A First-principles Investigation on the Co-segregation Energetics of Chromium-helium at Grain Boundaries in α-Fe

A Machine Learning Approach to Thermal Conductivity Modelling of Irradiated Nuclear Fuels

A Micromechanics-based Modeling Approach to Predict the Mechanical Properties of Zircaloy with Hydride Precipitates

A Physical Model of Zircaloy Corrosion in Water for Simulating Nuclear Reactor Clad Response

Ab-initio Molecular Dynamics Simulations of bcc U and U-Zr Alloys

Amorphous Zirconia: a Host for Excess Oxygen in Cladding Barrier Oxides?

Analyzing U-Zr Experimental Data Using Quantitative Phase-field Simulation and Sensitivity Analysis

Application of Variational Bayesian Monte Carlo Method for Improved Prediction of Doped UO2 Fuel Performance

Atomistic Studies of Nuclear Materials with Temperature: Uranium Nitride and Thermocouples

Atypical Melting Behaviour of (Th,U)O2, (Th,Pu)O2 and (Pu,U)O2 Mixed Oxides

Corrosion of Silicon Carbide in Nuclear Environments

Density Functional Theory Study of He/H Effect in W-Ni-Fe Composite for Plasma Facing Material

Developing Capabilities to Investigate the Effect of Curvature on the Radiation Response of Solid-state Interfaces

Development and Testing of Machine Learning Interatomic Potentials for Radiation Damage Calculations

DFT Calculations for Modeling Point Defect and Fission Gas Behavior in Nuclear Fuels

DFT+U Point Defect Calculations of Uranium Mononitride

Diffusion and Interaction of Prismatic Dislocation Loops in Stochastic Dislocation Dynamics

E-33 (Invited): Development of a New Thermochemistry Solver for Multiphysics Simulations of Nuclear Materials

E-34: Ab-initio Modelling of Iodine Defects in Strained Zirconium and Ordered Zirconium-oxygen Suboxides

E-36: ICME Modeling of U-10%wt Mo Alloys: A Linkage between Microstructure Evolution and Process Modeling

E-37: Machine Learning-assisted Risk-informed Sensitivity Analysis for ATF Under SBO

E-38: Mesoscale Modeling of High Burn-up Structure (HBS) Formation and Evolution in U-Mo Alloys

E-39: Molecular Dynamics and Phase-field Study of Anisotropic Grain Growth Behavior in UO2

E-40: Origin of Hardening in Spinodally-decomposed Fe-Cr Binary Alloys

E-41: Recrystallization and Grain Growth Simulations for Multiple-pass Rolling and Annealing of U-10Mo

E-44: The Contribution of Li Vacancies to the Evolution of Thermal Conductivity in Irradiate LiAlO2

E-45: Thermodynamics of Hydrogen Pickup in Zr Alloys

Electron-phonon Coupling Effects in Ion Irradiation of Metallic Systems

Exploration of Fundamental Radiation Effects Phenomena in Materials

First-principles Cluster Expansion Study of Fe and Mo Effects on Atomic Ordering in Ni-Cr Alloys

First Principle Studies of Effects of Solute Segregation on Grain Boundary Strength in Ni-based X-750 Alloy

First Principles Modeling of Ion Ranges in Self-irradiated Tungsten

First Principles Modelling of the Role of Electrons in Collision Cascades in Solids

Influence of Coordination Numbers on Representing Molten Salts for Nuclear Reactor Applications Using the Modified Quasi-Chemical Model (MQM)

Mesoscale Modeling and Experiments for Predicting the Thermal Conductivity of UZr Fuels

Microstructure-based Finite Element Model to Investigate the Effect of Grain Size and Homogenization on Hot-rolled U-10Mo

Modeling of Interface Evolution during Zirconium Alloy Corrosion

Modeling the Fracture of Zirconium at an Atomic Level and Analyzing the Effects of Temperature and Strain Rate on the Deformation Mechanisms

Molecular Dynamics Simulations of Mixed Materials in Tungsten

Molecular Dynamics Simulations of Phosphorus Migration in a Grain Boundary of α-iron

Molecular Dynamics Studies of Thermal Conductivity Degradation of UO2 due to Dispersed Xe Atoms and Xe Bubbles

Phase-field Simulation of Intergranular Fission Gas Bubble Growth in Uranium Silicide

Plasticity of Zirconium Hydrides: an Edge and Screw Planar Discrete Dislocation Model

Recent Development of Thermochimica for Simulations of Nuclear Materials

Reduced Order Modeling of Thermal Creep in 316H Stainless Steel

Shape and Stability of Voids and Fission Gas Bubbles in UO2

Stabilizing Gamma Hydrides in Zr through Mechanical Stress

The Effect of Minor Additives on Radiation Induced Segregation in Austenitic Steel Alloys

The Use of Molecular Dynamics Simulations for Modeling Gas - Point Defect Interaction Behavior in Nuclear Materials

Thermochemical and Phase Equilibria (CALPHAD) Modeling of Nuclear Fuel Materials: A Constant in Reactor Development

Thermodynamic Properties at the Rim in High Burnup UO2 Fuels

Zirconium Alloy Cladding Burst Mechanisms under LOCA with Burnup Extension

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