A Comparative Study of Two Nanoindentation Approaches for Assessing Mechanical Properties of Ion-irradiated Stainless Steel 316

A Comparison of Ring Pull and Axial Tensile Tests of HT-9 and 14YWT Thin-walled Tubes

A Virtual Experiment Approach to Positron Annihilation Spectroscopy

Alpha Self-Irradiation of Archive and Irradiated Fast Reactor Fuels

Changes in the Starting Microstructures of U-Mo Fuels due to the Effects of Neutron Irradiation

Comparison of Radial Microstructural Changes in Fast Reactor MOX Fuels Across Varying Burnup Profiles

Controlling Helium Morphology in Pure Metals: Toward Uniform Samples for the Accelerated Measurement of Bulk Irradiated Properties

Defect Evolution and Radiation Resistance of Advanced Fusion Materials Under Heavy Ion and Low Energy Helium Irradiation

Development of Advanced Low N-12Cr (wt.%) Ferritic/Martensitic Steel for Reactor Applications

Diffusion Analysis of Metallic Fission Products in Tristructural-isotropic Coated Fuel Using Representative Diffusion Couples

Diffusion of Fission Products in Virgin Nuclear Graphite

Direct Measurement of Radiation Damage Through the Energy Stored in Defects: Simulations and Experiments

Effective Defect Sinks in Metallic Composite with Nanodispersoids: In situ Ion Radiation Transmission Electron Microscopy and Position Annihilation Lifetime Spectroscopy

Fabrication and Characterization of Massive Crack-free Delta Phase-zirconium Hydride for High-performance Moderator Application

Fabrication and Charaterization of High Burnup Nuclear Fuel Surrogate for the Anlysis of Fuel Fragmentation Phenomenon

H-1 (Invited): Modeling the Uranium-Silicon Phase Equilibria

H-10: Radiation Response of HT9 Ferritic/Martensitic Alloys as a Function of Interstitial Content

H-2: Characterization of Helium Implanted Single Crystal Titanium

H-3: Femtosecond Laser Machining of Micro-Scale Structures

H-5: Effects of Helium Ion Irradiation on Single Crystal Vanadium

H-8: Mechanical Properties of Ion Irradiated and Helium Implanted HT9 Micropillars

H-9: Microstructure and Mechanical Behavior of Directed Energy Deposition Laser Additively Manufactured T-91

High-Throughput Synthesis and Ion Irradiation of High-Entropy Alloys using Additive Manufacturing

Impact of Ionization Effects and Defect Trapping on Microstructure Evolution in Light Ion Irradiated Uranium Dioxide

In-situ Heavy Ion Irradiation of FCC and BCC High-entropy Alloys at Cryogenic and High Temperatures

In-situ Neutron Characterization of Advanced Nuclear Fuels - The Road to a New Neutron Irradiation Testing Capability

In-situ Observation of Radiation-induced Phase Transformation in U-Mo

In-situ Studies on the Mechanical Properties of He Ion Irradiated Nanotwinned Ag

Irradiation Behavior of Mechanically Processed Zr-Nb Multilayers at Very High Doses

Kinetic Study on the Evolution of Nano-ceramic Coatings Under Heavy Ions Irradiation

Mechanical Characterization of Three Neutron Irradiated HT-9 Heats (ORNL, LANL and EBR II) at LWR and Fast Reactor Relevant Temperatures

Microstructural and Micro-chemical Characterization of Safety Tested TRISO UCO Fuel Kernels Irradiated in the Advanced Test Reactor

Microstructural Changes and Corrosion of Proton-pre-irradiated Hastelloy N in FLiNaK Molten Salt

Microstructure of HT-9 Cladding After fuel-cladding Chemical Interaction with an Annular U-10Zr Fuel Irradiated to 3.3% FIMA

Multiple Scale Mechanical Testing of Neutron Irradiated FeCrAl Alloys

Neutron Irradiation Damage and Fission Product Transport in the SiC Layer of TRISO Fuel Particles

On a Theory Based Accelerated Testing Methodology for Swelling

On the Role of Heterogeneity in Concentrated Solid‒solution Alloys in Enhancing their Irradiation Resistance

Rapid Investigation of Irradiation Temperature Sensitivity Using Charged Particles

Recent Applications of Ex-situ Transient Grating Spectroscopy to the Study of Radiation-induced Degradation of Nuclear Materials

Small Scale Mechanical Testing of Ceramic Interfaces in Nuclear Materials: Characterizing the Impact of Elastic Mismatch on Stress Intensity and Property Extraction

Synthesis of Intermetallic UZr2+x and Its Phase Transformation

Temperature Shift Evaluation for G-phase Clustering in Ferritic-martensitic Alloys

Testing of Nuclear Fuels and Materials in the Advanced Fuels Campaign

Three-dimensional Analysis of the IPyC/SiC Interface in Irradiated TRISO Fuel Particles

Questions about ProgramMaster? Contact programming@programmaster.org