Cumulative χ2 Metric for VALID for ENDF/B-VII.1 and ENDF/B-VIII.0 in SCALE 6.3b9... Conference Paper December, 2021
Evaluation of Oak Ridge National Laboratory Health Physics Research Reactor Operation Data for Criticality Accident Alarm System Benchmark Creation Conference Paper December, 2021
Reactor Cell Neutron Dose for the Molten Salt Breeder Reactor Conceptual Design... Journal November, 2021
Development of a Fast-Spectrum Self-Powered Neutron Detector for Molten Salt Experiments in the Versatile Test Reactor Conference Paper November, 2021
Skyshine Calculations for a Large Spent Nuclear Fuel Storage Facility with SCALE 6.2.3 Journal November, 2021