Crosscutting Technologies | FY2020 | |
| NEUP Project 21-24037: Design and intelligent optimization of the thermal storage and energy distribution for the TerraPower Molten Chloride Fast Reactor in an Integrated Energy System (IES) | University of Tennessee at Knoxville | $800,000 | The objective of this project is to explore the application of advanced reactors within Integrated Energy Systems, use extensive existing data from UIUC for model development and validation, and extend the predictions to larger grids and commercial applications. | Crosscutting Technologies | FY2020 | |
| NEUP Project 21-24522: Targeted Materials Characterization and Testing of Additively Manufactured Metals and Ceramics to Inform Print/Build Data Analytics | University of Texas at San Antonio | $800,000 | A collaborative program between the University of Texas at San Antonio and Boise State University is proposed to supply materials testing and characterization data sets to be leveraged by the TCR program to inform build/print data analytics. With the data provided by the proposing team, correlations among steam oxidation performance, micromechanical properties, chemical composition, local microstructure, and location specific print/build data will be achieved. | Crosscutting Technologies | FY2020 | |
| NEUP Project 21-24431: Location-specific material characterization of LPBF SS316L & IN718 TCR core structural materials | Utah State University | $800,000 | In this proposed work, we will experimentally characterize the spatial variability of the quasi-static (tensile), creep (strength and impression), and creep-fatigue properties as well as the underlying structures (microstructure and defect structures) for LPBF SS316L and IN718 components to be used as training data to the TCR program data-driven model. The resulting correlation will be used to drive the design process for an application as TCR core structural materials. | Crosscutting Technologies | FY2020 | |
| NEUP Project 21-23978: Rapid, Non-Radioactive Methods for Prediction and Quantification of Radiolytic Radical Decomposition Products in Nuclear Separations | Clemson University | $399,999 | High-throughput, non-radioactive, radical assays will be used to determine decomposition of monoamide separations complexants. Radical assay results will be correlated with classic radiolytic damage results to develop predictive models for screening complexant stability. These models will aid in single-stage separations complexant optimization, in the transition from lab-to industrial-scale nuclear waste separations and, ultimately, could yield field tests for radiolytic damage. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24350: Phosphate Mineral and Glass Waste Forms for Advanced Immobilization of Chloride and Fluoride-based Waste Streams | Clemson University | $600,000 | This proposal is intended to develop three waste form options for immobilizing the fluoride-and chloride-salt waste stream in highly durable and easily processable phosphate minerals and glasses, including phosphate apatite ceramic waste forms, phosphate glass waste forms, and phosphate glass-ceramic waste forms with apatite phase. Multiple monolithic waste form samples will be provided to DOE national laboratories for further testing. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24292: Passive multimodal tomography for dry storage casks imaging using passive neutron and gamma dosimetry and cosmic ray muons | Colorado School of Mines | $800,000 | A method for multimodal tomography of dry storage casks will be developed to determine fuel relocation and cladding failures using passive neutrons and gamma emissions in combination with cosmic ray muons. The use of multimodal imaging will allow 3-D reconstructions of the dry storage cask that would be unachievable with any single radiation source. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24374: Effects of Radiolysis on Pertechnetate under Solvent Extraction Conditions, including Tri-Butyl Phosphate | CUNY, Hunter College | $399,624 | The overarching objective of the proposed work is to assess the impact of radiolysis on pertechnetate speciation during tri-butylphosphate (TBP) solvent extractions from the molecular level to macroscale. The research in this project is designed to understand the interplay of radiolysis, degradation product formation, other important redox active metals, and oxidation states of technetium on its speciation and distribution coefficients in solvent extraction processes. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24183: Experimental investigation and development of models and correlations for cladding-to-coolant heat transfer phenomena in transient conditions in support of TREAT and the LWR fleet. | Massachusetts Institute of Technology | $800,000 | Thermal-hydraulics transient heat transfer phenomena of relevance for the safety and the operation of the TREAT and light water reactors will be investigated. The performance of accident tolerant fuel materials during a reactivity initiated accident scenario and post-critical heat flux and reflood scenarios will be elucidated, as well as the development of models and correlations to be integrated into computational tools for the design and safety analysis of nuclear systems. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24666: Wireless Multifunctional Ultrasonic Arrays with Interdigital and Airborne Transducers for Monitoring Leakage and Corrosion Conditions of Welded Dry Storage Canisters | Mississippi State University | $800,000 | This project aims to develop and validate wireless, multifunctional, ultrasonic sensor arrays that enable on-demand, quantitative interrogation and real-time monitoring of both the canister leakage indicators (helium, helium/air mixture, internal pressure, and temperature) and corrosion conditions (free and/or vapor water). The developed arrays will be fully functional, wirelessly powered and communicated, and compact. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24188: Uranium recovery from used nuclear fuel using metal sulfides | Northwestern University | $400,000 | An alternative and original method to recover uranium from spent fuel is proposed. This method will utilize a new type of regenerable sorbent materials with high selectivity in capturing uranium from complex mixtures in acidic solutions, such as those found in used nuclear fuel of high-assay low-enriched uranium. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24225: Characterizing Fuel Response and Quantifying Coolable Geometry of High-Burnup Fuel | Oregon State University | $800,000 | This study seeks to objectively determine, through empirical and numerical means, the actual impact of fuel dispersion in-core after fuel failure and whether high burnup dispersed fuel compromises coolable geometry and long-term cooling. The outcome of this study will yield an objective means of assessing two criteria (coolable geometry and long-term cooling) within the existing regulatory process to comprehensively understand whether it is feasible to increase burnup, while satisfying 10 CFR 50.46. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24288: Innovative Methods for Interrogation of DSC Internal Conditions | Oregon State University | $800,000 | The proposed work takes a two-pronged approach. The team will study techniques involving only external sensors and equipment, which could be deployed on existing dry storage canisters. In addition, small sensors located inside the canister that can be externally powered and read through the canister wall will also be investigated. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24439: Development of Novel Corrosion-Responsive Buffer Materials for Long-Term Immobilization of High-Level Nuclear Waste | Pennsylvania State University | $800,000 | The goal of this project is to develop a novel cementitious buffer material (CBM) for the safe disposal of spent nuclear fuel (SNF). The primary aim is to identify and characterize novel Mg-Al-P CBMs, complete with assessments of their repository stability as well as their transport and immobilization of radionuclides. The secondary aim is to use in-situ UT-EIS monitoring to understand the corrosive failure at the canister-CBM interface and provide long-term performance modeling of SNF packages. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24461: Estimation of low temperature cladding failures during an RIA transient | Pennsylvania State University | $800,000 | Researchers aim to create a multiphysics description of cladding response during a RIA, especially at high burnup, coupling reactor physics, thermal hydraulics and mechanics. The creation of a thermomechanical model in Bison will be the result of this project which can be used to evaluate the likelihood of low temperature cladding failures during a postulated RIA on a typical fuel rod (as these can lead to channel blockage), and thus identify the most important conditions to be studied at TREAT. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24460: Multiscale Modeling and Experiments for Investigating High Burnup LWR Fuel Rod Behavior Under Normal and Transient Conditions | Texas A&M University | $800,000 | The main objective of this work is to achieve a mechanistic understanding of and to develop a predictive model for the fuel rod behavior at high burn-up under both normal and transient conditions. Therefore, this study will provide the nuclear industry with validated, physics-based criteria to fuel fragmentation thresholds and rod mechanical integrity limits. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24388: Redox Chemistry of UO2 under Repository Relevant Conditions in the Presence of Zircaloy and Waste Canister Material | University of California, Irvine | $800,000 | This project will seek to improve understanding of spent nuclear fuel (SNF) corrosion. Hydrothermal experiments of SNF with cladding and waste canister material will give insights into the redox potential formed due to secondary phase formation as consequence of corrosion in a failed canister. The experimentally derived data about secondary phase formation will be utilized for phase relationship analysis to decipher the redox conditions and thus provide source term for performance assessment models of deep geologic repositories. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24006: High-fidelity modeling of fuel-to-coolant thermomechanical transport behaviors under transient conditions | University of Florida | $800,000 | The objective of the proposal is to develop a high-fidelity modeling tool that can capture some of the important phenomena in high burnup UO2 and ATF fuels during transient conditions. The BlueCRAB tool set will be improved and used to analyze TREAT loss of coolant accident experimental results. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24312: Accelerating the development of reliable and robust machine learning-based interatomic potentials for the prediction of molten salt structure and properties | University of Massachusetts Lowell | $400,000 | Machine learning-based interatomic potentials (MLIPs) used in molecular dynamics (MD) can accurately and efficiently predict molten salt properties. However many machine learning-based methods require large training sets, and can fail unpredictably. This project will overcome these challenges by developing a method for efficiently sampling diverse configurations from MD to train reliable and robust neural network potentials, and develop new models for predicting errors in MLIPs. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24697: Dual External Leak Sensing and Monitoring for Dry Storage Canister | University of Nebraska, Lincoln | $800,000 | Researchers aim to develop two complementary external sensing methods to evaluate the integrity of DSC through internal pressure monitoring and helium leakage detection. The proposed diffuse ultrasonic wave method will be able to measure biaxial strains in the canister wall with high sensitivity and minimum temperature effects. An innovative capacitance MEMS sensor will be developed for helium concentration measurement in air based on the extremely low permittivity of helium. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24449: Multi-modal Surface Acoustic Wave Sensing System for Pressure and Temperature monitoring of Spent Fuel Canisters | University of North Texas | $800,000 | University of North Texas (UNT) will collaborate with Oak Ridge National Laboratory (ORNL) and National Energy Technology Laboratory (NETL) to develop a multi-modal wireless passive SAW (Surface Acoustic Wave) sensor array, which are deployed on the outside surface of the canister, to monitor the strain of the canister and thus determine the inside pressure. In addition, the SAW strain sensor could also measure the surface temperature and potentially monitor helium gas leak. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24265: Fragmentation and Thermal Energy Transport of Cr-doped Fuels under Transient Conditions | University of Pittsburgh | $799,999 | This project will focus on multiple aspects of experimental testing and engineering-scale modeling in understanding thermal energy transport from high burnup, fractured/fragmented accident tolerant fuels, establishing a strong scientific basis to fill a critical knowledge data gap for modeling and simulation of transient fuel performance and safety, such as loss of coolant accident, for future integral testing and fuel licensing. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24310: Fusion of Distributed Fiber Optics, Acoustic NDE, and Physics-Based AI for Spent Fuel Monitoring | University of Pittsburgh | $800,000 | The proposal will leverage new concepts in the fusion between fiber optic distributed acoustic sensing and advanced acoustic nondestructive evaluation techniques with artificial intelligence enhanced classification frameworks to quantitatively characterize the state of dry cask storage containers for spent fuel monitoring, externally and non-invasively, without introducing additional risks of failure. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24261: Internal Wireless Sensors for Dry Cask Storage | University of South Carolina | $800,000 | The effort will test the reliability of wireless, internal sensors after exposure to drying and storage conditions. These sensors are used to internally monitor temperature, pressure, and dose. Radiation shielding will also be designed to protect sensors during long-term storage. The effort will develop piezoelectric techniques for miniaturization of optical emission spectroscopy for internal monitoring of gas composition during drying and long-term storage. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24533: Non-destructive Evaluation of Dry Storage Canisters Using Acoustic Sensing | University of Southern California | $800,000 | The objective of this project is to develop a robust non-destructive evaluation (NDE) technique based on acoustic sensing to detect impurity gases in a sealed (welded) dry storage canister (DSC) using only measurements collected on the external surface of the DSC. The method is based on the time-of-flight analysis of acoustic signals propagating through the fill gas of a DSC, which is influenced by the composition, density and temperature of the propagation medium. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-23984: Safety Implications of High Burnup Fuel for a 2-Year PWR Fuel Cycle | University of Tennessee at Knoxville | $800,000 | The objective of this project is to perform safety analysis of high burnup fuel for a Westinghouse 4-Loop Pressurized Water Reactor. The work aims to identify potential opportunities and gaps for high burnup fuel by utilizing both well-established and modern methodologies to model reactor physics, thermal-hydraulics, and plant system-level response that ultimately provide feedback to fuel performance analysis. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-23985: Fuel-to-Coolant Thermomechanical Behaviors Under Transient Conditions | University of Tennessee at Knoxville | $800,000 | This project will enhance the prediction of thermo-mechanical fuel-to-coolant heat transfer under transient conditions by using a coupled analysis and experiment approach. The effort is relevant to both high-burnup (> 62GWd/t) fuel applications and Accident Tolerant Fuel. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24070: Modeling high-burnup LWR fuel behavior under normal operating and transient conditions | University of Tennessee at Knoxville | $800,000 | This project aims to develop a high-burnup light water reactor fuel modeling capability to implement in the BISON code that would enable the accurate fuel rod behavior simulation during normal operation and design basis accidents, as wells as the identification of the rod life-limiting factors. Mechanistic engineering models will be developed for key phenomena, in particular, high burnup structure evolution, fuel fragmentation, and fission gas release. Traditional and accident tolerant fuels will be considered. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24033: Redox Chemistry in Nuclear Materials Storage Matrices under Ambient and Accelerated Aging Conditions | University of Washington | $800,000 | Deep geologic repositories must safely contain hazardous, high-activity nuclear wastes at geologic time-scales. However, such capability is centrally dependent on the element-specific redox chemistry within and at the interface of storage vessels. A comprehensive study of redox chemistry in cements used in long-term storage is proposed and emphasizes: 1) the actual consequences of accelerated aging modalities and 2) the novel use of newly available capabilities in advanced x-ray spectroscopies. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24063: Post-DNB Thermo-mechanical Behavior of Near-term ATF Designs in Simulated Transient Conditions | University of Wisconsin-Madison | $800,000 | The goals of the proposed research are to conduct coupled experimental and modeling investigations of thermo-mechanical performance of coated accident tolerant zirconium alloy claddings with simulated burnup doped fuels under thermal transients to predict complex thermal and mass transport phenomena of near-term Accident Tolerant Fuel designs in accident conditions. Experiments and modeling for understanding both cladding-coolant and fuel-coolant interactions will be performed. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24582: Machine-Learning-Accelerated Molecular Dynamics Approaches for Molten Salts | University of Wisconsin-Madison | $399,477 | New machine learning potential (MLP) approaches and new MLPs to enable rapid prediction of molten salt (FLiBe and Nal-MgCl2 with impurities) properties with near ab initio quantum mechanical accuracy will be developed. Uncertainty quantification with active learning and on-the-fly fitting will greatly accelerate MLP training. This work will support dramatically increased simulation speeds and associated data generation and understanding for molten salts. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-24067: Development of Full Understanding of Mechanical-Chemical Coupling in Bentonite THMC processes | Virginia Polytechnic Institute and State University | $800,000 | The central hypothesis is that mechanical stress in an engineered barrier can lead to pressure solution of solid minerals, leading to significant changes in pore water chemistry, which affects bentonite stability, longevity of the waste pack, and dissolution and migration of nuclides. The overall objective of this project is to develop full understanding of the role of pressure solution on pore water chemistry, the implications to large-scale heterogeneity, and THMC processes. | Fuel Cycle R&D | FY2020 | |
| NEUP Project 21-23987: Separate and Multi-Physics Effects IRPhEP Benchmark Evaluation using SNAP Experiments | Georgia Institute of Technology | $400,000 | The proposed project will develop an International Reactor Physics Experiment Evaluation Project (IRPhEP) mulitphysics microreactor benchmark evaluation based on data from the Systems for Nuclear Auxiliary Power (SNAP) program. This work will include systematic assessments of the experimental data with meticulous compilation and documentation, and validation of specific NEAMS tools to model effects that are unique to microreactors technologies. | Nuclear Energy | FY2020 | |
| NEUP Project 21-24630: Integral Benchmark Evaluation of Zero-Power Tests and Multi-Cycle Depletion Experimental Data of TVA WB1 Cycles 1-3 | North Carolina State University | $400,000 | This project proposes to develop an integral benchmark evaluation of available experimental data for zero-power tests and multi-cycle depletion for consistent and comprehensive validation of both novel high-fidelity and traditional multi-physics tools. The benchmark evaluation will be based on operational and measured data from the Pressurized Water Reactor Watts Bar Unit 1 released by Tennessee Valley Authority. | Nuclear Energy | FY2020 | |
| NEUP Project 21-24186: Regenerating Missing Experimental Parameters with Data-Assimilation Methods for MSRE Transient Benchmark Development and Evaluation | Virginia Commonwealth University | $400,000 | The proposed project will regenerate the undocumented basic data from available experimental data of the MSRE using advanced data-assimilation methods to facilitate the whole-loop modeling of the representative MSRE transients, and perform a thorough MSRE transient benchmark evaluation for the IRPhEP handbook. | Nuclear Energy | FY2020 | |
| NEUP Project 21-24194: Implementation of improved quasi-static, time-dependent, multi-physics methodology in Shift | Georgia Institute of Technology | $600,000 | A practical reference calculation route for time-dependent coupled Monte Carlo calculations, using Shift, will be developed. The proposed framework will be tailored to depletion and slowly varying transients, but with the flexibility to perform thermal-hydraulic time-dependent calculations with minimal computational overheads. This method relies on a hybrid-resolution stochastic approach in conjunction with a substep technique. | NEAMS | FY2020 | |
