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
Reactor Cell Neutron Dose for the Molten Salt Breeder Reactor Conceptual Design... Journal November, 2021
UNF-ST&DARDS: A UNIQUE TOOL FOR SPENT NUCLEAR FUEL CHARACTERIZATION AND LONG-TERM FUEL DATABASE MANAGEMENT Conference Paper October, 2021
Free Gas Elastic Scattering Algorithm for GPU-Based Particle Tracking... Conference Paper October, 2021
Spatially Dependent Resonance Self-Shielding Capability For Non-Uniform Temperature Profile In SCALE-6.3 XSPROC-BONAMI Conference Paper October, 2021
Improvement Of The SCALE-XSPROC Capability For High-Temperature Gas-Cooled Reactor Analysis Conference Paper October, 2021
