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
Validation of UNF-ST&DARDS As-loaded safety analysis methods for BWR decay heat calculations Journal January, 2022
Cumulative χ2 Metric for VALID for ENDF/B-VII.1 and ENDF/B-VIII.0 in SCALE 6.3b9... Conference Paper December, 2021