| NEUP Project 21-24078: Material transport model development and integration in the System Analysis Module (SAM) code | Rensselaer Polytechnic Institute | $400,000 | This project proposes to develop and implement models for System Analysis Module, which accurately characterize the sink, source, and interaction terms of key material species that are or may be present in various advanced reactor designs. | NEAMS | FY2020 | |
| NEUP Project 21-24195: Enhancing Yellowjacket for Modeling the Impact of Radiation and Stress on the Corrosion of Molten-Salt-Facing Structural Components | University of Florida | $692,088 | The objective of this project is to add the capability to model the impact of radiation and stress on corrosion to the Yellowjacket code, as well as to use Yellowjacket to create surrogate models that will be added to engineering-scale codes like Grizzly. We will also collect new experimental data for validation that quantifies the impact of stress and radiation on corrosion of 316 stainless steel in molten fluoride salts. | NEAMS | FY2020 | |
| NEUP Project 21-24405: Development of a High-fidelity Flow Boiling Database for Validation of High-void-fraction Flow Regime Models | University of Michigan | $800,000 | The primary objective of this proposed research is to develop a comprehensive, high-resolution, multiphase computational fluid dynamics validation-grade flow boiling data from rod bundle geometry simulating current light water reactor fuel designs by taking advantage of the instrumentation and facility developed by the research team. In addition, the applicability of the data through initial evaluations of selected test cases using Nek-2P boiling closure models will be studied and demonstrated for two-phase flow simulations. | NEAMS | FY2020 | |
| NEUP Project 21-24471: Technical Basis of Microstructure Criteria and Accelerated Testing for Qualifying Additively-manufactured 316H Stainless Steel for High-temperature Cyclic Service | Auburn University | $800,000 | This project seeks to reveal the fundamental relationship for AM 316H SS working at 500-750 C between additively-manufactured microstructures and creep/creep-fatigue properties through a multiscale experimental and modeling approach. The project also seeks to establish the technical basis for the microstructure criteria and accelerated testing method to support near-term nuclear qualification. | RCRD&D | FY2020 | |
| NEUP Project 21-24152: Direct heating of chemical catalysts for hydrogen and fertilizer production using Microreactors | Kansas State University | $799,202 | This proposal presents a novel integration approach to deliver process heat from microreactors by directly heating the catalyst particles from the primary heat transfer fluid in a moving packed bed heat exchanger (MPBHX). In this design, the tube side of the MPBHX can be a heat pipe or primary Helium coolant as in several microreactor designs. The shell side will be moving catalyst particles, which will enter the high temperature chemical reactor upon heating. | RCRD&D | FY2020 | |
| NEUP Project 21-24287: Investigating heat transfer in horizontally oriented HTGR under normal and PCC conditions | Kansas State University | $799,762 | Experimental research will be conducted to understand heat transfer inside the graphite matrix of horizontal microscale High Temperature Gas-cooled Reactors. Existing high temperature test facilities will be used to simulate normal operation and Pressurized Conduction Cooldown. The focus of these experiments is to generate benchmark data under forced and natural convection with coupled multi-mode heat transfer in scaled-down prismatic blocks. | RCRD&D | FY2020 | |
| NEUP Project 21-24104: Thermal Hydraulics Investigation of Horizontally Orientated Layout Micro HTGRs Under Normal Operation and PCC Conditions Using Integrated Advanced Measurement Techniques | Missouri University of Science and Technology | $800,000 | The proposed novel work will make a significant pioneering contribution to advance the knowledge and understanding of horizontal micro-high temperature gas cooled reactors. Quantification of metrics will pertain to convective heat transfer coefficients along the channel and gaps, comparative rates of convective and radiative heat transfer, location of peak temperature and its temporal variation, timescales for onset of natural convection, local gas velocity profiles, gas dispersion, crossflows, and temperature profiles over channel diameter and gap thickness. | RCRD&D | FY2020 | |
| NEUP Project 21-24004: An Open Source, Parallel, and Distributed Web-Based Probabilistic Risk Assessment Platform to Support Real Time Nuclear Power Plant Risk-Informed Operational Decisions | North Carolina State University | $800,000 | The main objective of the proposed work is to develop, demonstrate, and evaluate a probabilistic risk assessment (PRA) software platform needed to address the major challenges of the current legacy PRA tools. This includes better quantification speed, integration of multi-hazard models into traditional PRAs, and model modification/simplification and documentation automation. | RCRD&D | FY2020 | |
| NEUP Project 21-24228: Quantifying the Dynamic and Static Porosity/Microstructure Characteristics of Irradiated Graphite through Multi-technique Experiments and Mesoscale Modeling | North Carolina State University | $800,000 | This project proposes a joint experimental-computational approach to probe and quantify the porosity and microstructure characteristics of irradiated nuclear graphite grades and their influence on dimensional changes and turnaround behavior, as well as mechanical properties. The chief focus will be on quantifying both the static and dynamic porosity and crack characteristics in various graphitic phases through several experimental techniques. | RCRD&D | FY2020 | |
| NEUP Project 21-24247: Multi-scale Effects of Irradiation Damage on Nuclear Graphite Properties | Pennsylvania State University | $800,000 | Irradiation induces microstructural damage in graphite, causing both dimensional and property (stiffness, strength and creep) changes as a function of the displacement damage and temperature. The biggest gap remains is the fundamental deformation mechanisms behind the property changes. Researchers propose to eliminate this gap in knowledge with a comprehensive, multi-scale experimental framework exploiting in-situ transmission electron and X-ray computed tomography. | RCRD&D | FY2020 | |
| NEUP Project 21-23975: Development of Thermal Power Dispatch Simulation Tools for BWR Flexible Plant Operation and Generation | Rensselaer Polytechnic Institute | $800,000 | In the U.S. domestic light water reactor fleet, about one-third of operational nuclear power reactors are boiling water reactors (BWRs). Thermal power extraction technologies to be designed for BWRs will be different from those for pressurized water reactors due to differences in steam generation. This study proposes to investigate the thermal and electric power dispatch and required control algorithms for dynamic heat dispatch of up to 50% of the thermal energy from a BWR plant to a hydrogen plant. | RCRD&D | FY2020 | |
| NEUP Project 21-24111: Experimental Investigations of HTGR Fission Product Transport in Separate-effect Test Facilities Under Prototypical Conditions for Depressurization and Water-ingress Accidents | Texas A&M University | $800,000 | Experimental investigations will be performed for fission product (FP) lift-off, washoff, vaporization from plateout surfaces, and transport of FP at prototypical conditions representing depressurization and water-ingress accidents. Measurements will be performed on existing separate-effect facilities using intrusive and non-intrusive techniques to obtain shear stress, deposition velocity, thermal gradient, and gas impurity for advanced correlations. Modeling will be performed using system and computational fluid dynamics codes. | RCRD&D | FY2020 | |
| NEUP Project 21-24644: High-Resolution Measurements and Advanced Modeling for Design Optimization of Advanced Small Modular Reactor Steam Generators | Texas A&M University | $800,000 | Experiments and simulations will be performed to acquire multi-parameters of pressure drop, heat and mass transfer, and flow-induced vibration (FIV) effect for the design optimization of advanced small modular reactor steam generators (SMR SG). Measurements are performed on existing SMR SG facilities using intrusive/non-intrusive techniques to obtain velocity, temperature, pressure, heat flux, and FIV effects for various geo-dimensions, spacing, pitch angles. Simulations will be performed in StarCCM, Nek5000 and coupling with Diablo | RCRD&D | FY2020 | |
| NEUP Project 21-24332: A Virtual Reality Environment for Human Reliability Assessment in the Context of Physical Security Attacks | The Ohio State University | $800,000 | Recent studies have shown that the physical security workforce accounts for 20% of the entire workforce and, therefore, is responsible for significant operational and maintence costs. To reduce the security staffing, improve performance and reduce threats, modeling and simulation and models of attacker, defender and operator behavior could be employed. This proposal aims to model human behavior using a combination of known human reliability analyses models and experimental evidence from virtual reality experiments. | RCRD&D | FY2020 | |
| NEUP Project 21-24389: High Temperature Electromagnetic Acoustic (EMAT) Transducers for Structural Health Monitoring | University of Cincinnati | $800,000 | The aim of this project is to produce an electromagnetic acoustic transducer (EMAT) technology to enable ultrasonic structural health monitoring at the METL facility and similar high temperature assets. Ultrasonic nondestructive evaluation methods can be used for monitoring a range of damage mechanisms including thermal fatigue and corrosion. The project will seek to establish core design solutions that can be used as the basis of a range of EMAT designs for different applications. | RCRD&D | FY2020 | |
| NEUP Project 21-24380: Probabilistic Validation and Risk Importance Ranking Methodology for Automation Trustworthiness and Transparency in Nuclear Power Plants | University of Illinois at Urbana-Champaign | $800,000 | This project develops a methodology to improve trustworthiness and transparency of automation technologies in nuclear power plants. The proposed methodology will monitor risk emerging from automation processes and rank the criticality of automation factors influencing automation output, plant equipment, and system performance. The feasibility and practicality of the proposed methodology will be demonstrated with two case studies focusing on implementation of nuclear power plant automation technologies. | RCRD&D | FY2020 | |
| NEUP Project 21-24162: Self-powered wireless sensor system for health monitoring of liquid-sodium cooled fast reactors | University of Notre Dame | $800,000 | The goal of this project is to develop self-powered wireless multimodal sensors and instrumentation for health monitoring and diagnosing early-stage materials degradation for high-risk components in liquid-sodium cooled fast reactors. The synergistic and innovative integrations of the multimodal sensor array, wireless communication, and thermoelectric energy harvester have crosscutting benefit for a wide range of advanced reactors. | RCRD&D | FY2020 | |
| NEUP Project 21-24102: High temperature Molten salt reactor pump component development and testing | University of Wisconsin-Madison | $800,000 | This project will provide relevant key information on the tribology of bearing material and components (such as magnets, couplers, ceramic coated wire, and coatings) in high temperature molten salts that will be required in the design of reactor pumps. Investigation of in-service inspection and monitoring of the pump internals will also be addressed in an effort to reduce down time and operation and maintenance costs. | RCRD&D | FY2020 | |
| NEUP Project 21-24226: Cost Reduction of Advanced Integration Heat Exchanger Technology for Micro-Reactors | University of Wisconsin-Madison | $799,713 | Heat exchanger technology is a high-cost component of a micro-reactor system that is also critical to the overall reliability and performance. This project will develop the underlying advanced heat exchanger technology necessary to integrate a micro-reactor with any end-user application, as well as providing internal heat exchange. Economic optimization of the heat exchanger and experimental demonstration of the technology will be accomplished. | RCRD&D | FY2020 | |
| NEUP Project 21-24382: Advanced High-Fluence Low-Flux RPV Mechanical Property Models for Extended Life | University of Wisconsin-Madison | $799,717 | This project will further develop accurate models of the mechanical property changes under life-extension conditions in reactor pressure vessel (RPV) steels using reduced order Avrami models, cluster dynamics, and atomistic methods combined with massive comprehensive databases on irradiated steels. The work will provide models critical to extending the life of U.S. pressurized water reactors, as well as new fundamental insights into flux and fluence effects and sink and precipitate evolution in reactor pressure vessels and related steels. | RCRD&D | FY2020 | |
| NEUP Project 19-16987: Novel miniature creep tester for virgin and neutron irradiated clad alloys with benchmarked multiscale modeling and simulations | North Carolina State University | $800,000 | This project will develop a miniature creep machine to collect rapid thermal creep and load relaxation data for two selected ferritic alloys under "as-received" and irradiated conditions. Fast and accurate measurements of creep deformation are essential for qualifying new alloys for long term use in current and next generation reactors. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-17150: Speciation and Behavior of Neptunium and Zirconium in Advanced Separation Process | Oregon State University | $800,000 | This project will further develop the understanding of nuclear fuel reprocessing using Co-Decontamination (CoDCon). Radiolytic degradation products of tributylphosphate, nitric acid, redox buffer, masking agent, and water greatly affect the redox speciation, complexation and partitioning of the recycled metals. Fundamental understanding of chemical speciation and partitioning of Neptunium and Zerconium under such conditions is required. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-17395: Modeling and Uncertainty Analysis of MSR Nuclear Material Accounting Methods for Nuclear Safeguards | Pennsylvania State University | $800,000 | This project will model and analyze the limits of detection for the diversion of nuclear materials from a molten salt reactor (MSR) fuel cycle. MSR depletion under a range of uranium and/or plutonium diversion to quantify the resulting differences in salt composition will be evaluated. Sensors will also be investigated to quantify fuel salt contents and correlate the outputs with the reactor models to predict diversion detection. Results will be coupled with robust uncertainty analysis to determine limits of detection. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-16583: Neutron Radiation Effect on Diffusion between Zr (and Zircaloy) and Cr for Accurate Lifetime Prediction of ATF | The Ohio State University | $499,997 | This project will perform systematic diffusion studies on both neutron-irradiated and unirradiated accident tolerant fuel samples to obtain precise diffusion coefficients. This will result in a precise evaluation of the pure neutron irradiation effect on diffusion in these systems and enable accurate life prediction of the accident tolerant fuels. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-17381: High Throughput Assessment of Creep Behavior of Advanced Nuclear Reactor Structural Alloys by Nano/microindentation | University of Minnesota, Twin Cities | $800,000 | This project will develop a high throughput assessment of creep behavior of advanced nuclear reactor structural alloys by nano/microindentation. Experimental datasets will inform polycrystalline deformation models to predict material response over a variety of creep conditions. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-16549: Thermal Conductivity Measurement of Irradiated Metallic Fuel Using TREAT | University of Pittsburgh | $500,000 | This project intends to provide accurate thermal conductivity and thermal diffusivity data with microstructure characterization of metallic (U-Pu-Zr) fuel as a function of burnup and attain fundamental understanding of the thermal conductivity of the irradiated fuel to inform and validate computational models. This will be accomplished using an innovative thermal wave technique in the Transient Reactor Test Facility at the Idaho National Laboratory, with the Minimal Activation Reusable Capsule Holder. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-17002: Remote Laser-based Nondestructive Evaluation for Post-Irradiation Examination of ATF Cladding | University of South Carolina | $800,000 | To enable advanced nondestructive characterization techniques for light water reactor fuels that can be applied to the cladding coating, a remote nondestructive evaluation post irradiation inspection approach will be developed. This technique will measure the cladding coating layer thickness and detect defects within the cladding such as corrosion, micro-cracking and delamination. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-17276: Radiation-Induced Swelling in Advanced Nuclear Fuel | University of Tennessee at Knoxville | $799,989 | The microstructural evolution of advanced fuel (uranium carbide and uranium nitride) under fission-fragment type radiation has not been studied and remains unclear. This project will utilize advanced synchrotron X-ray characterization using microgram samples to obtain detailed nanoscale information on radiation-induced volumetric swelling and microstrain. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-16848: Metal-Functionalized Membranes for Radioiodine Capture | University of Utah | $799,031 | This proposed research will investigate high-surface area (>300 m2/g) metal-functionalized membranes. These novel chemically durable and mechanically robust membranes are formed using an aqueous fabrication process, which results in an interconnected porosity that is highly controllable, providing hierarchical structures ranging from the nano-to micrometer-scales. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-17350: Development and Experimental Validation of Pitting and SCC Models for Welded Stainless Steel Dry Storage Containers Exposed to Atmospheric Environments | University of Virginia | $799,027 | The specific goals of this project are to: (a) validate the maximum pit size model for dry storage canister relevant corrosion conditions as well as quantifying the effects of limited cathodic current on stress corrosion cracking (SCC) kinetics, (b) demonstrate a means to quantitatively rank the risk of SCC based on measurable parameters, (c) perform probabilistic predictions of SCC growth, and (d) validate the model predictions. | Fuel Cycle R&D | FY2019 | |
| NEUP Project 19-16879: Proactive Hybrid Nuclear with Load Forecasting | Brigham Young University | $799,933 | This project develops new capabilities of design and dispatch optimization of nuclear hybrid energy systems (NHES) in the "Risk Analysis Virtual Environment (RAVEN)" modelling software. Blended (physics-based and data-driven) machine learning will be applied to forecast demand and production of thermal and electrical loads. Two experimental case studies are proposed to test the software developments with a lab-scale thermal energy storage and with a large district energy system. As a final step, the software developments will be generalized to other NHES. | Nuclear Energy | FY2019 | |
| NEUP Project 19-17461: Development and Evaluation of Neutron Thermalization Integral Benchmarks for Advanced Reactor Applications | North Carolina State University | $400,000 | This project will develop integral benchmarks that aim to examine thermal neutron scattering data for graphite (ideal and nuclear), light water, and molten salt. The benchmark evaluations will be contributed to the International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhEP) database. | Nuclear Energy | FY2019 | |
| NEUP Project 19-16739: Improvements of Nuclear Data Evaluations for Lead Isotopes in Support of Next Generation Lead-Cooled Fast Systems | Rensselaer Polytechnic Institute | $400,000 | The objective of this project is to improve the accuracy of neutronics simulation of lead-based systems by improving the nuclear data of lead isotopes. The nuclear data for lead will be reevaluated with emphasis of the intermediate and fast energy regions that are required by reactor applications currently sought by several industrial entities. The deliverables of this project are new lead isotopes evaluations that will be candidates for inclusion in a future Evaluated Nuclear Data Library (ENDF) release. | Nuclear Energy | FY2019 | |
| NEUP Project 19-17219: Using Integral Benchmark Experiments to Improve Differential Nuclear Data Evaluations | University of New Mexico | $400,000 | This project will use the results of integral benchmark experiment to inform differential nuclear data evaluations and improve the predictive capability of modeling and simulation (M&S) tools. This goal will be accomplished by developing capabilities to assess the sensitivity of integral benchmark results to evaluated nuclear data parameters, and by using data assimilation tools to directly adjust the evaluated data parameters and improve the accuracy of M&S tools. | Nuclear Energy | FY2019 | |
| NEUP Project 19-16743: Paths Forward for Nuclear Energy: Using a Nationwide Post-Stratified Hierarchical Model to Facilitate Matching of New Nuclear Technologies to Receptive Host Communities | University of Oklahoma | $390,393 | This project will enable deployment of advanced nuclear technologies by developing a model, and an accompanying web-based tool that can be utilized by technology entrepreneurs, that identifies public support for siting new nuclear technologies at very local spatial scales across the US. The model will employ hierarchically structured, post stratified analysis of the largest US pooled-time series dataset on geocoded public support for nuclear technologies. | Nuclear Energy | FY2019 | |
