DEVELOPMENT OF A GRAPHITE IRRADIATION QUALIFICATION PLAN FOR THE XE-100 REACTOR Conference Paper July, 2023
Report on initial development of a database of nuclear graphite characteristics based on microstructural characterization ORNL Report July, 2023
Post Irradiation Examination of Pressurized Water Reactor Stainless Steel Internal Components Conference Paper July, 2023
Investigation on the explosion dynamics of large-format lithium-ion pouch cells... Journal June, 2023
Non-destructive characterization of advanced nuclear fuel materials using neutron imaging Journal June, 2023
Internal carburization and scale formation on austenitic steels in supercritical carbon dioxide Journal June, 2023
An innovative carbonated cementitious material and its printability and carbon mineralization capacity... Journal June, 2023
Predicting the creep-rupture lifetime of a cast austenitic stainless steel using Larson-Miller and Wilshire parametric approaches Journal June, 2023
Flash Diffusivity Measurement of Semi-Porous Insulation Material Intended for Radioisotope Thermoelectric Generators Conference Paper June, 2023
