Nathan Capps Contact CAPPSNA@ORNL.GOV All Publications The impact of chromium coatings on Zircaloy cladding deformation behavior under reactivity-initiated accident-like mechanical loading conditions Recrystallization driven softening and heating rate dependencies of FeCrAl nuclear fuel cladding during accident transients Identifying high-impact and high-uncertainty parameters in MiniFuel model predictions Design of a separate effects MiniFuel irradiation experiment investigating microstructure evolution in high burnup UO2 Step-loaded creep testing of Zircaloy-4 cladding at higher temperatures in the α-phase High-burnup boiling water reactor steady-state operating conditions and fuel performance analysis Status of the Fuel Fragment Dispersal Studies at Oak Ridge National Laboratory... A study on the impact of using a subchannel resolution for modeling of large break loss of coolant accidents MECHANICAL BEHAVIOR OF FRESH, HYDRIDED, AND Cr-COATED CLADDING TUBES AND SUB-SIZED FLAT SPECIMENS NON-DESTRUCTIVE POST IRRADIATION EXAMINATION OF FIRST CYCLE ACCIDENT TOLERANT AND ADVANCED ZIRCONIUM ALLOY HIGH BURNUP FUEL RODS BISON VALIDATION TO PRESSUREIZED WATER REACTOR HIGH-BURNUP POST-IRRADIATION EXAMINATION DATA DEVELOPMENT OF TRANSIENT FISSION GAS RELEASE CAPABILITIES TO STUDY HIGH BURNUP COMMERCIAL FUEL PERFORMANCE UNDER LOSS OF COOLANT ACCIDENT CONDITIONS THE U.S. ACCIDENT TOLERANT FUELS PROGRAM: RECENT ACCOMPLISHMENTS SUPPORTING IMPLEMENTATION FUEL FRAGMENT DISPERSAL DURING A POSTBURST VIBRATION EVENT... SAFETY AND PERFORMANCE ASPECTS IN THE DEVELOPMENT AND QUALIFICATION OF HIGH BURNUP NUCLEAR FUELS FOR WATER COOLED REACTORS... High-Burnup BWR LOCA Burst Analysis Framework Development and Demonstration... ROADRUNNER MiniFuel Experiment - Irradiation Target Design and Sample Characterization Recent High Burnup LOCA Testing at Oak Ridge National Laboratory... Modeling and design of a separate effects irradiation test targeting fission gas release from Cr-doped UO2... Fatigue Testing and Characterization of Pre-hydrided Zircaloy-4 Cladding Tubes Dispersal of high-burnup fuel fragment surrogate particles during and after loss-of-coolant accident tests Assessment of the CTF subchannel code for modeling a large-break loss-of-coolant accident reflood transient In Situ Cladding Surface Temperature Measurements during Simulated LOCA Transients M3FT-24OR020204043: REPORT ON DIC CYCLIC DRYOUT TESTING OF ATF CLADDING MATERIALS... Raman spectroscopy of uranium nitride kernels Pagination Current page 1 Page 2 Page 3 … Next page ›â¶Äº Last page Last » Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Fuel Development Section Fuel Cladding and Core Internals Group