| NEUP Project 19-16995: A Cyber-Attack Detection Platform for Cyber Security of Digital Instrumentation and Control Systems | University of Tennessee at Knoxville | $799,995 | The proposed research will develop a robust cyber-attack detection system (CADS) for monitoring digital instrumentation and control (I&C) systems. The project will develop a robust research tool for evaluating cyber defense of digital I&C systems and provide a framework for a cyber-attack detection system that provides continuous assurance of the security of digital I&C systems in nuclear power plants (NPPs). | Nuclear Energy | FY2019 | |
| NEUP Project 19-17327: Multi-Timescale Nuclear-Renewable Hybrid Energy Systems Operations to Improve Electricity System Resilience, Reliability, and Economic Efficiency | University of Texas at Dallas | $800,000 | The overarching objective of this project is to develop a multi-timescale nuclear-renewable hybrid energy systems (N-R HESs) operations framework to provide different types of grid products. The project will model and analyze the capabilities of N-R HESs to provide power grid services at different timescales ranging from seconds to days, such as day-ahead unit commitment, flexible ramping (5-45 minutes), regulation reserves (1-5 minutes), and frequency response (less than seconds). | Nuclear Energy | FY2019 | |
| NEUP Project 19-17192: The Design and Investigation of Novel Mechanical Filters for Molten Salt Reactors | Abilene Christian University | $762,246 | Researchers will develop a novel mechanical filtration system. The project will include the collection of filter media performance data and filter regeneration performance data for a novel sintered nickel-based filter prototype. The project will also provide a filter design that facilitates remote filter removal, cooling, replacement, and assay of fissile material hold-up in the filter media. | RCRD&D | FY2019 | |
| NEUP Project 19-16980: Determining the Effects of Neutron Irradiation on the Structural Integrity of Additively Manufactured Heat Exchangers for Very Small Modular Reactor Applications | Auburn University | $400,000 | Researchers will determine how to best use laser-powder bed fusion additive manufacturing methods for generating radiation-resistant channel/pore-embedded structures from Inconel (alloy 625 or 718) nickel-based superalloys for special purpose reactor (i.e. very small modular reactor) heat exchangers. | RCRD&D | FY2019 | |
| NEUP Project 19-17413: Validated, Multi-Scale Molecular Dynamics Simulations to Predict the Thermophysical Properties of Molten Salts Containing Fuel, Fission, and Corrosion Products | Brigham Young University | $798,291 | Researchers will use first principles molecular dynamics (FPMD) simulations on molten salts containing impurities including fuel, fission products, and corrosion products. These will be used to develop a classical molecular dynamics (CMD) potential. CMD will then be used to predict properties for a wide variety of salt compositions and temperatures, and physical property measurements will be performed to validate those predictions. Property correlations will be developed from this data. | RCRD&D | FY2019 | |
| NEUP Project 19-17183: Mixing of helium with air in reactor cavities following a pipe break in HTGRs | City College of New York | $800,000 | Researchers will conduct separate effects tests to obtain experimental validation data on mixing of helium and air in reactor building cavities during and after blowdown in HTGRs. Air and helium concentrations, and gas mixture velocity and temperature fields will be measured in simulated reactor cavities. An existing helium flow loop will be used as the source of high pressure/high temperature helium for injection into the cavities and different break configurations will be experimentally investigated. | RCRD&D | FY2019 | |
| NEUP Project 19-16391: GuArDIAN: General Active Sensing for conDItion AssessmeNt | Duke University | $800,000 | Researchers will develop a dependable, autonomous or semi-autonomous (i.e. low human involvement), and minimally disruptive framework for monitoring equipment and components in nuclear reactors. The project will develop GUARDIAN; a robust active sensing framework through the integration of model-based inference and mobile actuating/sensing robots. | RCRD&D | FY2019 | |
| NEUP Project 19-17251: Measuring Mechanical Properties of Select Layers and Layer Interfaces of TRISO Particles via Micromachining and In-Microscope Tensile Testing | Idaho State University | $799,815 | Researchers will characterize the strength of TRISO-coated particle layers and interfaces using FIB micro-machining and in-TEM tensile testing. Tensile test samples from coating layers of (1) unirradiated surrogate (fuel) TRISO particles, (2) unirradiated fueled TRISO particles and (3) irradiated fueled TRISO particles will be studied. Results of this project will both benefit and leverage the AGR Program. | RCRD&D | FY2019 | |
| NEUP Project 19-17185: Demonstrating Reactor Autonomous Control Framework using Graphite Exponential Pile | Massachusetts Institute of Technology | $400,000 | Researchers will demonstrate a detection-prediction-feedback framework for nuclear system autonomous control. It will adopt multiple detector channels to enable control feedback to spatially dependent perturbations. It will also utilize high-fidelity solutions trained surrogate models for real-time prediction and decision-making. In addition to the method development, the proposal will entail a first-of-a-kind engineering demonstration using the MIT Graphite Exponential Pile (MGEP). | RCRD&D | FY2019 | |
| NEUP Project 19-16754: Simultaneous Corrosion/Irradiation Testing in Lead and Lead-Bismuth Eutectic: The Radiation Decelerated Corrosion Hypothesis | Massachusetts Institute of Technology | $762,823 | Researchers will test candidate FeCrSi and F/M alloys in a new, simultaneous corrosion/radiation facility to try to identify an alloy that will satisfy all requirements for Lead Fast Reactor structural materials. Microstructural characterization, mechanical property testing, and corrosion tests, both during irradiation and following ion/He pre-conditioning, will assess how irradiation affects corrosion, potentially slowing it. | RCRD&D | FY2019 | |
| NEUP Project 19-17173: Ni-based ODS alloys for Molten Salt Reactors | North Carolina State University | $800,000 | The objective of this work is to (i) propose and develop a new Nickel (Ni) based Oxide Dispersion-Strengthened (ODS) alloy that can be used for structural applications in Molten Salt Reactor (MSR) and other nuclear reactor harsh environments, (ii) to demonstrate that its high temperature mechanical properties are adequate for MSR operating temperatures, (iii) to demonstrate its radiation damage resistance through ion irradiation testing and (iv) to demonstrate its improved corrosion resistance in MSR environment. | RCRD&D | FY2019 | |
| NEUP Project 19-17037: Investigation of HTGR Reactor Building Response to a Break in Primary Coolant Boundary | Purdue University | $799,832 | Researchers will perform a series of experiments to simulate HTGR reactor building response due to a break in the primary coolant boundary in a well-scaled test facility to obtain spatial distribution of oxygen concentration, perform analysis of the whole system response with 1-D thermal hydraulics codes and use CFD to make detailed localized predictions. The tests will be carried out with different locations and sizes of the breaks to create various vent and flow paths in the reactor cavity. | RCRD&D | FY2019 | |
| NEUP Project 19-17093: Integrating Multi-modal Microscopy Techniques and the MOSAIC Simulation Environment to Assess Changes in the Physical Properties and Chemical Durability of Concrete Following Radiation Exposure | University of California, Los Angeles | $800,000 | Researchers will develop unprecedented multi-modal imaging methodologies that integrate multiple microscopy techniques. The team will develop a generalizable protocol for quantifying the changes in physical properties and chemical durability of concrete and concrete constituents (minerals and aggregates) following radiation exposure. The imaging analyses will be input into the MOSAIC framework to reveal the nature and extent of degradation that is expected to result. The outcomes offer insights that are needed to enable and inform second license renewals. | RCRD&D | FY2019 | |
| NEUP Project 19-17167: Atomistically Informed and Experimentally Validated Model for Helium Bubble Growth in Welded Irradiated Metals | University of Florida | $797,861 | Researchers will construct a validated computational model for He bubble growth on grain boundaries in irradiated Fe-Ni-Cr microstructures, including intergranular fracture, as a function of material conditions and welding heat input. This model will be based on the phase-field methodology, leveraging numerical solvers in the MOOSE simulation platform, with critical inputs and validation provided by both atomic-level simulations and experiments. | RCRD&D | FY2019 | |
| NEUP Project 19-16909: Learning-based Computational Study of the Thermodynamic, Structural, and Dynamic Properties of Molten Salts at the Atomic and Electronic Scale and Experimental Validations | University of Illinois at Urbana-Champaign | $800,000 | Researchers will obtain the thermophysical, thermochemical, and transport properties, construct the phase diagrams, and build empirical physical models of molten salts that are relevant to Molten Salt Reactors (MSRs) with first-principles accuracy using molecular dynamics simulations driven by machine-learned high-dimensional neural network potentials combined with neutron/X-ray scattering and thermodynamic experimental validations. | RCRD&D | FY2019 | |
| NEUP Project 19-16298: I-PRA Decision-Making Algorithm and Computational Platform to Develop Safe and Cost-Effective Strategies for the Deployment of New Technologies | University of Illinois at Urbana-Champaign | $800,000 | Researchers will develop an integrated probabilistic risk assessment decision-making algorithm to support risk-and-cost-informed decision-making related to the deployment of new technologies. The project will enhance the financial analysis module and the challenging interface of social and technical systems to advance the algorithm. The project will conduct a case study for evaluating the safety impact and cost-effectiveness of FLEX strategies to support operational flexibility. | RCRD&D | FY2019 | |
| NEUP Project 19-16802: Evaluation of Semi-Autonomous Passive Control Systems for HTGR Type Special Purpose Reactors | University of Michigan | $400,000 | Researchers will investigate the use of variable flow controllers and a variable reflector as passive or semi-autonomous reactivity control mechanisms for multi-module HTGR type special purpose reactors. This applies to the commercially developed special purpose reactor concepts from HolosGen. The incorporation of these systems will reduce the movable parts count and enable more robust load follow capabilities over broader power ranges and local and global reactivity control. | RCRD&D | FY2019 | |
| NEUP Project 19-17467: Understanding the Speciation and Molecular Structure of Molten Salts Using Laboratory and Synchrotron based In Situ Experimental Techniques and Predictive Modeling | University of Nevada, Reno | $800,000 | Researchers will develop a methodology to accurately determine the structure and speciation of the molten salt electrolyte using laboratory-based spectroscopic techniques (Raman and UV-Vis-NIR) and synchrotron-based (scattering and absorption) techniques, in combination with computational modeling. | RCRD&D | FY2019 | |
| NEUP Project 19-17231: Prevention of Common Fault-Trigger Combinations for Qualification of Digital Instrumentation and Control Technology | University of Tennessee at Knoxville | $800,000 | Researchers will provide an effective design evaluation approach based on prevention of concurrent triggering conditions to eliminate common-cause failures (CCF) and enable qualification of digital I&C technology for application in nuclear plant modernization. The research involves classifying commonality among digital devices, categorizing faults and triggering conditions, determining fault-trigger relationships, and defining preventive design measures to resolve the potential for CCF. | RCRD&D | FY2019 | |
| NEUP Project 19-17087: Economic Risk-Informed Maintenance Planning and Asset Management | University of Tennessee at Knoxville | $800,000 | Researchers will provide a holistic framework for cost-minimizing risk-informed maintenance planning, including inspection. They will develop a two-tier framework that coarsely minimizes the total maintenance cost during the remaining normal operating cycle and uses the outputs of the first model to maximize the financial impact of these activities in the short term. | RCRD&D | FY2019 | |
| NEUP Project 19-16811: Liquid Metal-cooled Fast Reactor Instrumentation Technology Development | University of Wisconsin-Madison | $800,000 | Researchers will explore three different areas that will help to improve commercialization of SFRs and to aid in testing for the VTR. These include: 1. Advancement in understanding of low prandtl number heat transfer 2. Testing of compact heat exchangers for use with sodium 3. Development of in pool submersible flow meters. | RCRD&D | FY2019 | |
| NEUP Project 19-16954: Innovative In-Situ Analysis and Quantification of Corrosion and Erosion of 316 Stainless Steel in Molten Chloride Salt Flow Loops | University of Wisconsin-Madison | $800,000 | Researchers will use a thin-layer activation technique for the first time in molten salts, on 316H samples placed in natural convection and forced flow loops. The individual and synergistic effects of corrosion, irradiation and thermo-mechanical treatments will be evaluated in-situ to predict component service lifetimes and design limits. The effects of molten chloride flow velocity will also be assessed. | RCRD&D | FY2019 | |
| NEUP Project 19-17168: Fuel Salt Sampling and Enriching System Technology Development | Vanderbilt University | $799,989 | Researchers will combine insights from the Molten Salt Reactor Experiment with decades of advancements in applicable technologies into an enhanced Sampler Enricher (SE) concept to develop and test a flexible, reliable, and workable design. The prototype will then be tested in an existing salt loop. | RCRD&D | FY2019 | |
| NEUP Project 18-15345: Multiphysics Degradation Processes, and Their Mitigation, in Engineered and Geological Bariers: Experiments and Simulation | Duke University | $800,000.00 | This project will focus on filling the gaps in understanding of mechanisms of a series of degradation processes (thermal, hydric, geo-chemical, and transport processes phenomena) potentially affecting geo-materials used in repositories. The objectives of the work are to better recognize the conditions leading to preferential paths of radionuclide transport and rock weakening, and to build mathematical models and implement them into existing codes to predict material degradation and develop strategies to reduce the adverse consequences. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15043: Integration of Nuclear Material Accounting Data and Process Monitoring Data for Improvement on Detection Probability in Safeguarding Electrochemical Processing Facilities | Oregon State University | $800,000.00 | The goal of this project is to further studies on fusion of process monitoring (PM) data and nuclear material accounting (NMA) data. PM data, which includes monitoring by various types of equipment (radiation detectors, cameras, voltage, current sensors), can supplement NMA data to help improve safeguards. For aqueous-based reprocessing facilities, it is reported that PM, integrated with traditional NMA, has a high-detection probability for specific diversions. For electrochemical reprocessing, preliminary studies have shown that PM data can support traditional NMA by providing a basis to estimate some of the in-processing nuclear material inventories. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15148: Recovery of Rare-Earth Elements (Nd, Gd, Sm) in Oxide Wasteform Using Liquid Metals (Bi, Sn) | Pennsylvania State University | $800,000.00 | This project investigates a new approach for recovering rare-earth (RE) fission products (Nd, Gd, and Sm) from molten chlorine salts using liquid metal (Bi and Sn) electrodes. The research aids molten salt recycling by converting the RE products into chloride-free RE oxides, which could be incorporated into conventional glass/ceramic waste forms. Successful outcomes of the project include advanced separation of fission products from molten salts with better control of chemical selectivity and high-recovery yield. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15103: Microstructure-Based Benchmarking for Nano/Microscale Tension and Ductility Testing of Irradiated Steels | Purdue University | $800,000.00 | The objective of this project is to standardize methods for nano/micro-scale tensile and ductility testing of irradiated Fe-Cr steels, through microstructure-based benchmarking. The study will investigate key process parameters for TEM in situ tension and ductility testing. Coupling experimental studies with multiscale models, the research will identify the approaches that provide consistent deformation mechanisms between the nano/micro-scale and macro-scale tests, from which standard practices will be obtained. The primary project outcome will be a set of recommended guidelines for nano/microscale mechanical testing, which will lead to unprecedented reductions in the time and cost for qualifying materials for in-reactor service and to ensure consistency of methods and validity of results. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15559: Cold Spray Repair & Mitigation of Stress Corrosion Cracks in Spent Nuclear Fuel Dry Storage Canisters | Purdue University | $799,982.00 | This goal of this project is to demonstrate cold spray repair and mitigation of chloride-induced stress corrosion cracks (SCC) and pits in stainless steel dry storage canisters. The research will optimize the repair process and gain a scientifically informed understanding of SCC mechanisms. The outcome is to further develop cold spray as an attractive solution for the repair of existing SCC and mitigation of potential SCC necessary to ensure long-term integrity, security, and regulatory compliance of spent nuclear fuel storage. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15596: Capture of Organic Iodides from Vessel Off-Gas Streams | Syracuse University | $799,548.00 | This project will study the capture of radioactive organoiodides from off-gas streams produced during nuclear fuel reprocessing by conducting adsorption experiments using a selected silver adsorbents. Multifaceted simulation adsorption models will be developed to assist in the design of necessary capture systems for off-gas streams. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15585: Impact of Coupled Gas Migration and Thermo-hydro-mechanical Processes on the Performance of Repositories for High Level Nuclear Waste | Texas A&M University | $608,375.00 | The main goal of this project is to better understand the possible effect of gas migration (particularly through discontinuities) on the performance and long-term behavior of engineered barrier systems (EBS) envisaged for the isolation of high-level radioactive waste (HLW). Specific outcomes of this study will be an improved understanding of the role of gas migration and discontinuities in the performance of HLW disposals, with the underlying aim to improve design of EBS used for HLW. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15531: Repair and Mitigation of Chloride-Induced Pitting and Chloride-Induced Stress Corrosion Cracking in Used Nuclear Fuel Dry Cask Canister Materials | The Ohio State University | $800,000.00 | This project will evaluate and develop a set of tools to repair and mitigate chloride-induced pitting and stress corrosion cracking in stainless steel nuclear fuel canisters. Advanced processes, including low temperature friction stir welding and cold spray deposition, will be evaluated according to various criteria, such as corrosion performance. In addition, technologies that have not yet been evaluated for UNF applications, including vaporizing foil actuator welding and soldering will be assessed. The two most promising technologies will selected for further development and comprehensive study. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-14912: Bridging the Length Scales on Mechanical Property Evaluation | University of California, Berkeley | $800,000.00 | This project combines experimental and modeling methods to gain a comprehensive approach for addressing scaling effects on small-scale mechanical testing. Multiscale experiments, together with modeling on reactor-relevant and model alloys, will provide better understanding of appropriate scaling relationships. The study aims to gain fundamental understanding of plasticity interactions with specific strength-determining features, such as precipitates and grain boundaries. The goal of this work is to provide the basis to add small-scale mechanical testing in the toolbox for nuclear materials research. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-14911: Understanding of degradation of SiC/SiC materials in nuclear systems and development of mitigation strategies | University of California, Berkeley | $800,000.00 | This project investigates the best possible coatings to prevent SiCf/SiCm corrosion in LWR environments. The research features a computational and experimental rapid screening approach for numerous coating compositions. The work includes autoclave exposure of rapid screening coupons in prototypical environments in combination with thermodynamic modeling (CALPHAD) and Finite Element Methods (FEM). Small-scale mechanical testing, together with thermal cycling and FEM modeling, will provide guidance on the ideal coating system design. