3D-reconstruction via Genetic Algorithms: Application to Metallic Fuel

3D Reconstruction and Quantification of Oxide Nano-porosity in Zirconium Alloys

A First-principles Database Approach to Predicting Trans-uranic Waste Forms

A New Statistical Approach for Atomistic Calculations of Point Defect Formation Energies in Multicomponent Solid-solution Alloys

A Review of Current Understanding of Fluff Formation in Metallic Fuel via EBR-II Data and Modelling and Simulations.

A Study of the Corrosion Behavior of Cold-sprayed 304L Stainless Steel for Dry Storage Canisters

Accessing High Damage Level Microstructures Using Combined Ion and Neutron Irradiation of a 304L Stainless Steel

ACTINIS: Shielded SIMS for Analysis of Highly Radioactive Samples

Additive Manufacturing (AM) of Oxide Dispersion Strengthened (ODS) FeCrAl Using In Situ Oxidation

Advanced Manufacturing for Novel Material Design and Development

Advanced Technology Fuel Accelerated Development at Bangor University

An Investigation of FCCI Using Diffusion Couple Test between UMTZ Alloys and Cladding

Atom Probe Tomography for Nuclear Materials

Atom Probe Tomography Study of Elemental Segregation and Precipitation in Ion-irradiated Advance Austenitic Alloy A709

Atomic Scale Investigation of Thermodynamic and Defect Properties of (U,Pu)O2 Mixed Oxide

Atomistic Calculations on the Effective Bias of Cavities in BCC Fe

Beta Transmutations in Apatite with Ferric Iron as an Electron Acceptor – Implication for Nuclear Waste form Development

Calculation of Irradiation Enhanced Diffusivities Using Centipede

Cavity Formation in Ion Irradiated Fe and Fe-Cr Ferritic Alloys

Chemical Interaction and Incorporation of Lead with Uranium Nitride Fuels

Cluster Dynamics Simulations of Fission Gas and Product (Xe, Ag) Diffusivities in TRISO UCO Fuel Kernels

Cold Spray for Repair of Nuclear Power Plant Components

Comparison of Temperature-dependent Swelling Behavior in FCC Compositionally Complex Alloys and 316H Stainless Steel under Heavy-ion Irradiation

Constructing Multi-component Diffusion under Irradiation in U-Mo Alloys

Contextualizing Dispersoid Evolution within Friction Stir Welded and Ion Irradiated MA956

Correlating Properties of Irradiation Produced Nanoscale Superlattices with Irradiation Condition Parameters

Defect Cluster Configurations and Mobilities in α-zirconium: Implications for Breakaway Irradiation Growth

Defect Clustering in UO2 Doped Systems Studied Using XAS and Neutron Scattering

Deliquescence of Eutectic LiCl-KCl Diluted with NaCl for Interim Waste Salt Storage

Dependence of Sink Strength Effects on Defect Evolution in Dual-ion Irradiated Additive-Manufactured HT9

Design and Operation of an Out-of-pile Liquid Sodium Experimental Facility for Mechanical Testing

Design of a Test System for Hot Hydrogen-facing Components in Nuclear Thermal Propulsion Systems

Determination of Chromium Corrosion Potential in the Na-K-Mg-U(III) Chloride Molten Salt

Determination of Tritium Trapping Mechanisms in the TPBAR Aluminide Coating

Developing Neural Network Model for Automated Analysis of Radiation-induced Grain Growth in UO2

Development and Application of a UN Potential to Defect Properties and High Temperature Elastic Constants

Development and Application of an Interatomic Potential for the Investigation of Mixed Oxide Compounds Containing Americium

Development of a Multicomponent Ideal-solution (MCIS) Free Energy Phase-field Model for Simulation of Nuclear Materials Microstructural Evolution

Discerning the Effects of Solute Additions in FeCrAl on Dislocation Dynamics under Irradiation Using a Machine Learning Object Detection Algorithm

Dislocation Loop Evolution in Fluorite Oxides

Does the Fuel Fabrication Method Have an Impact on the Fuel Performance Microstructure in Uranium-molybdenum?

