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
Coupling SCALE with DAKOTA for Axial Burnup Profiles Assessment in Burnup Credit Conference Paper November, 2023
Critical Experiments Targeting the Epithermal/Intermediate Cross Sections of Tantalum Conference Paper November, 2023
Neutron Absorber Plate Characterization Plan for Criticality Experiments Design Conference Paper November, 2023