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15701: Time-dependent THMC Properties and Microstructural Evolution of Damage Rocks in Excavation Damage Zone | University of Colorado, Boulder | $799,978.00 | The proposed project focuses on the geomechanical aspects of modeling by addressing the time-dependent evolution of rock microstructure and its coupling with the THC processes that are of first-order importance to the stability and the isolation performance of repositories. The research will delineate an integrated experimental, theoretical and numerical strategy in assessing the evolution EDZ over time and its implication on the long-term migration of hazardous species. These results will enhance the confidence of the predicted long-term performance of repositories, which helps to move forward the goal of one-million-year isolation of high-level nuclear wastes. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15381: Multiaxial Failure Envelopes and Uncertainty Quantification of Nuclear-Grade SiCf/SiC Woven Ceramic Matrix Tubular Composites | University of Florida | $800,000.00 | This project proposes to develop a comprehensive experimental and computational approach for determining constitutive relations and multiaxial failure envelopes of nuclear-grade continuous silicon fiber (SiCf) and SiC matrix woven tubular composites. The result of this work can be adopted in industry for design refinement, optimization of performance under the desired operating conditions, and reliable prediction of failure under unforeseen accidental scenarios. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15496: Formation of Zeolites Responsible for Waste Glass Rate Acceleration: An Experimental and Computational Study for Understanding Thermodynamic and Kinetic Processes | University of Houston | $800,000.00 | Through experimental and computational studies, this project will expose the factors governing zeolite crystallization and their role in Stage III dissolution of radionuclide-containing glass waste forms generated in advanced nuclear fuel cycles. The overall goal of this project is to understand the formation of zeolite phases in order to develop process control methods to suppress Stage III dissolution. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-14998: Novel Processes for Capture of Radioactive Iodine Species from Vessel Off-Gas Streams | University of Idaho | $800,000.00 | The goal of this project is to develop a comprehensive understanding of the sorption system performance and effectiveness for capture of radioiodine species present in the off-gas streams from the used nuclear fuel (UNF) recycling operations, focusing particularly on the organic iodine species. The dynamic sorption experimentation and theoretical modeling will offer fundamental insights on the mechanism enabling the design and prediction the control system performance. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15261: Friction Stir Based Repair Welding of Dry Storage Canisters and Mitigation Strategies: Effect of Engineered Barrier Layer on Environmental Degradation | University of Idaho | $800,000.00 | The project goal is to apply friction stir based repair and mitigation technique for eliminating failure associated with pitting and stress corrosion cracking in dry storage canisters for spent fuels. The goal of these activities is to obtain a fundamental understanding of the processing-structure-properties correlations. This work will contribute to the development of a crack repair/mitigation strategy based on friction stir technology that can be efficiently implemented for spent fuel dry storage casks, which will enhance safety and reliability of these systems. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15263: X-ray Studies of Interfacial Molecular Complexes in ALSEP Back-Extraction | University of Illinois at Chicago | $800,000.00 | This project will use synchrotron X-rays to characterize the interfacial molecular complexes (of extractants and radiologically derived impurities, complexants, buffers, and metal ions) formed during the Actinide-Lanthanide Separation Process (ALSEP) back-extraction. This work addresses the critical knowledge gap of slow stripping kinetics in ALSEP, as well as the influence of radiolytic degradation products. The outcome of the project will be a molecular-level understanding of the role of different components in the interfacial mechanism of back-extraction in the ALSEP process, therefore leading to development of more efficient and faster metal stripping relevant to the separation of actinides from lanthanides in the nuclear fuel cycle. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15030: Mechanistic Understanding of Radiolytically Assisted Hydrothermal Corrosion of SiC in LWR Coolant Environments | University of Michigan | $800,000.00 | The objective of this project is to develop a mechanistic understanding of the hydrothermal corrosion behavior of monolithic SiC and SiC/SiC composites in LWR environment under the influence of water radiolysis products and radiation damage. Complementary atomistic simulations will be carried out to determine the rate controlling mechanisms for dissolution under different water chemistries and in the presence of radiation. Activation energies and kinetic rates will be calculated directly from these simulations and compared to experimentally fitted values. The dissolution rate constants determined and validated in this integrated experimental and modeling approach will allow predictions of long-term SiC corrosion behavior. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-14999: Probabilistic Failure Criterion of SiC/SiC Composites Under Multi-Axial Loading | University of Minnesota, Twin Cities | $800,000.00 | This project aims to develop a probabilistic failure criterion of SiC/SiC composites under multi-axial loading and to incorporate the criterion into a reliability analysis of the structural integrity of LWR SiC/SiC fuel cladding. This research will be anchored by a seamless integration of novel experimental and analytical tools, which will lead to a robust methodology for dependable analysis of SiC/SiC composite structures for LWR fuel cladding, as well as other nuclear applications. The resulting model will be experimentally validated and applied to analyze the reliability of LWR SiC/SiC fuel cladding. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15502: Reducing Uncertainty in Radionuclide Transport Prediction Using Multiple Environmental Tracers | University of Montana | $724,906.00 | In this project, direct modeling of multiple environmental tracers will be used to improve predictions of radionuclide transport in a shallow alluvial aquifer discharge. The research will take advantage of recent theoretical developments considering the use of environmental tracers, and advances in high-performance reactive flow and transport models, to obtain the maximum information on the transport system. The goal is to develop a new methodology to characterize natural reactive flow and transport systems, reduce predictive uncertainty in radionuclide transport simulations, determine the maximum information content of the tracer suite, and optimize future groundwater characterization efforts. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15578: Computational and Experimental Investigation of Thermal-Mechanical-Chemical Mechanisms of High-burnup Spent Nuclear Fuel (SNF) Processes at Elevated Temperatures and Degradation Behavior in Geologic Repositories | University of Nevada, Las Vegas | $800,000.00 | The overarching goal of this project is to use combined computational and experimental research and development activities to enhance understanding of the mechanisms and thermal-mechanical-chemical (TMC) parameters controlling the instant release fraction (IRF) and matrix dissolution of high-burnup (HB; burnup > 45 GWd/MTU) spent nuclear fuels (SNFs) and the subsequent formation, stability, and phase transformations of HB SNF alteration products under long-term storage and geological disposal conditions (e.g., high-temperature storage,-radiolysis). The results of this research will be used to enhance the mechanistic detail of process models to reduce uncertainty in, and improve the technical bases of, safety cases and performance assessment analyses. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15439: Radiolytic Dissolution Rate of Silicon Carbide | University of Notre Dame | $400,000.00 | This project seeks to develop a matrix of dissolution rates for high-purity SiC material, using intense electron beam irradiation, and to measure the products of dissolution (silicic acid and CO2 (or CO)) in the water downstream of the irradiation zone. The objective is to determine the rate of SiC dissolution and gather sufficient insight about its mechanism in LWRs, so that the use of SiC/SiC composite materials for accident tolerant fuel cladding can proceed with confidence. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15061: Development of an MC&A Toolbox for Liquid-fueled Molten Salt Reactors with Online Reprocessing | University of Tennessee at Knoxville | $799,207.00 | The purpose of this project is to develop a toolbox of swappable mass flow modules for liquid-fueled molten salt reactor (MSR) systems for the purposes of evaluating material control & accountancy measurement techniques. When combined together, these modules enable modeling of the time-dependent mass flows for a variety of MSR variants. The test platform will consist of a toolbox of independent process modules representing discrete physical units, each with its own self-contained physics responsive to the input mass flow, along with appropriate measurement models that can be coupled to key flow points. These dynamic physical signatures would allow testing of the viability and efficacy of potential accountancy techniques under the full range of reactor operating conditions. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15307: A Novel and Flexible Approach for Converting LWR UNF Fuel Into Forms That Can Be Used to Fuel a Variety of Gen-IV Reactors | University of Tennessee at Knoxville | $400,000.00 | This project will investigate the chemical decladding and the digestion of whole MOX-based fuel rods, using thionyl chloride and surrogate materials. Digesting entire LWR fuel assemblies results in product streams that include pure decontaminated ZrCl4; pure UCl4; and a stream containing TRU/FPs, as well as alloying metals (as chloride salts). The objectives of this project are to provide a new, highly efficient protocol for the transformation of used nuclear fuel into useful components and to effectively contain a concentrated stream of highly radioactive materials for appropriate handling. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15459: Reduced Diffusion and Enhanced Retention of Multiple Radionuclides from Pore Structure Studies of Barrier Materials for Enhanced Repository Performance | University of Texas at Arlington | $567,831.00 | The project seeks to better understand and quantify the pore structure (geometry and topology) and pore connectivity of porous media and its emergent effect on diffusion and retention of various radionuclides in barrier materials. The anticipated outcome of the project will be to more accurately evaluate the performance of geological repositories. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15649: Benchmarking Microscale Ductility Measurements | University of Utah | $776,669.00 | The objectives of this project are to establish best practices for obtaining tensile microscale ductility measurements and to validate methodologies for comparing them to macroscale ductility measurements. Anticipated outcomes of the project are: 1) measurement of grain and sub-grain localization processes micro and macroscales; 2) establishment of best practices for microtensile experimentation; 3) identification of statistically significant relationships between specimen geometry, microstructure variables and mechanical behavior; 4) modified phenomenological elongation-based ductility models to enable direct upscaling of ductility measurements from microscale to macroscopic. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15003: Advanced Coating and Surface Modification Technologies for SiC-SiC Composite for Hydrothermal Corrosion Protection in LWR | University of Wisconsin-Madison | $799,990.00 | This project focuses on the development of coatings and surface modification approaches for hydrothermal corrosion protection of SiC-SiC composite in normal LWR operation environments. Innovative surface treatment recipes will be explored using processes including, interfacial stitching to improve adhesion, multi-layered structures to improve ductility, and compositions and structures resulting from thermal treatments. The surface treatment concepts involve corrosion resistant metallic and ceramic materials, and are amenable to industrial scalability for the cladding application. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15332: Low-Force Solid-State Technologies for Mitigation of Stress Corrosion Cracking in Dry Storage Canisters | University of Wisconsin-Madison | $800,000.00 | This project will focus on evaluating and developing two technologies used for field mitigation and repair of stress corrosion cracking (SCC): 1) additive friction stir welding; and 2) cold spray deposition. The work involves developing low-force, low-heat input solid state technologies to lessen and repair SCC in stainless steel canisters for used nuclear fuel (UNF). This outcome of the study will inform feasibility of using the two technologies to conduct on-site field repairs. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-14913: The Role of Temperature on Non-Darcian Flows in Engineered Clay Barriers | Virginia Polytechnic Institute and State University | $800,000.00 | This project intends to accomplish three tasks: 1) to develop a predictive model to facilitate experimental data interpretation and provide mechanistic insights into the role of temperature on non-Darcian flows in low-permeability engineered clay barriers; 2) conduct experiments to unravel the role of temperature on the threshold gradient of non-Darcian flow in both saturated and unsaturated bentonite; and 3) use molecular dynamics (MD) simulation to improve fundamental understanding. The experimental data, associated with the MD simulation, will provide valuable information to improve fundamental understanding and scientific knowledge with respect to the temperature dependence of threshold gradient in non-Darcian flows, because very limited experimental data for saturated flow and no experimental data for unsaturated flow are available. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-14815: C-SiOC-SiC Coated Particle Fuels for Advanced Nuclear Reactors | Virginia Polytechnic Institute and State University | $400,000.00 | This project will study a new concept for nuclear fuel encapsulation using an amorphous SiOC plus carbon system as the inner coating and nanocrystalline SiC plus minor carbon as the outer coating for nuclear fuel kernel particles. The outcomes of this work are: 1) new directions and possible replacement guidance for current nuclear fuel materials in operation; 2) new fuel materials for future nuclear reactor material design and development; 3) nuclear composite microstructure evolution and performance degradation understanding; 4) screening tools to guide future nuclear fuel material activities; and 5) mechanisms of nuclear fuel material evolution and degradation and effective strategies to mitigate/reduce undesirable fuel behaviors. | Fuel Cycle R&D | FY2018 | |
| NEUP Project 18-15226: An Evaluated, Transient Experiment based on Simultaneous, 3-D Neutron-Flux and Temperature Measurements | Kansas State University | $399,972.00 | This project will evaluate existing and near-term experimental data for inclusion in the International Reactor Physics Experiment Evaluation Project (IRPhEP) handbook. The data to be evaluated include compositions from a recent fuel replacement as part of an LEU conversion, a number of critical, fresh-fuel configurations, fuel temperature measurements at fresh-fuel configurations, and records from nearly a decade of operation. The proposed work would lead to a first-of-a-kind evaluation of transient, spatially-dependent reaction rates. | Nuclear Energy | FY2018 | |
| NEUP Project CFA-18-15773: Evaluation of the Thermal Scattering Law for Advanced Reactor Neutron Moderators and Reflectors | North Carolina State University | $398,821.00 | The objective of this project is to narrow the nuclear data gap for advanced nuclear reactors that are driven by thermal neutrons. This includes concepts such as gas-cooled high-temperature reactors and molten salt or salt-cooled high temperature reactors. The generated data TSL libraries will be provided in EDNF File 7 format to the National Nuclear Data Center (NDDC) to immediately include in beta releases of the ENDF/B libraries and to consider for the future release of ENDF/B-VIII.1. | Nuclear Energy | FY2018 | |
| NEUP Project 18-15602: Modeling and Experimental Verification of Thermal Energy Storage Systems to Enable Load Following Capability for Nuclear Reactors | University of Idaho | $761,640.00 | This project purposes to integrate new thermal energy storage (TES) models, developed in Modelica, with ongoing nuclear-renewable hybrid energy systems (NRHES) modeling efforts, in order to evaluate economic potential and advantages of new process designs over baseload electricity production. The computational phase of this project includes developing mathematical and physics-based TES models, which could later be translated to Modelica and integrated with existing NRHES components. The testing and optimization would be conducted using RAVEN. A techno-economic analysis will be performed to evaluate the compatibility of the newly formed integration, as well as to quantify its feasibility and economic benefits. The experimental aspect is focused on the development of scaled TES systems, which serve as verification for the Modelica models and allow system testing upon being integrated with DETAIL. | Nuclear Energy | FY2018 | |
| NEUP Project 18-14963: Development of Nuclear Hybrid Energy Systems: Temperature Amplification through Chemical Heat Pumps for Industrial Applications | University of Idaho | $800,000.00 | The overall goal of this project is to develop and demonstrate, through modeling and experimental investigations, temperature amplification capabilities of a chemical heat pump (CHP) system that can be coupled to a conventional light water reactor or a near-term small modular reactor. The outcomes would include nuclear hybrid energy system architecture containing a CHP, experimental data on the CHP performance, and dynamic model of the system, validated through experimentation, which could be used for scale-up and design. | Nuclear Energy | FY2018 | |
| NEUP Project 18-15008: Development of Thermal Inelastic Scattering Covariance Data Capabilities with Demonstration of Light Water Evaluation | University of Michigan | $400,000.00 | The goal of this project is to produce a format for covariance data for inelastic thermal neutron scattering data for moderators in the ENDF format. To demonstrate the viability of this new format, an evaluation of the covariance data for thermal scattering in light water in this format will be produced, along with the capabilities to generate the files and test their efficacy. A capability for calculating sensitivity coefficients using multigroup methods to the fundamental physics parameters governing light-water scattering will be developed to facilitate identifying nuclear data needs related to thermal scattering. | Nuclear Energy | FY2018 | |
| NEUP Project 18-15056: Model-Based Diagnostics and Mitigation of Cyber Threats | University of Michigan | $800,000.00 | This project intends to develop a toolkit for modeling digital instrumentation and control (I&C) systems for nuclear power plants so that the consequences of cyber-attacks on I&C systems may conveniently be modeled using nuclear plant simulation software. The results of the toolkit-based models, the corresponding responses, and the performance of the diagnostic schemes will be tested on a virtual control room driven by a plant simulator. | Nuclear Energy | FY2018 | |
| NEUP Project 18-15055: NICSim: Nuclear Instrumentation and Control Simulation for Evaluating Response to Cyber-attacks | University of New Mexico | $799,945.00 | The objective of the project is to develop a Nuclear Instrumentation and Control Simulation (NICSim) platform with a novel emulytics capability to simulate control systems and components in nuclear power plants. The outcome of this work would be a first-in-class emulytics platform with an associated documentation and library of physical models of components that could be used by analysts and designers to assess the resilience and cybersecurity risks of different control system designs for a wide range of power plants. | Nuclear Energy | FY2018 | |
| NEUP Project 18-15324: Validation of Pressure Relaxation Coefficient in RELAP-7 Seven-Equation Model | George Washington University | $800,000.00 | This project aims to validate the Seven-Equation model in RELAP-7 by: 1) measuring velocity and pressure in each phase and the interface as well as return to equilibrium in fast transients with high-speed non-intrusive laser diagnostics in canonical experiments; 2) complementing experimental data with a multiscale computational approach, including a 3D proprietary direct numerical solver; and 3) validating RELAP-7 with a combination of experimental data and first-principle simulations. This combination would provide unique and complete datasets to validate RELAP-7 with high confidence and offer a new class of experimental and numerical tools. | NEAMS | FY2018 | |
