A Study on the Characteristics of the Radiation Source Terms of Spent Fuel and Various Non-Fuel Hardware for Shielding Applications ORNL Report May, 2022
SCALE Analysis of a Fluoride Salt-Cooled High-Temperature Reactor in Support of Severe Accident Analysis ORNL Report March, 2022
Post-closure Nuclear Criticality Safety Evaluations for Disposition of Criticality Control Overpacks at the Waste Isolation Pilot Plant ORNL Report February, 2022
Fuel Assembly Reference Information for SNF Radiation Source Term Calculations ORNL Report September, 2021
