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
Review of SCALE Validations Applicable to Spent Nuclear Fuel Shielding Calculations ORNL Report December, 2022
Preliminary Data and Thermal Modeling of In Situ Wireless Sensor Irradiation in the High Flux Isotope Reactor Conference Paper December, 2022
A Parametric Study of Criticality in Dual-Purpose Canisters for Long-Term Disposal Conference Paper November, 2022
Overview of ORNL SCALE Shielding Analyses for Spent Nuclear Fuel Transportation and Storage Applications... Conference Paper November, 2022
A Method for Semi-Automated Point Cloud to Watertight Mesh Conversion for Rapid MCNP Input file generation of Indoor Scenes Conference Paper November, 2022