| NEUP Project CFA-18-15104: Demonstration of Utilization of High-fidelity NEAMS Tools to Inform the Improved Use of Conventional Tools within the NEAMS Workbench on the NEA/OECD C5G7-TD Benchmark | North Carolina State University | $800,000.00 | The goal of this project is to demonstrate the utilization of high-fidelity Nuclear Energy Advanced Modeling and Simulation (NEAMS) tools (PROTEUS, Nek5000, and BISON) to inform the improved use of conventional tools (DIF-3D, CTF, and CTFFuel) within the NEAMS Workbench on the NEA/OECD C5G7-TD benchmark. This would result in more accurate predictions of safety parameters and margins, which is important for both safety and performance improvements of the nuclear power plants being currently operated and built. The developed Workbench-based framework will also assist end users to apply high-fidelity simulations to inform lower-order models for the design, analysis, and licensing of advanced nuclear systems. | NEAMS | FY2018 | |
| NEUP Project 18-14741: Demonstration of a Methodology for Direct Validation of MARMOT Irradiation-Induced Microstructural Evolution and Physical Property Models Using U-10Zr | Texas A&M University | $500,000.00 | The objective of this project is to demonstrate, for the first time, a methodology that enables the direct validation of microstructural evolution models for fuel in MARMOT, and the direct correlation of changes in physical properties with specific irradiation-induced microstructural features. Properly implementing this methodology will result in rapid development of MARMOT mesoscale models. | NEAMS | FY2018 | |
| NEUP Project 18-15520: Accurate and Efficient Parametric Model-Order Reduction for Turbulent Thermal Transport | University of Illinois at Urbana-Champaign | $800,000.00 | The project objective is to develop reduced-order models (ROMs) that will improve accuracy of LMR system-level analysis with low overhead. These new models will systematically mine high-fidelity DNS, LES, or uRANS simulations to construct low-order dynamical systems that can couple with a systems analysis code, such as the SAM code being developed under NEAMS. These simulations provide useful data and will be made available to the scientific community, and the overall effort will contribute to more efficient LMR conceptual design studies and licensing. | NEAMS | FY2018 | |
| NEUP Project 18-15484: A Novel High Fidelity Continuous-energy tTansport Tool for Efficient FHR Transient Calculations | Georgia Institute of Technology | $800,000.00 | The objective of the project is to develop a high-fidelity continuous energy (CE) transport tool for efficient transient calculations in fluoride salt-cooled high-temperature reactors with prismatic core/fuel assembly design. This will be accomplished by extending the high-fidelity 3-D continuous energy coarse mesh radiation transport (COMET) code with formidable computational speed to solve transient problems in FHRs with accurate thermal hydraulic feedback. The new capability would enable plant system codes to perform analyses necessary to address complex technical design, regulatory, reactor safety, and economic hurdles prior to construction. | RCRD&D | FY2018 | |
| NEUP Project 18-15093: Determination of Molecular Structure and Dynamics of Molten Salts by Advanced Neutron and X-ray Scattering Measurements and Computer Modeling | Massachusetts Institute of Technology | $800,000.00 | This project will seek detailed knowledge about molecular structure and dynamics of molten salts to inform the design of new molten-salt reactors. A combination of advanced neutron and x-ray scattering and ab initio molecular dynamics simulations will be used to model the ionic-cluster structure of the fluid and solubility of impurities. Machine learning will be applied to regress from simulations and experiments in order to develop the model and predict chemical potentials as a function of composition and temperature. | RCRD&D | FY2018 | |
| NEUP Project 18-15171: Oxidation Behavior of Silicon Carbide and Graphitic Materials | Missouri University of Science and Technology | $800,000.00 | The objectives of this project are to determine the oxidation behavior of silicon carbide and graphitic materials in oxygen and/or moisture, to accurately measure the kinetic parameters of oxidation, to ascertain the oxidation mechanisms in relation to the microstructures, to determine the effect of irradiation on oxidation behavior, and to provide data and input to the safety analysis of high-temperature gas reactors under air and moisture ingress accident conditions. | RCRD&D | FY2018 | |
| NEUP Project 18-15276: Coping Time and Cost Analysis of Accident Tolerant Plant Design based on Dynamic PRA Methodology | Rensselaer Polytechnic Institute | $800,000.00 | This project will evaluate the failure modes of accident tolerant fuel ATF candidates to understand the different failure characteristics. The research aims to obtain a response surface of coping time by investigating the various uncertainties of accident mitigation in PWR and BWR reactors. These outputs will aid the decision making process on the implementation of ATF and FLEX to existing LWR plants from the perspective of risk reduction and economic feasibility. | RCRD&D | FY2018 | |
| NEUP Project 18-15270: Innovative Use of Accident Tolerant Fuels (ATF) with the RCIC System to Enhance Passive Safety of Commercial LWRs | Texas A&M University | $748,000.00 | The overarching objectives of this project are to: 1) demonstrate new operational strategies with the combined use of Accident Tolerant Fuels (ATF) and the Reactor Core Isolation Cooling (RCIC) System to increase the passive safety capabilities of current Boiling Water Reactors (BWRs) in delaying or preventing core damage; and 2) pursue the delay of containment venting until after a 72-hour coping period through new BWR Suppression Pool mixing procedures. The research will use both simulation and experimental data to validate the objectives. The work has the potential to increase the ability of existing nuclear power plants to passively respond to beyond design basis events using existing equipment and without changes to the plants. | RCRD&D | FY2018 | |
| NEUP Project 18-15346: Big Data For Operation and Maintenance Cost Reduction | The Ohio State University | $800,000.00 | This project will develop a first-of-a-kind framework for integrating Big Data capability into the daily activities of our current fleet of nuclear power plants. This research will mainly focus on incorporating the wide range of data heterogeneities in nuclear power plants into an integrated Big Data Analytics capability. The primary end product of this work will be a Big Data framework that is capable of dealing with the large volume and heterogeneity of the data found in nuclear power plants to extract timely and valuable information on equipment performance and to enable optimization of plant operation and maintenance based on the extracted information. | RCRD&D | FY2018 | |
| NEUP Project 18-15065: in situ Measurement and Validation of Uranium Molten Salt Properties at Operationally Relevant Temperatures | University of Connecticut | $799,979.00 | This project proposes to use advanced spectroscopic and scattering methods to provide information at the atomic and molecular scale. The research will use synchrotron-based x-ray absorption fine structure (XAFS) spectroscopy and Raman spectroscopy, at operationally relevant temperatures, to measure the local and intermediate structure as well as speciation of chloride fuel salts (NaCl, ZrCl, UCl3) for fast-spectrum applications and fluoride fuel salts ( 7 LiF, UF4) primarily for thermal spectrum applications This approach is expected to generate theories and concepts that would allow models to predict behavior, and develop the means for in situ monitoring. | RCRD&D | FY2018 | |
| NEUP Project 18-15058: High-resolution Experiments for Extended LOFC and Steam Ingress Accidents in HTGRs | University of Michigan | $800,000.00 | The objective of this project is to better understand key phenomena in high-temperature gas-cooled reactors relevant to steam ingress and loss of forced circulation (LOFC) accidents. Specifically, the research will: 1) experimentally investigate, using an existing integral-effect test facility with some improvements, the steam-ingress accident caused by a postulated steam generator tube rupture initiating event; 2) carry out integral-effect tests for the extended LOFC accident to study the establishment of global natural circulation flow in the primary loop; 3) design, based on a scaling analysis, and construct a separate-effect test facility to study the complex helium flows in the core and hot plenum during the extended LOFC accident; and 4) perform detailed, high-resolution, separate-effects experiments using the results obtained as boundary/initial conditions. | RCRD&D | FY2018 | |
| NEUP Project 18-15471: Integral Experimental Investigation of Radioisotope Retention in Flowing Lead for the Mechanistic Source Term Evaluation of Lead Cooled Fast Reactor | University of New Mexico | $800,000.00 | The purpose of this project is to experimentally investigate the integral effects of radioisotope interactions with liquid lead to support the following technical goals: 1) evaluating the mechanistic source term of the Lead-cooled Fast Reactor (LFR); 2) developing a universal integral effect test methodology for liquid metal source term evaluations; and 3) establishing a basis for the comparison of radioisotope retention between lead and sodium. This aim of the research is to advance the LFR licensing pathway by establishing the phenomenological foundation of the interaction between fission products and liquid lead. | RCRD&D | FY2018 | |
| NEUP Project 18-15153: Understanding Molten Salt Chemistry Relevant to Advanced Molten Salt Reactors through Complementary Synthesis, Spectroscopy, and Modeling | University of Tennessee at Knoxville | $800,000.00 | The goal of the proposed research is to understand molten salt chemistry relevant to advanced molten salt reactors through complementary synthesis, spectroscopy, and modeling. Through complementary synthetic, spectroscopic, and computational efforts, the aim is to achieve atomistic and molecular-level understanding of liquid structure, coordination geometry, chemical bonding, and reactivity of novel molten salt melts relevant to advanced molten reactor designs. | RCRD&D | FY2018 | |
| NEUP Project 18-15111: Improving Nuclear Power Plant Efficiency Through Data Analytics | University of Tennessee at Knoxville | $799,727.00 | This project aims to develop and provide data analytics solutions to improve nuclear power plan economic efficiency by utilizing empirical models to integrate disparate data sources while providing uncertainty estimates to quantify risk and support decisions. The outcomes will enhance the technical and economic competitiveness by enabling advanced monitoring of critical assets, improving the operating capability of the existing fleet, and helping achieve enhancements in organizational effectiveness. Additionally, the research would provide an agile and modular data analytic framework that would have high commercialization value and supports the industry-wide drive towards digital innovation. | RCRD&D | FY2018 | |
| NEUP Project 18-14846: Development of Corrosion Resistant Coatings and Liners for Structural Materials for Liquid Fueled Molten Salts Reactors | University of Wisconsin-Madison | $800,000.00 | The goal of the proposed research is to develop corrosion-resistant coatings and liners for structural materials for use in fuel dissolved molten salt environment for future Molten Salt Reactors (MSRs). Innovative, but industrially scalable, surface cladding approaches are proposed to lead to promising surface and interfacial compositions. The processes themselves are commercial, and have high technology readiness levels, and consequently would facilitate the accelerated developments of MSRs. | RCRD&D | FY2018 | |
| NEUP Project 18-15280: Advanced Alloy Innovations for Structural Components of Molten Salt Reactors | University of Wisconsin-Madison | $796,792.00 | The goal of the proposed research is to develop and evaluate specific advanced metallic alloys for structural components in fluoride salt-cooled molten salt reactors (MSRs). The research will investigate four categories of metallic alloys: advanced Ni-based; radiation damage tolerant high entropy; refractory Mo-based, and compositionally-graded, designed for high-surface corrosion resistance and good bulk strength. Additionally, the propensity for radiation embrittlement, as well as weldability, of the alloys will be evaluated. | RCRD&D | FY2018 | |
| NEUP Project 18-14957: Big Data Analytics Solutions to Improve Nuclear Power Plant Efficiency: Online Monitoring, Visualization, Prognosis, and Maintenance Decision Making | University of Wisconsin-Madison | $797,820.00 | The overarching goal of this project is to significantly advance the ability to assess equipment condition and predict the remaining useful life to support optimal maintenance decision making in nuclear power plants. This research will work toward accomplishing and establishing a modern set of data-driven modeling, online monitoring, visualization, prognosis, and operation decision-making methodologies to address the significant opportunities and challenges arising from the emerging data-rich environment in nuclear plants. The potential impact of the work is significant and transformative and could deliver important advances in productivity with reduced unscheduled downtime and improved equipment performance. | RCRD&D | FY2018 | |
| NEUP Project 18-15097: Oxidation Study of High Temperature Gas-Cooled Reactor TRISO Fuels at Accidental Conditions | Virginia Polytechnic Institute and State University | $800,000.00 | This project is to study the oxidation behaviors of TRISO fuels during accidental air and water vapor ingress conditions. The work focuses on the oxidation and burn-off of the graphite fuel matrix and oxidation of the TRISO fuel SiC layer at high-temperature accidental states in the presence of air and/or water vapor. It will include both unirradiated and irradiated graphite fuel matrix and simulated fuel particles with the SiC layer. | RCRD&D | FY2018 |
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 | |
|---|---|---|---|---|---|---|
| Understanding PM-HIP Interparticle Evolution and its Influence on Fracture Toughness in Alumina-Forming Steels | Purdue University | $1,100,000 | This project aims to understand how interparticle evolution during hot isostatic pressing (HIP) influences fracture toughness of Al-bearing steels. The team will use a series of interrupted HIP experiments with phase field models to understand the formation mechanisms of interparticle defects during HIP of alumina-forming austenitic (AFA) stainless steels and FeCrAl steels, and the influence of these defects on fracture behavior. | Document | Advanced Manufacturing Technologies | FY2024 |
| Multiscale high-throughput experiment/modeling approach to understanding creep behavior in Additively Manufactured reactor steels | University of Minnesota, Twin Cities | $1,043,271 | This project proposes to develop a predictive capability for processing-microstructure-property correlations in additive manufactured microstructures utilizing a multiscale approach encompassing bulk creep tests, miniaturized tensile testing, and a high-throughput, indentation based, cost-effective method for elevated temperature mechanical mapping of additively manufactured 316H Stainless Steel, Grade 91, and Titanium-Zirconium-Molybdenum (TZM) alloys. | Document | Advanced Manufacturing Technologies | FY2024 |
| Hi-fidelity characterization of molten salt-graphite pore interactions through experiments and embedded modeling | North Carolina State University | $1,100,000 | We propose a suite of fuel salt (FLiBe + U) infiltration experiments (University of Michigan-UM) followed by X-ray computed tomography, XCT (NCSU), in-situ mechanical property evaluation with scanning electron microscopy (NCSU) and high fidelity data analytics and modeling (NCSU/Leeds) along with complimentary porosimetry measurements (ORNL) and XPS analysis at University of Manchester (UoM). Three graphite grades are selected in this project: NBG-18, IG-110 and POCO: ZXF-5Q. | Document | Advanced Nuclear Materials | FY2024 |
| Assessing molten salt corrosion resistance of stainless steel 316H in nuclear reactor environments | North Carolina State University | $1,100,000 | The proposed goal is to leverage a blend of innovative molten salt corrosion experiments and cutting-edge characterization techniques to advance our understanding of molten salt corrosion in both commercial and additively manufactured (AM) stainless steel (SS) 316H, particularly under radiation or stress environments. | Document | Advanced Nuclear Materials | FY2024 |
| Polymer-Derived C-SiC Coatings on Kernel Particles for Advanced Nuclear Reactors | University of Alabama at Birmingham | $1,100,000 | This program is to use a polymer-derived ceramic approach to develop C-SiC/ZrC coatings on ZrO2 kernel substitute particles. We aim to create new fuel encapsulation materials in replacement of the coatings on fuel kernel particles, including the TRISO layers, for advanced reactors, conduct ion irradiation testing of the new materials for nuclear performance evaluation, and carry out detailed microstructure and composition characterization to assess the C-SiC/ZrC coated fuel particle behaviors. | Document | Advanced Nuclear Materials | FY2024 |
| Sorbent regeneration, recycling, and transformation: A transformative approach to iodine capture and immobilization | University of Nevada, Reno | $1,000,000 | The project will focus on the development of materials and processes for regeneration and recycling of sorbents, and the transformation of iodine-loaded sorbents into waste forms. A combination of computational and experimental studies will be conducted to understand (a) how the components in a primary off-gas stream interact with the sorbent, (b) how this off-gas stream affects the regeneration lifetime, and (c) low-temperature binders and processing paths that leads to durable waste forms. | Document | Advanced Nuclear Materials | FY2024 |
| Developing place-based understandings of respectful community engagement for consent-based siting | University of Michigan | $1,100,000 | Through this project we seek to develop (1) guiding principles for respectful community engagement-to support consent-based siting-empirically rooted in the lived experiences of Native Communities; (2) metrics and indicators of consent; and (3) a generative AI tool to facilitate community-based storytelling of the past and imagining of the future to visualize how nuclear infrastructures have and could in the future alter community landscapes. | Document | Consent-based Siting for SNF Management | FY2024 |
| Informing Consent-Based Siting of a Consolidated Interim Storage Facility (CISF): Examining Public Engagement Through History and Evaluation of Prior & Current Outreach Results | Vanderbilt University | $1,000,000 | We will use two phases of research to assist NE in understanding factors that influence the quality and extent of public engagement needed to address different people and communities seeking to make decisions regarding the siting of a CISF. Supporting NE's the consent-based siting process we have developed an accelerated 2-year schedule, focusing on three geographic areas of the US: IL, TX & NM and the area served by the TVA/Duke Power Ñeach contain multiple SNF storage facilities. | Document | Consent-based Siting for SNF Management | FY2024 |
| Accident Tolerant Fuels to Support Power Uprates in LWRs | University of Wisconsin-Madison | $1,100,000 | This project will demonstrate that power uprates higher than the current state of operation can be reached using accident tolerant fuels in light water reactors while not exceeding reactor safety margins during normal operation and accidents. We will analyze it considering fuel enriched up to 10% and peak rod average burnup up to 75GWd/tU concerning reactor physics, thermal-hydraulics, reactor safety, and economics. Considerations will be made in consultation with the named industry advisory board. | Document | Existing Plant Optimization | FY2024 |
| Comparative study of three-dimensional microstructural imaging and thermal conductivity evolution of irradiated solid and annular U-Zr fuels | Massachusetts Institute of Technology | $1,000,000 | Uranium-zirconium (U-Zr) annular metallic fuel holds the promise to simultaneously increase sodium fast reactor (SFR) core uranium loading and reduce peak cladding temperatures, thus greatly improving fuel performance. However, key convolved fuel degradation mechanisms during irradiation at temperature threaten to hold back its real-world applicability, requiring more detailed understanding to both predict U-Zr fuel performance and suggest improvements. | Document | Fuels | FY2024 |
| Mechanistic study and modeling of fission gas release in UO2 and doped UO2 | Oregon State University | $1,000,000 | The objective of this project is to enhance the safety and performance of light water reactors and other advanced reactor designs by gaining a fundamental understanding of fast gas reactor mechanisms and developing mechanistic models for UO2 and doped UO2 fuels under HBU and transient conditions. | Document | Fuels | FY2024 |
| Anisotropic Thermal Properties of SiC-SiC Cladding: Method Development & Characterization | University of Pittsburgh | $1,000,000 | We propose to develop a high-temperature nondestructive thermal conductivity (k) measurement system coupled with validated multiscale models to accurately determine the anisotropic thermal conductivity of SiC-SiC composite cladding tubes. The multiscale measurement and modeling results benefit both DOE ATF programs as well as providing a fundamental understanding of how the microstructure of the composite leads to its anisotropic properties. | Document | Fuels | FY2024 |
| Understanding the Performance of SiC-SiCf Composite Cladding Architectures with Cr Coating in Normal Operating and Accident Conditions in LWRs and Advanced Reactors | University of Wisconsin-Madison | $1,000,000 | The project will focus on investigating the impact of Cr-coating on the SiC-SiCf composite cladding of various architectures under normal operating and accident conditions in light water reactors and advanced reactors for the safe and economic deployment of SiC cladding. Cr-coating will provide protection from high-temperature corrosion and better hermeticity under accident conditions. The performance of the claddings will be evaluated through the corrosion test, reflood test, burst test, and non-destructive evaluation(NDE). | Document | Fuels | FY2024 |
