Effect of Decay Time on Criticality Safety Analyses for High Burnup and Extended Enrichment Fuels Conference Paper July, 2024
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
Nuclear Data–Induced Uncertainties in Criticality Safety Analyses for High-Burnup and Extended Enrichment Fuels Journal June, 2024
Impact of Increased Monte Carlo Parameters on Sensitivity Calculations with SCALE... 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
