SCALE Analysis of a Fluoride Salt-Cooled High-Temperature Reactor in Support of Severe Accident Analysis ORNL Report March, 2022
SOURCE TERM AND DEPLETION COUPLING WITH DYNAMIC SYSTEM MODELING SOLUTIONS FOR FUEL CYCLE OPERATIONS Conference Paper March, 2022
Nuclide Inventory Benchmark for BWR Spent Nuclear Fuel: Challenges in Evaluation of Modeling Data Assumptions and Uncertainties Journal January, 2022
