Current Overview of Neutron Moderator Thermal Scattering Kernels for HALEU-Fueled Advanced Reactors... Conference Paper June, 2024
Review of Available Critical Experiments and Critical Experiments Facilities to Perform High-Assay Low-Enriched Uranium Fuel Transport Validation for Advanced Reactor Deployment Conference Paper June, 2024
Hypothetical Sodium-Cooled Fast Reactor Fuel Transport Using the Existing ES-3100 ORNL Report May, 2024
SCALE 6.3 Modeling Strategies for Reactivity, Nuclide Inventory, and Decay Heat of Non-LWRs ORNL Report May, 2024
Comparison of Temperature-Dependent Cross Section Treatments Within the Shift Monte Carlo Radiation Transport Code ORNL Report April, 2024
Scoping Studies on the Impacts of Increased Enrichment on Nuclear Criticality Safety... ORNL Report April, 2024
SCALE depletion capabilities for molten salt reactors and other liquid-fueled systems Journal February, 2024