Design of a separate effects MiniFuel irradiation experiment investigating microstructure evolution in high burnup UO2 Journal May, 2025
Swelling and Fission Gas Release of U-10Mo and U-17Mo Following Neutron Irradiation at 250 – 500°C Journal April, 2025
Californium-252 production at the High Flux Isotope Reactor − I: Validation study using campaign data Journal February, 2025
Status of GPU capabilities within the Shift Monte Carlo radiation transport code Conference Paper January, 2025
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