| Developing critical insights on the effects of Mo on a' precipitation and dislocation loop formation in FeCrAl alloys | University of Wisconsin-Madison | $1,000,000 | This project aims at developing a mechanistic understanding on the effects of Mo on a' precipitation and dislocation loop formation in FeCrAl alloys in thermal and irradiation conditions and turns it into a set of design principles guiding further optimization, by integrating atomistic simulations, CALPHAD modeling, thermal aging, proton irradiation, and advanced characterization. The material discoveries will be generalized to other solutes other than Mo. | Document | Fuels | FY2024 |
| Inference of flow conditions from in-core detector measurements for accelerating SMR licensing | Massachusetts Institute of Technology | $1,000,000 | Reactor modelling relies on the detailed description of reactor systems but often lacks the true as-built characteristics of a system. This proposal seeks to fill these geometrical data gaps using available detector data, predictive models and machine learning in order to provide better information to analysis tools and thus better prediction of future performance. | Document | Licensing, Safety, and Security | FY2024 |
| Taggants in Future Nuclear Fuels by Design as an Enabling Technology to Track Nuclear Materials | Rensselaer Polytechnic Institute | $1,000,000 | The overarching goal of this project is to develop an innovative materials accounting and control technology by adopting an approach of "safeguard by design" during fuel fabrication to fill nuclear control technology gaps in tracing and tracking nuclear fuels for advanced nuclear reactors. The project is based on a concept of "taggants in fuels" that can greatly increase forensic attributes, and enhance intrinsic proliferation resistance and MPACT effectiveness for advanced nuclear fuel cycles. | Document | Licensing, Safety, and Security | FY2024 |
| Non-Destructive Plutonium Assay in Pyroprocessing Bulk Materials with a 3D Boron-Coated-Straw Detector Array | University of Illinois at Urbana-Champaign | $1,100,000 | The objective of the proposed project is to develop and demonstrate a 3D boron-coated-straw detector array (3D-BCSDA) with high efficiency and spatial resolution. This detection system will be specifically designed to accurately assess the fissile mass in bulk nuclear material during pyroprocessing operations, thereby improving the precision and reliability of accountability measurements during separation. | Document | Licensing, Safety, and Security | FY2024 |
| Improving the computational efficiency and usability of dynamic PRA with reinforcement learning | University of Maryland, College Park | $1,064,400 | The overall objective of the proposed research is to improve the efficiency and usability of dynamic probabilistic risk assessment (PRA). Specifically, the first objective is to develop a new algorithm for dynamic PRA analysis that can significantly increase the computational efficiency. The second objective is to develop a question-answering system to streamline the process of risk-informed decision-making based on results obtained from the dynamic PRA analysis using the new algorithm. | Document | Licensing, Safety, and Security | FY2024 |
| Development of a Benchmark Model for the Near Real-Time Radionuclide Composition Measurement System using Microcalorimetry for Advanced Reactors | Virginia Commonwealth University | $1,100,000 | The primary goal of this proposed project is to develop high fidelity Monte Carlo radiation transport models of a microcalorimetry detector informed by fuel depletion models of a molten salt reactor and a pebble bed reactor to quantify the current and future capabilities of this detector technology to characterize and assay used fuel from these reactors in near real-time. | Document | Licensing, Safety, and Security | FY2024 |
| Concurrent Surrogate Model Development with Uncertainty Quantification in the MOOSE Framework Using Physics-Informed Gaussian-Process Machine Learning | University of Florida | $999,999 | The objective of this project is to develop a general capability for concurrent generation and use of physics-informed Gaussian process (GP)-based surrogate models to facilitate multiscale and multiphysics modeling. We will implement this new capability as part of the Multiphysics Object-Oriented Simulation Environment (MOOSE) so that every application based on the MOOSE framework will have access to it. | Document | Modeling and Simulation | FY2024 |
| Unstructured Adaptive Mesh Algorithms for Monte Carlo Transport | University of Illinois at Urbana-Champaign | $1,098,000 | We propose to develop the fundamental methods and techniques for unstructured adaptive mesh refinement with Monte Carlo tallies. This work enables a transformative leap forward in speed, accuracy, and robustness to enhance the contribution of high-fidelity radiation transport to advanced simulation. Adaptive refinement is deployed on a challenging multiphysics simulation, cascading heat pipe failure, to study acceleration and stabilization properties. | Document | Modeling and Simulation | FY2024 |
| Feasibility Study of Micro-Nuclear Reactor Thermal Output for Air Rotary Kilns in the High-Temperature Manufacturing of Portland Cement Clinker | Pennsylvania State University | $998,793 | This project aims to design and test a micro-nuclear reactor for high-temperature portland cement clinker production, a process responsible for 6%-8% of global CO2 emissions. Leveraging advanced reactors' heat output, the project explores TRISO-based nuclear microreactor core modifications and new working fluids for heat pipes. The research addresses uncertainties in micro-nuclear reactor deployment for clinker production and investigates high-efficiency heat exchanger designs. | Document | Non-Traditional and Non-electric Applications | FY2024 |
| Redox potential, ionic speciation, and separation and recovery challenges from molten salts containing actinides and fission products | Massachusetts Institute of Technology | $999,999 | Establishing an efficient, safe, secure, and economical Molten-Salt Reactor (MSR) fuel cycle is imperative for MSR implementation. Molten salt fuel recycling technology requires predictive knowledge of the chemical and physical behavior of lanthanide and actinide ions with different oxidation states dissolved in solvent salts. A combination of off-gas and X-ray measurements with machine-learning simulations will be used to produce predictive modeling of separation and recovery conditions. | Document | Nuclear Fuel Recycle Technologies | FY2024 |
| Pre-Treatment and Bulk Separation of Used Fuels with Carbonate-Peroxide Solutions | Pennsylvania State University | $1,000,000 | To use carbonate-peroxide chemistries to develop a pre-processing method for used uranium-based fuels that enables the subsequent use and optimization of current solvent extraction reprocessing schemes. Using simple precipitation, this innovative method provides an initial, bulk separation of uranium from fission products and actinides. | Document | Nuclear Fuel Recycle Technologies | FY2024 |
| Optimization of Fueling Strategies and Material Surveillance through Real-time Pebble Tracking in Pebble Bed Reactors | University of Illinois at Urbana-Champaign | $1,100,000 | Flexible operation of the energy grid of the future introduces uncertainty in determining the optimal operating conditions of Pebble Bed Reactors. The proposed work will help to address these challenges and enable more economical operation by providing the tools to determine of optimal fuel reloading strategy through pebble identification and tracking. | Document | Reactor Development and Plant Optimization | FY2024 |
| Effects of Tritium-Graphite Interactions on Safety Transients in Graphite-Moderated Nuclear Reactors. | University of Illinois at Urbana-Champaign | $1,000,000 | MSRs, FHRs, and HTGRs have tritium production rates 10 to 10,000 times larger than LWRs. Objective of this project is to:-Quantify the concentration of tritium in graphite in new generation FHRs and HTGRs as a function of time and operational conditions-Assess the impact of the tritium content in graphite on reactor physics during normal operations and safety transients-Quantify tritium release rates and release kinetics during reactor transients inducing temperature increases | Document | Reactor Development and Plant Optimization | FY2024 |
| Experimental Study and Computational Modeling of P-LOFC and D-LOFC Accidents in the Fast Modular Reactor Consisting of Silicon Carbide Composite Rods | University of Michigan | $1,100,000 | The primary objectives of this proposed research are to better understand NC flow phenomena and heat transfer under both D-LOFC and P-LOFC accidents in the FMR, produce experimental data in a well-scaled integral-effects test facility for the two accidents, and develop and validate predictive CFD models for NC flow phenomena in both accidents. | Document | Reactor Development and Plant Optimization | FY2024 |
| Sodium heat pipes; design and failure mode assessment for micro-reactor applications | University of Wisconsin-Madison | $1,000,000 | The present proposal aims to experimentally investigate the thermal-hydraulics performance of liquid sodium heat pipes applied to microreactors, with a focus on exploring different design parameters, effects of different parameters on operating performance and understanding the evolution and impact of different failure modes. | Document | Reactor Development and Plant Optimization | FY2024 |
| Interfacial Interactions between Graphite and Molten Fluoride Fuel Salt | Virginia Polytechnic Institute and State University | $1,000,000 | NaF-KF-UF4 fuel salt will be selected to study graphite-salt interactions and impact of the existence of fission products (FPs) and corrosion products on the interactions at different temperatures and pressures. Fundamental mechanisms of graphite-salt interaction and degradation will be understood. | Document | Reactor Development and Plant Optimization | FY2024 |
| AI to Guide Sorption Data Acquisition and Assimilation into Uncertainty Quantifications for the Nuclear Waste Disposal Performance Assessment | Massachusetts Institute of Technology | $800,000 | The objective of this project is to develop machine learning (ML) and AI toolsets to effectively expand the global sorption database-the datasets collected by multiple institutions around the world-and to assimilate these datasets into the uncertainty quantification (UQ) in the performance assessment (PA) of nuclear waste repositories. | Document | Spent Fuel, Waste Science & Technology and Integrated Waste Management System | FY2024 |
| Local resonance-based linear and nonlinear NDE techniques for repaired DSC wall structures | University of Illinois at Urbana-Champaign | $1,000,000 | The proposed work plan will develop nondestructive examination (NDE) methods that develop and evaluate linear and nonlinear resonant ultrasound spectroscopy methods (such as NRUS, NIRAS, etc.) to cold spray (CS) repaired dry shielded canister (DSC) wall structures. With the support of our partners from Pacific Northwest National Laboratory (PNNL) and Oak Ridge National Laboratory (ORNL), we will perform technology development and validation on plain and cold spray-repaired DSC wall specimens. | Document | Spent Fuel, Waste Science & Technology and Integrated Waste Management System | FY2024 |
| Thermodynamic Models for Multivalent Actinide Solubility and Speciation as a Function of Temperature and Ionic Strength | University of Notre Dame | $1,000,000 | This proposed project will quantify the solubility and speciation of Np and Pu under temperatures, ionic strengths, and pH values that are relevant to the generic repository concept. The major deliverable will be full thermodynamic descriptions of the studied systems, which will lead to improved radionuclide transport models and support the development of a sound technical basis for the geologic disposal of spent nuclear fuel and other actinide-bearing wastes. | Document | Spent Fuel, Waste Science & Technology and Integrated Waste Management System | FY2024 |
| Advancing Fundamental Molten Salt Modeling using Ultrafast Spectroscopy | North Carolina State University | $600,000 | The overarching goal of the proposed research is to advance our fundamental understanding of molten salts by combining ultrafast spectroscopic experiments with high fidelity atomistic simulations. The proposed research will introduce a new experimental technique to the study of molten salts that will directly measure ion kinetics, specifically, terahertz time-domain spectroscopy (THz-TDS), which will further validate AIMD as a predictive modeling tool. | Document | Strategic Needs Blue Sky | FY2024 |
| Hydrodynamics of Two-Phase Flow Under the Geometric Effects of Pipe Orientation and U-bends | Purdue University | $600,000 | Most two-phase flow analyses have been performed in straight vertical-upward pipes. However, nuclear reactor systems include piping with different geometric components, such as elbows or U-bends, as well as changes in flow orientations. The proposed work performs experiments in a scaled test facility existing at the institution's lab to investigate the effects of flow orientations and geometries relevant to nuclear reactor systems on the hydrodynamics of two-phase flow. | Document | Strategic Needs Blue Sky | FY2024 |
| Interface-Resolved Experimental and Numerical Studies of Two-Phase Flow for Nuclear Engineering Applications | Virginia Polytechnic Institute and State University | $500,000 | The project aims at advancing the interface-resolved simulation capabilities for the two-phase flows found in various nuclear engineering applications. We will develop a comprehensive, high-resolution, interface-resolved database emphasizing bubble dynamics and bubble interaction mechanisms. The data will be used to validate the sub-grid models implemented in an interface-resolved simulation tool to improve simulation accuracy by developing physics-based coalescence models. | Document | Strategic Needs Blue Sky | FY2024 |
| Mechanism Driven Evaluations of Sequential and Simultaneous Irradiation-Creep-Fatigue Testing | University of Michigan | $1,000,000 | This project addresses a critical need for irradiation and creep-fatigue testing by carrying out a systematic, mechanistic-driven benchmarking for irradiation creep, irradiation fatigue and creep-fatigue tests under various environments. | Document | Advanced Nuclear Materials | FY2023 |
| Mechanisms-based Acceleration of Materials Qualifications for Creep-Fatigue Performance in Advanced Nuclear Systems | University of Illinois at Urbana-Champaign | $1,000,000 | The goal of this research is to fully understand, quantify and model creep-fatigue 'damage' as a function of loading patterns, temperature and microstructural evolution. Using this experimental information over a large range of relevant stress levels and temperatures, a mechanisms-based creep-fatigue analysis approach will be demonstrated which will properly qualify high temperature alloys for extended service in advanced nuclear systems where creep-fatigue is currently a major design limitation. | Document | Advanced Nuclear Materials | FY2023 |
| Subwavelength Ultrasonic Imaging for Rapid Qualification of Additively Manufactured Nuclear Structures and Components | University of Michigan | $1,000,000 | The objective of this project is to develop a transformational capability for rapid nondestructive quality assessment of actual nuclear additively manufactured structures and components through advanced ultrasonic imaging with subwavelength resolution. The resolution of conventional ultrasonic systems is limited by diffraction on the order of the wavelength. In this project, the goal is to break the diffraction limits of ultrasonic imaging by implementing a negative-index lens. | Document | Advanced Nuclear Materials | FY2023 |
| MXene as Sorbent Materials for Off-gas Radioiodine Capture and Immobilization | Clemson University | $1,000,000 | The overarching goal of this project is to develop efficient and stable new sorbent materials, for off-gas radioiodine capture and immobilization, that are based on MXenes with two-dimensional transition metal carbides/nitrides. The exploratory research will focus on three main objectives: 1) Design and synthesis of MXenes as radioiodine sorbent and support materials, 2) Quantification of iodine sorption capacity of MXenes in different forms, 3) Synthesis and characterization of consolidated waste forms. | Document | Advanced Nuclear Materials | FY2023 |
| Fundamental understanding of grain boundary cracking in LWR environments | University of California, Los Angeles | $1,000,000 | The objective of this project is to understand the details of stress corrosion cracking (SCC) and irradiation assisted stress corrosion cracking (IASCC) by targeted experiments and modeling efforts. A comprehensive model will be produced, which will predict the conditions under which these failure modes occur and when the materials may see onsets of the failure mode. This work will directly impact the nuclear industry by refining predictive models of component lifetime. | Document | Advanced Nuclear Materials | FY2023 |
| Facile manufacturing of fiber-reinforced-SiC/SiC composite using aerodynamic fiber deposition (AFD) and metal assisted polymer impregnation and pyrolysis processes (MAPIP) | University of Pittsburgh | $999,886 | SiC/SiC ceramic matrix composites (CMCs) are promising candidate materials for the cladding of accident tolerant fuels. Superior material properties of SiC/SiC CMC, however, come at a high manufacturing cost. The objective of the proposed research is to apply aerodynamic fiber deposition (AFD) and metal assisted polymer impregnation and pyrolysis (MAPIP) to develop a new facile manufacturing approach of SiC/SiC CMC. | Document | Advanced Nuclear Materials | FY2023 |
| High Concentration Monoamide Separations: Phase Modifiers and Transuranic Chemistry | Colorado School of Mines | $999,900 | Extraction of actinides from used nuclear fuel with high concentrations of monoamide extractants is a promising strategy to intensify separation processes; however key issues remain to be understood and resolved. This project will examine three questions: 1) Can phase modifiers mitigate issues with organic phase viscosity? 2) Can the chemistry of neptunium be controlled to ensure complete separation? 3) Do high concentrations of monoamides affect the oxidation states of important metals and can that be exploited? | Document | Fuel Cycle Technologies | FY2023 |
| Multiple Uranium Complexes in Chloride Fast Reactor Molten Salt Properties | University of Connecticut | $1,000,000 | Multivalent transition metal ions in a melt can exhibit multiple coordination states that affect molten salt properties. This project will use a new high-energy resolution fluorescence detection (HERFD) spectroscopy to overcome issues associated with measuring coordination numbers of multiple complexes, along with Raman spectroscopy and advanced simulations to accurately predict properties of molten salts with multiple uranium complexes. | Document | Fuel Cycle Technologies | FY2023 |
| Validation of Geochemical Reactive Transport Long-Term predictions Using Natural Cements and Ancient Cements Analogues | Vanderbilt University | $950,000 | This project will validate long-term performance predictions of rock/cement interfaces based on characterization of natural analogues, ancient cements and interfaces with rock formations, and demonstrate applicability of the established testing and simulation workflow with argillite rock (representative of potential U.S. repository systems). This project addresses the research gap of long-term validation and uncertainty assessment associated with cement barrier performance and multi-physics models. | Document | Fuel Cycle Technologies | FY2023 |
| Predicting Pitting and Stress Corrosion Cracking of Dry Cask Storage Canisters via High Throughput Testing, Multiscale Characterization, and 3D Computer Vision based Machine Learning | The Ohio State University | $1,000,000 | This project consists of a US-UK collaborative research program focusing on the nucleation and growth of pits and stress corrosion cracking of stainless steel 304 (a canister material used for dry cask storage of spent nuclear fuels) by leveraging multi-scale characterization techniques, 2D/3D computer vision, and machine learning approaches. The study will enable the understanding and prediction of how and when pitting corrosion can nucleate, grow, and transition into stress corrosion cracking. | Document | Fuel Cycle Technologies | FY2023 |
| Multiscale Residual Stress Tailoring of Spent Fuel Canister CISCC Resistance | Purdue University | $1,000,000 | The objective of this project is to understand the role of residual stress in chloride-induced stress corrosion cracking (CISCC) of austenitic steel, then tailor CISCC initiation and propagation through engineered multiscale residual stress distributions. Microscopic and macroscopic residual stresses will be systematically varied, then a novel sequence of advanced, site-specific, correlative characterization techniques will be applied to directly link residual stress, pitting, and crack propagation. | Document | Fuel Cycle Technologies | FY2023 |
| Illuminating Emerging Supply Chain and Waste Management Challenges | University of Illinois at Urbana-Champaign | $1,000,000 | Regional constraints on domestic fuel supply and greater variation in demand from advanced reactors has led to a shift in the U.S. fuel cycle, and modeling tools must reflect this. In this work, Cyclus will be updated to better reflect new and emergent regional supply constraints, spatial and temporal fluctuations in material needs, and those impacts on the back-end of the fuel cycle will be quantified. This work will allow for flexible, reproducible analysis to inform stakeholder decision-making. | Document | Fuel Cycle Technologies | FY2023 |
