3D X-Ray Micro-Tomography Imaging-Based Study of PYCASSO TRISO Fuel Particles

A Comparative Study of the Third Element Effect in FeCrAl Oxidation and Corrosion

A Phase-Field Model for Studying Palladium Attack of SiC In TRISO

Advanced Characterization of Irradiated FAST U-10Zr Rodlets Using Transmission Electron Microscopy and Atom Probe Tomography

Advanced Electron Microscopy Characterization of the Fuel-Cladding Chemical Interaction Region in a High Burnup U-10Zr Fuel

An Irreducible Derivatives Approach to Improve Empirical Interatomic Potentials for Thermophysical Property Predictions: the Case of ThO2 and UO2

Arc-Melt Synthesis of Uranium Borides: A New Approach to Volatilization

Assessing the Microhardness of Medium and High Burnup U-Mo Dispersion Fuel and Matrix Al Using Nanoindentation on FIB-Prepared Microcubes

Assessing Thermochemical Stability and Fission Product Mobility in Advanced Nuclear Fuels

Atomistic-Scale Simulations to Predict Creep Rates in Doped UO2

Bayesian Calibration of Ab-Initio Based Self- and Fission Gas Diffusivity in UN Nuclear Fuel

Characterization and Modeling of Joint Oxyde-Gaine and Inner Cladding Corrosion in Fast Reactor Fuels

Chemical Compatibility of UC/UO2 Composites for Accident Tolerant Fuel

Cluster Dynamics Modeling of Interstitial Loop Evolution and Unfaulting Process in Proton-Irradiated Single Crystal ThO2

Comprehensive Fracture Property Analysis of High Burnup UO2 Fuels Using Multiscale Phase-Field Fracture Modeling

Computational Studies of Radiation Induced Segregation in Metallic Alloys

Correlation of Thermal Properties with Local Microstructure of Irradiated Sodium-Bonded U-Zr Metallic Fuel

Deep Learning Potential for Exploring High‑Temperature Properties of Yttrium Hydride

Density Functional Theory Study of Charge Distribution and Transport at Metal-ZrO2 Interface

Density Functional Theory Study of Helium Diffusion in Ni-M alloys (M= Cr, Mo)

Developing a Parallelized Thermal Characterization Method for TRISO Fuel Compacts

Development of a Macroscopic Model of Irradiation-Enhanced Densification

Development of Coated Particle Fuels with New Architectures for an Expanded Service Envelope

Development of Elemental Technologies for Application of SiC Fuel Cladding to BWR

Direct Modeling of Irradiation Driven Microstructure Evolution and Swelling in Uranium Nitride

Dynamic System Sensitivity Analysis of Burnup Accelerated UO2 and Cr2O3 Doped UO2 Rodlet Fission Gas Release

Effect of FIB Damage on the Defect Evolution in Ceramic Fuels Under In-Situ TEM Annealing

Effects of Charge State on Chromium Substitution and Oxygen Vacancy Segregation Energies at Grain Boundaries in Uranium Dioxide

Evaluating Effect of Layer Cracking And Interfacial Debonding on Triso Fission Product Diffusion and Thermomechanical Performance

Evolution of Sputtered Protective Bilayer Coatings Under LOCA Steam Exposure

Examining Constituent Redistribution in U-19Pu-10Zr Fuel as it Evolves with Local Burnup

Experimental and Theoretical Study of He-Irradiated Zr/Nb Nanoscale Multilayers

Faulted Loop Formation by Rapid 1D Migration of Interstitial Clusters in ThO2: Insights from Molecular Dynamics Simulations

First Principle Based Modeling of the Impact of Dislocation Loops on the Thermal Transport of Nuclear Fuels

Fission Gas Behavior Modeling at High Burnup in UO2

Fission Product Distribution Analysis in Zr Lined U-Mo Fuels Using Transmission Electron Microscopy and Atom Probe Tomography

Fission Product Migration and Speciation in Uranium Mononitride SIMFUEL

Guarded Comparative Longitudinal Heat Flow Rig to Study Gap Conductance Between Nuclear Fuel and Cladding

High Temperature Creep Behavior of Uranium Oxide: Crystal Plasticity Modeling and Experiments

Impact of Short-Range Order on Thermodynamic Properties of Point Defects in UMo Fuels

Impact of Uranium Feedstock Impurities on the Microstructure and Oxidation Resistance of Uranium Nitride (UN)

Implications of Accurate Point Defects Estimation on UO2 Thermal Conductivity and Fission Gas Release for Accelerated Fuel Irradiation

Improving Radiation and Corrosion Resistance of Cr-Based Coatings Through Structural and Compositional Optimization

In-situ Irradiation of Uranium Carbide and Zirconium Carbide

In-situ Thermal Conductivity of Uranium Nitride (UN) and SIMFUEL Composites Under Irradiation

