History of Pu-238 Production Restart Efforts at Idaho National Laboratory and Oak Ridge National Laboratory Journal November, 2024
A study on the impact of using a subchannel resolution for modeling of large break loss of coolant accidents Journal November, 2024
NON-DESTRUCTIVE POST IRRADIATION EXAMINATION OF FIRST CYCLE ACCIDENT TOLERANT AND ADVANCED ZIRCONIUM ALLOY HIGH BURNUP FUEL RODS Conference Paper October, 2024
BISON VALIDATION TO PRESSUREIZED WATER REACTOR HIGH-BURNUP POST-IRRADIATION EXAMINATION DATA Conference Paper October, 2024
METHOD FOR EXPOSING IRRADIATED FUEL CLADDING TO RAPID THERMAL TRANSIENTS Conference Paper October, 2024
DEVELOPMENT OF TRANSIENT FISSION GAS RELEASE CAPABILITIES TO STUDY HIGH BURNUP COMMERCIAL FUEL PERFORMANCE UNDER LOSS OF COOLANT ACCIDENT CONDITIONS Conference Paper October, 2024
SAFETY AND PERFORMANCE ASPECTS IN THE DEVELOPMENT AND QUALIFICATION OF HIGH BURNUP NUCLEAR FUELS FOR WATER COOLED REACTORS... Conference Paper October, 2024
THE U.S. ACCIDENT TOLERANT FUELS PROGRAM: RECENT ACCOMPLISHMENTS SUPPORTING IMPLEMENTATION Conference Paper October, 2024
FY24 Progress Report on Viscosity and Thermal Conductivity Measurements of Nuclear Industry Relevant Chloride Salts: An Experimental and Computational Study ORNL Report October, 2024
Characterization of Fuel and Cladding In and Near the Pellet-Pellet Gap of a High-Burnup Pressurized Water Reactor Fuel Rod Conference Paper October, 2024
