Jason M Harp Contact harpjm@ornl.gov | 865.341.0221 All Publications Characterization of the radial microstructural evolution in LWR UO2 using electron backscatter diffraction Short Communication: Observation of Initial Burst Release of Fission Gas from High-Burnup UO2 Nuclear Fuel During Thermal Transient Identifying chemically similar multiphase nanoprecipitates in compositionally complex non-equilibrium oxides via machine lear... Postirradiation Examination from Separate Effects Irradiation Testing of Uranium Nitride Kernels and Coated Particles... A Critical Review of High Burnup Fuel Fragmentation, Relocation, and Dispersal under Loss-Of-Coolant Accident Conditions... Summary of the Postirradiation Examination of the First Samples from a MiniFuel Irradiation... Characterization of a minor actinides bearing metallic fuel pin irradiated in EBR-II... Post-irradiation examinations of annular mixed oxide fuels with average burnup 4 and 5% FIMA... Uranium nitride tristructural-isotropic fuel particle... Dispersal of high-burnup fuel fragment surrogate particles during and after loss-of-coolant accident tests Parallel Irradiation Testing to Support Accelerated Down-Selection of Advanced Fuels... High-temperature steam oxidation study of irradiated FeCrAl defueled specimens Metallographic examinations and hydrogen measurements of high-burnup spent nuclear fuel cladding Irradiation creep measurement and microstructural analysis of chromium nitride–coated zirconium alloy using pressurized tubes FeCrAl fuel/clad chemical interaction in light water reactor environments Thermal Conductivity Degradation Due to Radiation-Induced Amorphization in U3Si2: A Pilot Study Mechanical Properties of Neutron-Irradiated Zr-Alloy Weldments (Batch #2) SATS Transient Fission Gas Release Test with Irradiated Fuel under Loss of Coolant Accident Conditions Volume 8: Epithermal and Fast Neutron Radiography Facility HFIR Futures – Enhanced Capabilities Series Advanced Multiscale Microscopy Characterization of High Burnup LWR UO2 Before and After LOCA Testing UCO TRISO Minifuel FY23 NSUF-Kairos Power Post-Irradiation Examination Status Report Analysis of orientation-dependent deformation mechanisms in additively manufactured Zr using in-situ micromechanical testing: Twinning and orientation gradient Analysis of iron-chromium-aluminum samples exposed to accident conditions followed by quench in the QUENCH-19 experiment Empirical and mechanistic transient fission gas release model for high-burnup LOCA conditions Irradiation Testing of Fully Ceramic Microencapsulated (FCM) Fuel Compacts in the High Flux Isotope Reactor... Pagination Current page 1 Page 2 Page 3 Next page ›› Last page Last » Key Links Curriculum Vitae Google Scholar ORCID LinkedIn Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Fuel Development Section Nuclear Fuel Element Performance Group