Nathan A Capps Contact cappsna@ornl.gov | 865.341.0458 All Publications A study on the impact of using a subchannel resolution for modeling of large break loss of coolant accidents 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 Raman spectroscopy of uranium nitride kernels... In Situ Cladding Surface Temperature Measurements during Simulated LOCA Transients... M3FT-24OR020204043: REPORT ON DIC CYCLIC DRYOUT TESTING OF ATF CLADDING MATERIALS Design and Assembly of MiniFuel Targets for Characterization of High Burnup UO2 Specimens Irradiated in the High Flux Isotope Reactor Raman Spectroscopy of Zirconium Hydride... An integrated statistical-thermodynamic model for fission gas release and swelling in nuclear fuels... In-situ determination of strain during transient burst testing and the temperature dependence of Zircaloy-4 claddings NEAMS Burnup Extension Accomplishments and Remaining Modeling Gaps Impact of LWR assembly structural features on cladding burst behavior under LOCA conditions Mesoscale modeling of the effects of accelerated burnup on UO2 microstructural evolution Residual Stress Measurements of Cr-coated Cladding Effects of transient fission gas release on rod balloon burst behavior during a loss-of-coolant accident In Situ Strain Analysis of Cr-coated Zircaloy-4 Under Simulated LOCA Conditions Characterization of the radial microstructural evolution in LWR UO2 using electron backscatter diffraction Multiphysics analysis of fuel fragmentation, relocation, and dispersal susceptibility–Part 3: Thermal hydraulic evaluation of large break LOCA under high-burnup conditions Multiphysics analysis of fuel fragmentation, relocation, and dispersal susceptibility–Part 1: Overview and code coupling strategies Advanced Multiscale Microscopy Characterization of High Burnup LWR UO2 Before and After LOCA Testing Differences in high burnup fuel management strategies to minimize FFRD and increase economic viability... Status of Mechanistic Fission Gas Model in High Burnup Fuel AFC FY 2023 HFIR Irradiation Test Matrix – Supported by the Design of a Ring Specimen Irradiation Vehicle SATS Transient Fission Gas Release Test with Irradiated Fuel under Loss of Coolant Accident Conditions Pagination Current page 1 Page 2 Page 3 Next page ›› Last page Last » Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Fuel Development Section Advanced Fuel Fabrication and Instrumentation Group