Benchmark Gap Assessment for the Manufacturing of High-Assay Low-Enriched Uranium Fuels ORNL Report January, 2025
Credible Criticality Safety Margin in the 30B Package with LEU+ UF6 and Hypothetical Water Ingress ORNL Report October, 2024
Post-closure Criticality Control Optimization Scheme for RCCAs in As-Loaded Dual Purpose Canisters Considering Site Specific ... ORNL Report September, 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