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
Facility to Alleviate Salt Technology Risks (FASTR): Preliminary Design Report with Failure Modes and Effects Analysis ORNL Report December, 2019
Reactor performance and safety characteristics of ThN-UN fuel concepts in a PWR... Journal December, 2019
