Impact of recent ENDF nuclear data update, high initial enrichment and high burnup fuel on critical experiments applicability determination via the integral index ck for burnup credit validation Journal November, 2025
SCALE Analyses of Scenarios in the TRISO-based Heat Pipe Microreactor Fuel Cycle ORNL Report July, 2025
Design of a separate effects MiniFuel irradiation experiment investigating microstructure evolution in high burnup UO2 Journal May, 2025
Design of Critical Experiments Involving Graphite elements at the IPEN/MB-01 Plate-Type Core ORNL Report May, 2025
Swelling and Fission Gas Release of U-10Mo and U-17Mo Following Neutron Irradiation at 250 – 500°C Journal April, 2025
Unresolved resonance parameter evaluation and uncertainty quantification of n+181Ta reactions Journal March, 2025
