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
SCALE 6.3.1 Radiation Source Terms and Shielding Analysis for a Postulated Sodium-Cooled Fast Reactor Accident Scenario Conference Paper April, 2024
SCALE depletion capabilities for molten salt reactors and other liquid-fueled systems Journal February, 2024
Optimization of the Second Target Station cold source moderators using an automated workflow Journal January, 2024