Dose and Temperature Effect on Dispersoids in Neutron Irradiated Oxide Dispersion Strengthened (ODS) Alloys

Effect of Cr and Temperature on Dislocation Loops in Heavy Ion Irradiated Ultra-high Purity FeCr Alloys

Effect of Damage Rate and Cascade Size on α' Precipitate Stability in Fe-15Cr

Effect of Helium Injection Rate on Cavity Microstructure in Dual Ion Irradiated T91 Steel

Effect of the Inner Liner on Radial Delayed Hydride Cracking

Effects of Heat Treatment, Build Angle and Radiation Type on the Hardness and Microstructure of Inconel 625 and 718 Fabricated via Laser-powder Bed Fusion Additive Manufacturing

Electron Probe Microanalysis of Fuel from EBR-II Experiment X441A: Effects of Varying U:Pu:Zr Elemental Ratios

Explorations in Automated Cavity Detection Using an Expanded Machine Learning Training Data Domain

Fabrication and Properties of Uranium Dioxide-uranium Boride Composites

Fabrication of Potentially High Burnup Annular U-10Zr Fuel by SPS

Finding a Balance in FeCrAl Alloys: Optimization of Alloy Chemistry for Balanced Properties

First-principles Study of the Interfaces between Gamma-U and Uranium Carbide

Fracture Mechanics-based Testing and DCPD in FLiNaK

Free Surface Impact on Radiation Damage in Pure Nickel by In-situ Self-ion Irradiation: Can It be Avoided?

Grain Growth and Mechanical Properties of Nano ZrO2 Oxide Dispersion Strengthened Mo30W

High Throughput Study of Hardening and Void Swelling in Ion Irradiated Compositionally Complex Alloys

How Does PUREX Actually Work and What Do Chemists Do?

IASCC Initiation Testing of ex-PWR Baffle-former Bolts

Identifying Crystalline Phases in Irradiated U-Pu-Zr Fuels Using TEM

Impact of Grain Boundary and Surface Diffusion on Fission Gas Release in UO2 Nuclear Fuel Using a Phase Field Model

Impact of Zirconium Concentration Variation on Metal Fuel Constituent Redistribution

In Situ Mechanical Testing Method for Materials in Gaseous Environments

Influence of Different Heat Treatments and Ion Irradiation on the Microstructural Evolution and Microhardness of Inconel 625 Fabricated via Laser-powder Bed Fusion

Innovative Elaboration Method of ODS Ferritic Steels Reinforced by Y2Ti2O7 Pyrochlore Phase Oxide

Insights into Prediction of Thermodynamic Properties for Chloride Salts for Generation IV MSRs

Instrumentation in Molten Salt Systems: Commercial Availability, Custom Solutions, and Gaps

Irradiation Creep and Fatigue Observed via In-situ Electron Microscopy

Kinetics of SiC Reaction with Water and Oxygen Under Light Water Reaction Conditions

MAX Phases for Nuclear Applications

Mechanical Behavior of Additively Manufactured 316L Stainless Steel and SiC before and after Neutron Irradiation

Mechanical Response of HT9 and T91 under Dual-ion and Neutron Irradiations

Mechanical Testing of Fuel Cladding Tubes

Mesoscale Simulations of Interactions between Dislocation Loop and Point Defects in bcc Iron

Mesoscale YellowJacket: A Phase-field Model for Microstructure Dependent Corrosion of Ni-Cr Alloys by Molten Fluoride Salts

Metal Hydride Moderator Development at Los Alamos National Laboratory

Microstructural Analysis of Oxidized Tristructural Isotropic Particles (TRISO) in Mixed Gas Atmospheres

Mitigating Irradiated Assisted Stress Corrosion Cracking with Minor Refractory Element Modification – A High-throughput Approach Using Compositionally-graded Specimen

Modeling the Mechanisms of Fuel Pulverization Using Cluster and Molecular Dynamics

Molten Salt Thermal Properties Database-Thermochemical (MSTDB-TC) Status and New Assessment of MF-UF4 (M = Li, Na, K, Cs) Systems

Neutron Irradiation Effects on PM-HIP Inconel 625

New Microscopic Insights into the Fuel Cladding Interaction Layer of High Burnup Fuel

Next Steps for Improved Defect Production and Mixing Parameters: Beyond NRT DPA, ARC-DPA and RPA

Novel Nickel-based Alloys for Molten Salt Fast Reactor Structural Applications

Opportunities for Advanced Concepts in Nuclear Fuel Development

Overview of Fuel System Options for Nuclear Thermal Propulsion

Overview of in Reactor Mechanical Testing in the Versatile Test Reactor

Oxidation Performance of High Uranium Density Fuels for Light Water Reactors

Perovskite-derived Cs2SnCl6-Silica Composites as Advanced Waste Forms for Chloride Salt Wastes