Investigating Microstructural and Local Thermal Conductivity Changes in Irradiated U-Zr Annular Fuel

Investigating Microstructural Effects on TRISO Fuel Mechanics via Multiphysics and Multiscale Modeling

Investigating Porosity and Swelling Evolution in Uranium-10wt%Zirconium Fuels Under Varied Irradiation Conditions

Investigating the Effect of Grain Growth Additive Incorporation on the Microstructure and Radiation Stability of UO2 Fuels

Investigation of Fuel Cladding Chemical Interactions with UO2 and Doped UO2 Using Diffusion Couples

Investigation of the Creep and Fracture Behavior of Irradiated UO2 Fuel Through Density Functional Theory (DFT)

Irradiation-Induced Formation of High- and Low-Angle Grain Boundaries, Microcracking, and Fission Gas Release

Kernel Composition and Variability Influence on TRISO Fuel Behavior

Material Characterization and Pellet Cladding Interaction Performance of Optimized ZIRLO™ with Liner

Methods of Implmentation and Sequestration of Iodine in UO2 Fuels

Micromechanical Characterization of AGR-2 TRISO-Coated Particle Buffer, IPyC, and SiC Interfaces

Microstructural Impacts of Dopants in Advanced Nuclear Fuels

Microstructurally Informed Modeling of Fragment Size in the BISON Fuel Performance Code

Microstructurally Informed Modeling of High Burnup Structure in UO2 Fuel

Mitigating FCCI in Metallic Fuels: Evaluating Cladding Liners with Multiscale Modeling

Multimodal Investigation of the Neutron Induced Defect of SiC/SiC Composites

Multiphysics and Multiscale Modeling of High Burnup UO2

Multiscale Fuel Performance Modeling of U-Mo Fuel for Research Reactors

Nanostructured U-Mo Based Metallic Fuels for Fast Reactors – Electronic Structure Calculations and Machine Learning

Numerical Modelling of Delayed Hydride Cracking in Nuclear Material Using the Phase Field Modelling

Obtaining the Chemical Information of Secondary Phases and Precipitates Induced by Fission Products in FCCI Region of a High Burnup Metallic Fuel using Nano SIMS and TEM-EELS

Oxygen Potential and Uranium Diffusion in UO2±x: Density Functional Theory Calculations Including Spin-Orbit Coupling Effect and Dispersion Interactions

Pebble Integrity in Action: Robust Testing for Safe Refueling

Phase-Field Modeling of Constituent Redistribution in U-Zr Metallic Fuel Considering Porosity Effects

Phase-Field Modeling of Fission Fragment Track Effects on Nucleation and Re-Solution of Fission Gas Bubbles in UO2

Phase Evolution of Neutron-Irradiated U-Mo Alloys at Low Temperature in the Low-Fluence Regime

Pipe Diffusion Along Edge Dislocation in UO2 and UN Nuclear Fuels

Point Defect Mobility and Phase Stability of Novel UZrCN Nuclear Fuel from First Principles

Polyepitaxial Approach to Studying Topotactic Phase Transitions in Actinides

Recent Progress on Ceramic Coating Development for Advanced Cladding

Recent Transient Fission Gas Results from High Burnup UO2 Under Severe Accident Conditions

Room Temperature Oxidation Mechanisms of Uranium Monocarbide

Stability of the U-Zr δ-Phase

Synthesis of Uranium Dinitride by Ammonolysis of Uranium Tetrafluoride

The Thermal Mechanical Properties and Transient Behavior of High Burn-Up Structure Pure and Cr2O3-Doped UO2 Pellets with Xe Gas Bearing Under the LOCA and RIA Thermal Shock Tests

Thermal Properties Degradation in Proton Irradiated Cr-Doped UO2

Thermal Response and Mechanical Integrity of High Temperature Cr-Coated Zr Cladding Under Multiple Quench Tests

Tracking Structure Evolution and Alloy Element Redistributions During Zircaloy-4 Oxidation via Complementary In-Situ XRD, Ex-Situ Electron Microscopy, and Atom Probe Tomography

UN-UB2 Fuel Material: A Path to UN Use in LWRs

Understanding Burnup Effects on UO2 Mechanical Behavior Using Surrogate Materials

Understanding the Impact That the UO2 Radial Microstructural Evolution has on Temperature Transient Performance in LWR Pellets

Understanding the Process-Microstructure-Property Relationship of FeCrAl Alloy Deposited via L-DED

Unraveling the Mechanisms of Oxide Texture Formation on Zirconium Alloys

Uranium-Containing Refractory Multiple Principal Element Alloy Characterization for High Temperature Metallic Fuel

Westinghouse Perspective on Accelerated Fuel Qualification

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