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 April, 2024
SCALE depletion capabilities for molten salt reactors and other liquid-fueled systems Journal February, 2024
Neutron Absorber Plate Characterization Plan for Criticality Experiments Design Conference Paper November, 2023