Phase-field Simulations of Fission Gas Bubbles in High Burnup UO2 during Steady-state and LOCA Transient Conditions

Phase and Thermodynamic Analysis of Uranium Mononitride in High-temperature Steam Light Water Reactor Atmospheres

Physical Understanding of Radiation Hardening of Neutron Irradiated FeCr Alloys

Plutonium Defect Characterization through Mechanical Deformation

Point Defect Evolution under Irradiation: Finite Size Effects and Spatio-temporal Correlations

Predicting Phase Stability of Potential Actinide-bearing Hollandite Waste Forms Using First Principles Calculations

Pushing towards the Limits in Characterization of Radiation Damage

Quantifying the Impact of an Electronic Drag Force on Defect Production from High-Energy Displacement Cascades in α-zirconium

Radiation-decelerated Corrosion of Nuclear Structural Materials in Gen IV Reactor Environments

Radiation-induced Segregation in Nanocrystalline FeCrNi under Concurrent Grain Boundary Movement

Radiation Damages Bohr’s Metrics: The Elemental Landscape

Radiation Effects and Thermal Stability in Ferritic Steels and High Entropy Alloys

Radiation Enhanced Diffusion (RED) and the Coupled Effects of Irradiation and Corrosion in Fe2O3

Radiation Tolerance of Capacitive Discharge Resistance Welded 14YWT

Rapid Simulation of the Irradiated Microstructure in Flux Thimble Tubes to High Dose Using Ion Irradiation

Recent Advances in Pyroprocessing of Light Water Reactor Fuel

SKAPHIA: Presentation of the Latest Shielded Electron Probe Micro Analysis (EPMA)

Solute Segregation and Precipitation Across Damage Rates in Dual Ion Irradiated T91 Steel

Strengthening Effects across Ultrasonic Additive Manufacturing (UAM) Interfaces

Structural Materials Testing for the Westinghouse Lead Fast Reactor

Study on Role of Irradiation Induced Vacancies and Voids on Strain-induced Martensitic Transformations by Molecular Dynamics

Suppressing Irradiation Instabilities in Nanocrystalline Tungsten through Grain Boundary Doping

Synthesis of UN-U3Si2 Composite Fuels by Spark Plasma Sintering and Properties Characterization

Temperature-controlled Friction Stir Welding: A Potential Crack Repair Technology for 304L Stainless Steel Spent Nuclear Fuel-dry Storage Canisters (SNF-DSC)

The Challenges of α-uranium: Fundamental Understanding of a Past and Future Nuclear Fuel Material

The Effect of Phase Structure on the Aqueous Corrosion of Yttrium Disilicate

The Kinetics and Stability of Alpha Prime (α’) Precipitates in FeCr Binary Alloy under Ion Irradiations

The Role of Alloying Species on Radiation Tolerance of BCC Fe Binary Alloys

The Subtle Effects of Nitrogen on Radiation Effects in Tempered Martensitic Steels

The Xe-100 Advanced Reactor Concept

Thermal Analysis of Advanced Nuclear Fuels during Simulated Off-normal Events

Thermal Annealing and Irradiation Behavior of Ultrafine-grained and Nanocrystalline FeCrAl Alloys

Thermal Diffusivity of Nuclear Materials at the Miniature Scale

Thermal Gradient Effect on the Helium and Intrinsic Defects Transport Properties in Tungsten

Three-dimensional Characterization of Microstructural Features in Oxide Fuels

Three-dimensional Characterization of Pore Evolution in High-burnup U-Mo

Transmission Electron Microscopy of the Uranium-22.5 Atom% Zirconium System Following Casting, Cold-working, and Annealing

Ultra-fine Lattice Wicking Structures Additively Manufactured from Tungsten

Understanding Tritium Permeation in FeCrAl Alloys

Utilization Potential for the Molten Salts Thermal Properties Database – Thermochemical (MSTDB-TC) in Operational and Safety Analysis for MSRs

Wear and Friction Behavior of Fuel Pebbles in Molten Fluoride Salt

What’s Driving the Acceleration of Nuclear Materials Technology?

Questions about ProgramMaster? Contact programming@programmaster.org