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
DEVELOPING AND SCALING AN OPENFOAM MODEL TO STUDY TURBULENT FLOW IN A HFIR COOLANT CHANNEL ORNL Report March, 2024
Methodological guidelines on concrete degradation based on predictive models and the release of MOSAIC for industry use ORNL Report March, 2024