| Determination of Local Structure and Phase Stability of Uranium Species in Molten Halide Salts: Linking Microscopic Structure with Macroscopic Thermodynamics | Arizona State University | $1,000,000 | The goal of this project is to determine the local structures (valence state, coordination configuration and medium-range structure) and thermodynamic stability of uranium species in molten chloride and fluoride salts at high temperatures using a combination of experimental and modeling methods. The obtained results will allow for revelation of the structure-stability relations of the studied systems and development of acid-base scales to determine the solubility of uranium in molten halide salts. | Document | Fuel Cycle Technologies | FY2023 |
| Thermal-Hydraulics Assessment of SiC Compared to Other ATF Cladding Materials and its Performance to Mitigate CRUD | University of Wisconsin-Madison | $1,000,000 | This project aims to experimentally investigate the thermal-hydraulics performance of SiC compared to the Cr-coated zircaloys and APMT ATF cladding materials under accident scenarios, including both DNB and dryout conditions. The project is divided into five tasks that will advance the understanding of the operation and optimization of heat pipes for advanced nuclear reactors. | Document | Fuels | FY2023 |
| Physics-Informed Artificial Intelligence for Non-Destructive Evaluation of Ceramic Composite Cladding by Creating Digital Fingerprints | University of Florida | $1,000,000 | The objective of this project is to spatially map the material composition, structure, and defect distribution of SiCf-SiCm composite tubes from ultrasonic wavefields measured from the materials and the defects within them. Specifically, this project will delve into the unique ultrasonic fingerprints (i.e., dispersion relations and mode shapes) of the SiCf-SiCm composites using physics-informed machine learning to assess the quality of the manufactured tubes based on their spatial-spectral ultrasonic characteristics. | Document | Fuels | FY2023 |
| Improving Reliability of Novel TRISO Fuel Forms for Advanced Reactors via Multiscale, High-Throughput Characterization and Modeling | Brigham Young University | $1,000,000 | This project will use a parallelized thermal conductivity (k) measurement device coupled with multiscale models to accurately predict the thermal conductivity of TRISO fuel composites. This project overcomes the issue plaguing many "localized" microscale measurements, namely the inability to scale local measurements up to engineering scale properties. This will be done by using Bayesian inference techniques and finite element models to predict effective thermal conductivity. | Document | Fuels | FY2023 |
| Understanding Constituent Redistribution, Thermal Transport, and Fission Gas Behavior in U-Zr Annular Fuel Without a Sodium Bond | University of Florida | $999,462 | This project will investigate the reason for changed constituent redistribution in annular U-Zr fuel without a sodium bond and how it changes the fission gas behavior and thermal conductivity. This will be achieved using a combination of microstructure characterization and thermal conductivity measurements of irradiated U-Zr annular fuel and multiscale modeling and simulation using the MARMOT and BISON fuel performance codes. | Document | Fuels | FY2023 |
| Getting AnCers: Metallothermic Molten Salt Synthesis and Reaction Thermodynamics of Actinide Ceramic Fuels | Oregon State University | $1,000,000 | Synthesis of high quality actinide ceramics (AnCers) remains a costly challenge. A low-temperature, high-yield, short-duration reaction that directly synthesizes UN and UC could reduce the cost of these advanced fuels greatly. This proposal aims to demonstrate a method by which the costs of AnCers can be greatly reduced-metallothermic molten salt synthesis. Optimization and thermodynamics data will be obtained. | Document | Fuels | FY2023 |
| Integrated Stand-off Optical Sensors for Molten Salt Reactor Monitoring | University of Pittsburgh | $1,000,000 | This project intends to develop robust and stand-off optical sensors to perform real-time molten salt levels, flow, and impurity measurements of molten salts. | Document | Instrumentation and Controls | FY2023 |
| Optical Sensors for Impurity Measurement in Liquid Metal-cooled Fast Reactors | University of Michigan | $1,000,000 | This project will investigate whether a unique combination of two versatile optical techniques-laser-induced breakdown spectroscopy (LIBS) and two-photon absorption laser-induced fluorescence (TALIF)-could provide a sensitive, robust, and convenient method for in-situ, real-time detection of trace impurities ( | Document | Instrumentation and Controls | FY2023 |
| Cybersecurity in advanced reactor fleet by cyber-informed design, real-time anomaly detection, dynamic monitoring, and cost-effective mitigation strategies | University of Wisconsin-Madison | $1,000,000 | The goal of this research is to provide technical solutions to unique cybersecurity challenges in future microreactor fleet through cyber-informed design (C-ID), real-time anomaly detection, dynamic monitoring, and cost-effective mitigation strategies. The efforts will significantly improve the economics and effectiveness of cybersecurity risk management in future microreactor fleets. | Document | Instrumentation and Controls | FY2023 |
| Building Cyber-Resilient Architecture for Advanced Reactors via Integrated Operations and Network Digital Twin | Georgia Institute of Technology | $1,000,000 | The research will develop a secure-by-design architecture via integrating plant operation and network digital twins for advanced reactors. Automatic attack path and vulnerability analysis will be developed and used to assess and harden critical digital assets (CDA) against cyber risks prior to and during operation to identify vulnerabilities, attack pathways, and threat vectors. A CDA selection method will also be developed by combining vulnerability scores and assets importance. | Document | Instrumentation and Controls | FY2023 |
| Extending PRA and HRA legacy methods and tools with a cause-based model for comprehensive treatment of human error dependency | University of California, Los Angeles | $1,000,000 | This project aims at developing a solution to HRA dependency assessment in PRA from methodological and practical/computational perspectives within legacy PRA tools and methods. The solutions will include procedures for quantifying dependency when using PRA legacy tools, a method for modeling and quantifying dependency in HRA comprising a BN-causal model suitable for use with legacy PRA methods and tools, and the computational tools for its integration. | Document | Licensing and Safety | FY2023 |
| An Integrated Elemental and Isotopic Detector for Real-Time Molten Salt Monitoring | North Carolina State University | $1,000,000 | The overarching theme of the proposed research is to develop and demonstrate a real-time elemental and isotopic detector of molten salts for advanced reactors and fuel fabrication and recycling processes. The detector's longevity, limits, and latency will be tested in static uranium chloride salts, in pyroprocessing chloride salt, and on flowing fluoride salt with evolving actinide composition, respectively. | Document | Licensing and Safety | FY2023 |
| Development of a Thin-Layer Electrochemical Sensor for Molten Salt Reactors and Fuel Cycle Processes | Brigham Young University | $811,755 | A thin-layer electrochemical sensor capable of detecting uranium, plutonium and other species of interest in molten salts, at both high and low concentrations, will be developed for application in molten salt reactors and fuel cycle process units. This will provide a valuable tool for performing material control and accountancy measurements. | Document | Licensing and Safety | FY2023 |
| Risk-Informed Consequence-Driven Hybrid Cyber-Physical Protection System Security Optimization for Advanced Reactor Sites | Georgia Institute of Technology | $1,000,000 | This project aims to develop an expanded methodology for designing a novel cybersecurity-integrated physical protection system (PPS) framework for advanced reactor concepts that serves to reduce the operational costs for the life of a reactor against that of a traditional light water reactor PPS design, promoting efforts to credit safety features of advanced reactors through proposed amendments to current security regulations, while integrating health and economic consequence analyses. | Document | Licensing and Safety | FY2023 |
| A risk analysis framework for evaluating the safety, reliability, and economic implications of electrolysis for hydrogen production at NPPs | University of Maryland, College Park | $1,000,000 | The RAFELHyP project will develop a modular risk analysis framework that enables evaluating the safety, reliability, and economic implications of upcoming deployments of electrolyzers to produce hydrogen at nuclear power plants. The framework will be implemented to conduct an integrated safety, reliability, and economic analysis of multiple plant configurations to provide detailed recommendations for plant protective features and layouts. | Document | Licensing and Safety | FY2023 |
| Reduced Order Modeling of Heat and Fluid Flow: Multi-Scale Modeling of Advanced Reactors to Enable Faster Deployment | University of Illinois at Urbana-Champaign | $1,000,000 | Novel multi-scale algorithms for thermal-hydraulics (TH) simulations of advanced reactors will be developed. The methods will leverage recent advances in hardware and reduced order modeling approaches to enable TH simulations of vastly accelerated speed, while maintaining accuracy comparable to high-fidelity methods, such as large-eddy simulation. The methods will allow designers to perform parameter sweeps, develop closures, and enable high fidelity simulation of transients. | Document | Modeling and Simulation | FY2023 |
| Embedded Monte Carlo | Massachusetts Institute of Technology | $1,000,000 | Monte Carlo methods have long been considered the standard in terms of accuracy and have seen increased use in design of small nuclear systems; however, the uncertainty quantification (UQ) of the desired output is often relegated to later stages of the design process. This project seeks to embed nuclear data UQ in a single Monte Carlo simulation, such that each desired quantity will not only provide the mean value and statistical uncertainty, but also the related nuclear data uncertainty. | Document | Modeling and Simulation | FY2023 |
| A Low Order Transport Method Based on the Dynamic Truncation of the Integral Transport Matrix Method (ITMM) that Converges to the SN Solution with Increasing Cell Optical Thickness | North Carolina State University | $1,000,000 | A novel low-order transport operator capable of approximating Monte Carlo (MC) results within a variance range will be developed. This does not require MC reference solutions to calibrate the low-order model, so repeated solutions of the latter in-transient scenarios does not require repeated MC simulations. Truncation of the low-order operator is done dynamically for evolving configurations to ensure accuracy of the low-order solution. This will involve proof of principle on Cartesian meshes, then implementation in Griffin. | Document | Modeling and Simulation | FY2023 |
| CFD based Critical Heat Flux predictions for enhanced DNBR margin | Massachusetts Institute of Technology | $1,000,000 | This project seeks to demonstrate a robust high-fidelity CFD-based methodology to predict CHF behavior at varying quality conditions, enabling the development of advanced DNBR correlations with reduced uncertainty, and in support of upgraded plant economics. The availability of a virtual CHF methodology will allow greatly extending the database for DNBR correlations development and further support advancement in the design of high-performing nuclear fuel. | Document | Modeling and Simulation | FY2023 |
| Immersed Boundary Methods for Modeling of Complex Geometry: A Leap Forward in Multiscale Modeling using NekRS | University of Illinois at Urbana-Champaign | $1,000,000 | A major challenge to Computational Fluid Dynamics (CFD) modeling of complex geometries is the need to generate body-fitted meshes, which can occupy 80% of the CFD practitioner's time. Immersed boundary methods will be added in the NekRS CFD code, dramatically simplifying modeling of complex 3-D structures and facilitating a new paradigm for CFD-informed multiscale analysis. This will be demonstrated by informing SAM transient systems-level models with NekRS heat exchanger correlations for advanced reactors. | Document | Modeling and Simulation | FY2023 |
| Uncertainty Quantification of Model Extrapolation in Neural Network-informed Turbulent Closures for Plenum Mixing in HTGRs | Utah State University | $1,000,000 | This project will quantify the uncertainty in prediction of Neural Network-informed Turbulent Closures when they are operating in a model extrapolation state. Once the method is developed for canonical buoyant jets, the protocols will be applied to plenum mixing in HTGRs. | Document | Modeling and Simulation | FY2023 |
| Impact of moisture on corrosion of NiCr alloys in MgCl2-NaCl Salt Systems | University of Wisconsin-Madison | $999,983 | This project aims to gain a fundamental understanding of the impact of moisture and salt chemistry on corrosion of NiCr alloys in molten chloride salts. A novel approach coupling multiscale simulations and experiments will be designed to determine salt acidity, its dependence on salt composition (i.e., the NaCl to MgCl2 ratio), and its effects on the transport of H2O and Cr ions and the corrosion kinetics of NiCr alloys in chloride salt. | Document | Reactor Development and Plant Optimization | FY2023 |
| Transforming Microreactor Economics Through Hydride Moderator Enabled Neutron Economy | State University of New York, Stony Brook | $1,000,000 | Microreactors will potentially require the cost of electricity to be 10 MWD/kg at >3 kW/kg core specific power. These goals are best achieved through a well-thermalized spectrum. Neutron economy as a core material selection criterion to advance entrained hydride composite moderators will be used with the primary goal of significantly reducing fuel costs through novel microreactor designs. | Document | Reactor Development and Plant Optimization | FY2023 |
| Integrating Nuclear with ZLD Seawater Desalination and Mining | University of Wisconsin-Madison | $1,000,000 | An integrated nuclear system will be developed that would utilize electricity and waste heat to operate a desalination and mining process from adjacent seawater. The desalination approach targets zero-liquid discharge with multiple marketable minerals extracted. The ability of nuclear facilities to load follow is increasingly important, so a cold thermal storage system will be incorporated. The desalination and mineral extraction process will be experimentally validated at lab scale. | Document | Reactor Development and Plant Optimization | FY2023 |
| Reference Designs of Green Ammonia Plants Powered by Small Modular Reactors | Utah State University | $1,000,000 | The overarching goal of this project is to develop two reference designs for green ammonia plants. One design uses freshwater as the source for hydrogen, while the other design uses seawater (or brackish water) as the source. In both designs, a small modular reactor (SMR) is used as the primary energy source providing both electricity and steam for the plants. | Document | Reactor Development and Plant Optimization | FY2023 |
| Development of the Technical Bases to Support Flexible Siting of Microreactors based on Right-Sized Emergency Planning Zones | Pennsylvania State University | $1,000,000 | The objective of this project is to provide the technical basis to support the application of a right-sized Emergency Planning Zone (EPZ) size to support the deployment of a microreactor at the Penn State University Park campus. This research study will serve as a template to provide flexible siting in support of future microreactor deployments that may be placed closer to demand centers, thereby making them more economically competitive. | Document | Reactor Development and Plant Optimization | FY2023 |
| Bayesian Optimization for Automatic Reactor Design Optimization | Arizona State University | $1,000,000 | The objective of this project is to develop analytical tools based on Gaussian process modeling and Bayesian Optimization that facilitate reactor design optimization by modeling the responses from the physics simulator. Existing capabilities will be applied in an AI field and they will be adapted to address the key characteristics of nuclear reactor design problem. This project will automate the simulation-based design procedure, reduce the number of iterations, and minimize the design cycle time. | Document | Reactor Development and Plant Optimization | FY2023 |
| A Pathway for Implementation of Advanced Fuel Technologies in Light Water Small Modular Reactors | Texas A&M University | $1,000,000 | A comprehensive characterization of the performance of the Lightbridge Helical Cruciform advanced fuel design will be performed, which will generate unique sets of experimental data of friction factor, flow and heat transfer behavior under NuScale's LW-SMR simulated normal and off-normal conditions. The project will accelerate the deployment of advanced fuels for LW-SMR applications by leveraging the use of existing testing infrastructures. | Document | Reactor Development and Plant Optimization | FY2023 |
| Engaging New Mexican communities in developing an equitable and just approach to siting advanced reactor facilities | University of Michigan | $1,000,000 | This project will engage diverse New Mexican communities to develop an equitable approach for advanced reactor siting. The findings of this project will shed light on how technology developers and the DOE can explore and potentially site advanced reactors with the informed consent and engagement of host communities, regions, and states. The findings of this study will also more generally apply to the potential for equitably exploring both brownfield and greenfield sites for nuclear facilities. | Document | Reactor Development and Plant Optimization | FY2023 |
| Deciphering Irradiation Effects of YHx through In-situ Evaluation and Micromechanics for Microreactor Applications | University of New Mexico | $998,000 | This project addresses a critical gap in accelerated testing of YH evolution coupling multi-length scale mechanical testing with ion irradiation and advanced characterization to establish a baseline understanding of YH evolution under ion irradiation. Our approach will couple ion irradiation and gamma irradiation with small scale mechanical testing to decipher multi-scale impacts on phase stability to advance understanding of YH in a microreactor moderator application. | Document | Reactor Development and Plant Optimization | FY2023 |
| Active Learning Estimation and Optimization (ALEO) of Irradiation Experimental Design for Efficient Accelerated Fuel Qualification | University of Texas at San Antonio | $997,247 | This collaborative project creates novel AI/ML models and algorithms integrated with physical knowledge and expertise to explore more efficient ways to calculate irradiation temperatures and fuel specimen burnups for new fuel sample configurations of MiniFuel experiments proposed for irradiation in the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL). | Document | Reactor Development and Plant Optimization | FY2023 |
| Unraveling how mixing vane spacers affect cladding-to-coolant heat transfer phenomena in light water reactors | Massachusetts Institute of Technology | $500,000 | Experiments will be conducted to quantify the effect of mixing vane spacers on cladding-to-coolant heat transfer phenomena, namely single-phase forced convection, nucleate boiling, and CHF. The results of the experimental research will allow elucidating the physical phenomena triggered by the presence of mixing vane spacers. They will also allow assessing the performance of M-CFD tools developed within CASL and in use by the nuclear community. | Document | Strategic Needs Blue Sky | FY2023 |
| Quantum Computing Algorithms for Deterministic Neutron Transport | University of Michigan | $500,000 | This project will develop algorithms for solving the k-eigenvalue form of the neutron transport equation in a nuclear reactor physics context on a quantum computer. The asymptotic scaling of the algorithms will be analyzed. Investigation into implementation will be made by making resource estimates by synthesizing explicit circuits for the algorithms and be studied by emulation on a classical computer. | Document | Strategic Needs Blue Sky | FY2023 |
| Optimizing Application-Dependent Energy Group Structures for Multigroup Neutron Transport Models using Machine Learning | Colorado School of Mines | $500,000 | Machine Learning methods will be developed that will dramatically reduce both the computational run-time and manual effort needed to find multigroup energy structures that accurately capture the underlying physics of neutron reactions, while allowing multigroup simulations to run quickly without overwhelming available memory. | Document | Strategic Needs Blue Sky | FY2023 |
| Functionally-graded Cermet Coatings for Molten Salt Technologies by High Throughput Finite Element Modeling and Additive Manufacturing | Rensselaer Polytechnic Institute | $500,000 | This project proposes an integrated approach/methodology to design, manufacture and verify functionally-graded metal-ceramic composite coatings on structural alloys with desired interfacial properties, capabilities of mitigating residual stress and improved corrosion resistance for molten salt reactor applications. | Crosscutting Technologies | FY2022 | |
