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
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Methodological guidelines on concrete degradation based on predictive models and the release of MOSAIC for industry use ORNL Report March, 2024
An Assessment of Machine Learning Applied to Ultrasonic Nondestructive Evaluation... ORNL Report March, 2024
Sister Rod Destructive Examinations (FY23) Appendix G: CIRFT Uncertainty Calculations ORNL Report March, 2024