Identifying high-impact and high-uncertainty parameters in MiniFuel model predictions Journal May, 2025
Development of Large Bore Rabbit Capsules in Support of BWR Cladding Irradiations in HFIR ORNL Report May, 2025
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
Critical response to M. Worrall et al. Published in Annals of Nuclear Energy 207 (2024) 110731... Journal February, 2025
Phase stability and microstructure of neutron-irradiated substoichiometric yttrium dihydrides Journal January, 2025
Development of Commercial-Length Nuclear Fuel Post-Irradiation Examination Capabilities at the Oak Ridge National Laboratory... Conference Paper September, 2009
An Expanding Plug Test Method for Determining Hoop Stress-Strain Curves of Irradiated Nuclear Fuel Cladding... Conference Paper September, 2009