| An Innovative Monitoring Technology for the Reactor Vessel of Micro-HTGR | Texas A&M University | $800,000 | This project seeks to develop an innovative sensor technology for real-time monitoring of the thermo-mechanical stresses in the reactor vessel of micro-HTGR. The technology will be based on a sparse network of outer wall temperature measurements and plant operating conditions. An integrated software-hardware sensing system aimed at monitoring the health of the pressure vessel of gas micro-reactors will be implemented and tested. The proposed work will have a broad impact on sensing in other reactor designs. | Crosscutting Technologies | FY2022 | |
| High throughput mechanical testing of additively-manufactured materials | University of California, Berkeley | $500,000 | This project proposes fast and high throughput mechanical testing of AM produced materials. It will include the generation of automated tensile testing, hardness testing and microstructure assessment and data comparison to build data via machine learning. | Crosscutting Technologies | FY2022 | |
| Accelerated irradiation creep testing coupled with self-adaptive accelerated molecular dynamics simulations for scalability analysis | University of Michigan | $500,000 | The goal of the proposed work is to accelerate traditional irradiation creep using instrumented in-situ ion irradiation creep and long-time molecular dynamics simulations to accelerate traditional neutron irradiation creep testing. This goal will be accomplished by coupling a novel ion beam flux jump test using tapered creep specimens and self-adaptive accelerated molecular dynamics. The outcome is a rapid, low-cost accelerated method to determine the fundamental irradiation creep mechanisms. | Crosscutting Technologies | FY2022 | |
| Creation of a Pebble Database for Material Control and Accountancy in Pebble Bed Reactors | Virginia Commonwealth University | $399,969 | The primary goal of this proposed project is to develop a database of NDA signatures from a wide variety of used PBR pebbles. This database can be used for facility operations, safety, security, and safeguards (3S) to directly measure fission product content and indirectly 235U and plutonium content of each PBR pebble. This project has significant synergy with current 3S PBR research at ANL, BNL, and ORNL, all of whom are collaborators to this proposed project. | Crosscutting Technologies | FY2022 | |
| Integrated Marine Platform for Hydrogen and Ammonia Production | Massachusetts Institute of Technology | $800,000 | This study investigates the economic and environmental value of a floating integrated GW-scale green hydrogen/ammonia production facility powered by an advanced nuclear reactor. Floating Production Storage and Offloading units (FPSOs) are deployed worldwide in the oil and gas industry, and can be used for hydrogen and ammonia processing. Deployment of an advanced reactor on a floating platform offers several advantages, including the efficiencies of shipyard fabrication. | Crosscutting Technologies | FY2022 | |
| Quantifying Aerosol Deposition Mechanisms in Model Dry Cask Storage Systems | Clemson University | $800,000 | The objective of this work is to measure aerosol deposition and resuspension rates in laboratory models of dry cask storage systems to compare with and validate the DOE deposition model. The project team will conduct experiments to directly measure the deposition/resuspension rates of bulk aerosol in the system and to isolate and quantify individual aerosol deposition mechanisms, with a focus on those sensitive to variable humidity and surface temperature. | Fuel Cycle R&D | FY2022 | |
| Using Amide-Functionalized Electrodes to Elucidate Interfacial Actinide Redox Chemistry for Improved HALEU Supply | Florida International University | $400,000 | The goal is to decrease HALEU fuel cycle costs by examination of the redox behavior of U, Np, and Pu at the water-organic interface using amide functionalized electrodes, and in organic media after extraction with amides. Experiments with redox active interferences including additional actinides in different oxidation states will also be conducted. | Fuel Cycle R&D | FY2022 | |
| Advancing the technical readiness of FeCrAl alloys and ODS steels under extreme conditions for fast reactor fuel cladding | North Carolina State University | $800,000 | A key technology gap for advanced high-performance fuel applications is the current unavailability of materials that can withstand extremely high doses without significant degradation of cladding performance. The project team will perform in-situ thermo-mechanical experiments (tension, torsion, creep, and creep-fatigue and nanoindentation) on ion-irradiated (to 400 dpa) cladding materials (up to 700 C) along with microstructures using TEM and mesoscale phase field simulations. | Fuel Cycle R&D | FY2022 | |
| A molten salt community framework for predictive modeling of critical characteristics | Pennsylvania State University | $400,000 | This research aims to develop a molten salt community framework to address the needs in advanced fuel cycles, including understanding salts via new theory of liquids, predicting salt characteristics via simulations (DFT, MD, and CALPHAD by implementing advanced models), optimizing inversely molten salts, and verifying simulations by experiments. This project has outstanding value for US taxpayers, educates students, and delivers outreach opportunities for academia, industry, and the public. | Fuel Cycle R&D | FY2022 | |
| Understanding the Interfacial Structure of the Molten Chloride Salts by in-situ Electrocapillarity and Resonant Soft X-ray Scattering (RSoXS) | Pennsylvania State University | $400,000 | The objective of the proposed research is to investigate the interplay between the interfacial structure of the molten salts and their electrochemical corrosion properties in Molten Salt Reactors (MSRs). | Fuel Cycle R&D | FY2022 | |
| Clay Hydration, Drying, and Cracking in Nuclear Waste Repositories | Princeton University | $800,000 | This project will develop a new multiscale model of the thermal-hydrologic-mechanical-chemical (THMC) evolution of an engineered clay barrier in the near field of a nuclear waste repository, including initial hydration and eventual post-closure criticality. This new model will directly link micro-scale material properties to large-scale barrier performance, thus facilitating future design advances or modifications, and enable robust validation of large-scale simulation predictions. | Fuel Cycle R&D | FY2022 | |
| Physics-guided Smart Scaling Methodology for Accelerated Fuel Testing | Purdue University | $800,000 | This project proposes to employ novel informatics algorithms for mapping/scaling uncertainties from experimentally accessible scaled state to application/prototypical state, informed by an equivalent mapping obtained from high-fidelity multi-physics simulations for the fuel thermo-mechanical behavior, specifically, a rate theory-based model for thermal conductivity and fission gas behavior in the BISON code, and employing relevant HALDEN reactor and FAST experiments. | Fuel Cycle R&D | FY2022 | |
| Materials Accountancy During Disposal and Waste Processing of Molten Salt Reactor Fuel Salts | Texas A&M University | $399,997 | The objective of this work is to develop and validate a method for measuring and predicting hold-up to eliminate operational risks and expenses during disposal of salt-wetted MSR components. These objectives will be met by applying robust measurement/detection methods to realistic salt loop environments to validate their use in decommissioning MSRs. | Fuel Cycle R&D | FY2022 | |
| Advanced Screening Approaches for Accelerating Development of Separations Technologies | University of California, Berkeley | $400,000 | The goal of this project is to establish a unified selection criterion for chelating molecular structures to more efficiently address ligand applicability to metal ion separation problems, for current and future nuclear fuel cycles. By establishing this criterion, the team will seek to enable the accelerated, cost-effective discovery of new separation workflows, as well as their implementation beyond early radiotracer experiments. | Fuel Cycle R&D | FY2022 | |
| Advancing NMA of TRISO-fueled pebbles using fast and accurate gamma-ray spectroscopy | University of Colorado, Boulder | $385,307 | This proposal will provide new Nuclear Materials Analysis (NMA) capabilities for TRISO-fueled pebbles using gamma-ray spectroscopy, through a program of simulations of expected signatures from irradiated pebbles, resulting in a detailed measurement plan to monitor burnup and actinide content throughout the fuel cycle. These simulations will be used to develop requirements for NMA sensor technology and identify opportunities for focused technology development to meet these requirements. | Fuel Cycle R&D | FY2022 | |
| Development of Irradiation and Creep Resistant High-Cr Ferritic/Martensitic Steels via Magnetic Field Heat Treatment | University of Kentucky | $800,000 | The objective of this proposed study is to develop and test new generation of Ferritic/Martensitic (F/M) steels specifically designed for advanced reactors that will exceed the current limitations due to temperature and irradiation dose. To achieve this objective, a systematic study is proposed to employ an innovative tempering heat treatment under high external magnetic field (up to 9T) on F/M steel HT9 to engineer an optimized microstructure composed of refined carbides and martensite laths. | Fuel Cycle R&D | FY2022 | |
| Investigation into the processing parameters of phosphate-based dehalogenation for chloride-based waste salt | University of Nevada, Reno | $399,999 | This proposal will focus on several topics needed to advance the iron phosphate process: 1) Dehalogenation/vitrification processes using salt simulants to generate process flow sheets, 2) Reactions of crucible materials with phosphate products and byproducts, 3) Collection of glass property-composition data to develop models based on the glass-forming regions, 4) Development of a process for reacting recovered NH4Cl with metals that need to be fed into the system (U, Li, etc.). | Fuel Cycle R&D | FY2022 | |
| A Validated Framework for Seismic Risk Assessment of Spent Fuel Storage Facilities | University of Nevada, Reno | $799,883 | This is a collaborative research program with a primary objective of developing a validated numerical framework for seismic risk analysis of spent fuel storage facilities from the global cask behavior to the localized behavior of internal spent fuel assemblies. In building and validating this framework, advanced data analysis, data assimilation, and forward and inverse modeling techniques will be utilized. | Fuel Cycle R&D | FY2022 | |
| International Collaboration to Advance the Technical Readiness of High Uranium Density Fuels and Composites for Small Modular Reactors | University of Texas at San Antonio | $800,000 | An international team of high uranium density fuels (HDFs) experts advised by industry leaders in nuclear reactor innovation propose a US-UK collaboration to advance the technical readiness of UN, UB2, and their composites for fuel forms specific to small modular reactors (SMRs). The project will bridge the critical data gaps in HDF performance specific to the impact of common impurities and microstructural variations that originate at fabrication. | Fuel Cycle R&D | FY2022 | |
| Development of Advanced Control Rod Assembly for Improved Accident Tolerance and High Burnup Fuel Cycle | University of Wisconsin-Madison | $800,000 | Research will focus on the development of new materials' designs for control rod sheaths and neutron absorbers, coupled with neutronics analysis and thermo-mechanical modeling to improve accident tolerance and to achieve higher fuel burnup in PWRs. Functionality of the proposed designs consisting of Cr coated control rod sheaths of current and advanced alloys as well as novel neutron absorbers will be evaluated in prototypical reactor conditions and accident scenarios. | Fuel Cycle R&D | FY2022 | |
| Optical Basicity Determination of Molten Fluoride Salts and its Influence on Structural Material Corrosion | University of Wisconsin-Madison | $400,000 | The proposed research is aimed at developing ion probes to determine the optical basicity of molten fluoride salts and studying its influence on structural material corrosion. Combining with the molten salt structure study using X-ray absorption spectroscopy, the salt chemical constitution, the resulting optical basicity, and molten salt structure will be inextricably linked and their connections will be unveiled. | Fuel Cycle R&D | FY2022 | |
| Extending the HMF71 Benchmark Series for Graphite Reflector Thickness up to 18 Inches | University of Tennessee at Knoxville | $399,522 | The objective of this proposal is to extend the HEU-MET-FAST-071 (HMF-71) experiment benchmark series in ICSBEP by evaluating the historical (existing) experimental data for critical experiments with graphite reflector thickness from 3 inches up to 18 inches. | Nuclear Energy | FY2022 | |
| Fast and Rigorous Methods for Multiphysics SPn Transport in Advanced Reactors | University of Michigan | $600,000 | This project proposes to perform rigorous theoretical and numerical analysis of the Generalized SPn method and underlying cross section models to enable a fast and robust multiphysics low-order transport capability for advanced reactors. This includes 5 major tasks focused on the efficient discretization and solution of the GSPn equations, numerical analysis of XS models having multiphysics and depletion, analysis of equivalence factors, improved MC estimators, and several V&V applications of the methods. | NEAMS | FY2022 | |
| Development of Hydrogen Transport Models for High Temperature Metal Hydride Moderators | Colorado School of Mines | $800,000 | Understanding the transient behavior of metal hydride moderator materials at high temperatures is a key challenge to the design and deployment of future microreactors. This project will use neutron radiography techniques provide the necessary data for this understanding and demonstrate the development of time and temperature dependent hydrogen transport models using both commercial FEA software coupled to MCNP and coupled models developed in the MOOSE framework. | RCRD&D | FY2022 | |
| Characterizing fast reactor fuel failure mode through separate effect and prototypic tests | Oregon State University | $800,000 | The project consists of conducting separate effect fuel pin failure tests with surrogate fluid and prototypic test with sodium. The outcome of this study will generate an experimental database that will be used to develop mechanistic model and validate the CDAP module of the SAS4A/SASSYS-1 code. Ultimately the quality data can be used to benchmark other fuel codes developed for LMFR application, which are seeking validation for licensing purpose. | RCRD&D | FY2022 | |
| Science-based development of ASTM standard tests for graphite-based fuel pebbles | University of California, Berkeley | $700,000 | This project proposes the development of mechanical test procedures as well as wear and friction tests on Graphite fuel pebbles | RCRD&D | FY2022 | |
| Role of Heterogeneity in Manganese and Nickel Rich Precipitate Distribution on Hardening of Reactor Pressure Vessel Steels: Integrated Modeling and Experimental Characterization | University of Florida | $799,803 | The hypothesis of this work is that the different nucleation and coarsening kinetics of manganese and nickel rich precipitates (MNPs) compared to copper rich precipitates, and the heterogeneous distribution of manganese and nickel rich precipitates on or near dislocations, both lead to unique hardening behavior at high neutron fluence. The objective of this work is to understand hardening in reactor pressure vessel steels caused by MNPs via integrated multiscale modeling and experiments. | RCRD&D | FY2022 | |
| Integrated Thermal-Electric Energy Management of All-Electric Ship with Advanced Nuclear Reactors | University of Texas at Dallas | $400,000 | The overall objective of this research is to comprehensively model, design, and evaluate the use of advanced nuclear reactors in future nuclear-powered ships, to enhance the efficiency, reliability, and resilience of shipboard energy distribution systems. The novelty of the proposed approach lies in (i) integrated thermal-electric modeling of advanced nuclear-powered shipboard energy system, and (ii) novel solutions for total-ship energy management to improve energy efficiency and resiliency. | RCRD&D | FY2022 | |
| Open Architecture for Nuclear Cost Reduction | University of Wisconsin-Madison | $800,000 | Open architecture has potential to reduce advanced reactor (AR) costs, through exploiting modular design and construction, with common, openly available interfaces between modules. A comprehensive assessment of the challenges and opportunities of open architecture for ARs will be performed. Supported by a pilot study, actionable recommendations for the implementation or otherwise of open architecture for ARs will be developed. | RCRD&D | FY2022 | |
| Telescopic Control Rod for Significant Reduction in HTR Height and therefore Cost | University of Wisconsin-Madison | $800,000 | This project proposes a design for a small modular High Temperature Reactor (HTR) control rod that extends telescopically, consisting of ~5 concentric annuli that nest together above the core when withdrawn. This compact component substantially reduces the length of the depth of the silo. Modelling and experimental testing will be performed to develop the control rod to evaluate feasibility, plus perform a cost-benefit analysis, with a view to its inclusion in both pebble bed and prismatic HTR designs. | RCRD&D | FY2022 | |
| NEUP Project 21-24394: Computer vision and machine learning for microstructural qualification | Carnegie Mellon University | $497,518 | Quantifying and understanding microstructure is a key driver for performance-based materials qualification. In this proposal, well-curated data sets of microstructural images will be gathered and computer vision and machine learning will be applied to build quantitative deep learning frameworks to accelerate and enable qualification of nuclear materials based on microstructural features. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-24156: Experimental thermofluidic validation of TCR fuel elements using distributed temperature and flow sensing | Kansas State University | $798,250 | The overall goal of this project will be to test the performance of 3D printed Transformational Challenge Reactor core geometry parts using existing Helium flow loops and distributed temperature, and velocity sensing systems. Thermal transport capabilities of scaled 3D printed ceramic core will be evaluated experimentally and measurements will be used to qualify computational models. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-24636: Risk-informed Consequence-driven Physical Protection System Optimization for Microreactor Sites | Texas A&M University | $400,000 | This proposed project will utilize a risk-informed, consequence-driven analysis to develop an approach for "right-sizing" physical protection systems (PPS) for microreactors. The hypothesis presented for this proposal is that the explicit coupling of consequence modeling to PPS design will provide a similar benefit that can be applied prior to reactor construction. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-24131: Total Mass Accounting in Advanced Liquid Fueled Reactors | The Ohio State University | $400,000 | A total mass determination method for nuclear materials accounting (NMA) in liquid-fueled molten salt reactors will be validated with fuel-bearing salt, mixed with a + radioisotope of known activity, that will be irradiated to reproduce the practical NMA scenario in a molten salt loop. Irradiated fuel salt will be sampled and measured for its mass and activity. The mass-to-activity ratio will be used to calculate the unknown salt mass in the original container. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-24037: Design and intelligent optimization of the thermal storage and energy distribution for the TerraPower Molten Chloride Fast Reactor in an Integrated Energy System (IES) | University of Tennessee at Knoxville | $800,000 | The objective of this project is to explore the application of advanced reactors within Integrated Energy Systems, use extensive existing data from UIUC for model development and validation, and extend the predictions to larger grids and commercial applications. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-24522: Targeted Materials Characterization and Testing of Additively Manufactured Metals and Ceramics to Inform Print/Build Data Analytics | University of Texas at San Antonio | $800,000 | A collaborative program between the University of Texas at San Antonio and Boise State University is proposed to supply materials testing and characterization data sets to be leveraged by the TCR program to inform build/print data analytics. With the data provided by the proposing team, correlations among steam oxidation performance, micromechanical properties, chemical composition, local microstructure, and location specific print/build data will be achieved. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-24431: Location-specific material characterization of LPBF SS316L & IN718 TCR core structural materials | Utah State University | $800,000 | In this proposed work, we will experimentally characterize the spatial variability of the quasi-static (tensile), creep (strength and impression), and creep-fatigue properties as well as the underlying structures (microstructure and defect structures) for LPBF SS316L and IN718 components to be used as training data to the TCR program data-driven model. The resulting correlation will be used to drive the design process for an application as TCR core structural materials. | Crosscutting Technologies | FY2021 | |
| NEUP Project 21-23978: Rapid, Non-Radioactive Methods for Prediction and Quantification of Radiolytic Radical Decomposition Products in Nuclear Separations | Clemson University | $399,999 | High-throughput, non-radioactive, radical assays will be used to determine decomposition of monoamide separations complexants. Radical assay res |