Jason M Harp Contact harpjm@ornl.gov All Publications Advanced microscopy for characterization of high burnup commercial uo2 fuel before and after LOCA testing Separate Effects Testing of TRISO Fuel Particles using the MiniFuel Irradiation Vehicle Initial microstructure examination of high burnup fuel with varying operational histories Application of BISON to UO2 MiniFuel fission gas release analysis FY23 Post-LOCA Characterization of Irradiated Fuel - NSUF Award 17-12985 MiniFuel Experimental Capability at Oak Ridge National Laboratory Development and Standup Testing of a System to Observe Fission Gas Release During Transient Heating of Nuclear Fuel Element S... Sister Rod Destructive Examinations (FY21) Appendix B: Segmentation, Defueling, Metallographic Data and Total Cladding Hydrog... Phase evolution of U-Zr system in a thermal cycling neutron diffraction experiment: as-cast U-35Zr and U-50Zr Postirradiation characterization of palladium as an additive for fuel cladding chemical interaction mitigation in metallic fuel High-temperature compressive creep tests of U3Si2 with spark plasma sintering: Experiments and finite element modeling Investigation of constituent redistribution in U-Pu-Zr fuels and its dependence on varying Zr content Destructive Examination of a FeCrAl-UO2 Irradiation Test POST-TEST EXAMINATIONS OF A LOCA SAMPLE FROM AN IRRADIATED HIGH-BURNUP PWR M5 FUEL ROD The U.S. Accident Tolerant Fuels Program — Update on a National Initiative Characterization of Fuel and Cladding In and Near the Pellet-Pellet Gap of a High-Burnup Pressurized Water Reactor Fuel Rod Engineering Assessment of UO2 and Cladding Behavior under High Burnup LOCA Conditions MICROSTRUCTURAL ANALYSIS OF IRON-CHROMIUM-ALUMINUM SAMPLES EXPOSED TO LOCA-TYPE CONDITIONS FOLLOWED BY QUENCH Assembly of MiniFuel Targets for Irradiation of U-Mo Fuel Specimens in the High Flux Isotope Reactor... Demonstration of Novel Post-Irradiation Examination Capabilities on MiniFuel Disk Specimens Analysis and Design for Irradiation of High Power TRISO Fuel Compact Specimens in HFIR High Temperature Steam Oxidation of Irradiated FeCrAl in the Severe Accident Test Station Aluminum-doped U3Si2 composite fuels with enhanced oxidation resistance Microstructure Evolution of U–Zr System in A Thermal Cycling Neutron Diffraction Experiment: Extruded U–10Zr (wt. %) Fuel-cladding chemical interaction of a prototype annular U-10Zr fuel with Fe-12Cr ferritic/martensitic HT-9 cladding Pagination First page « First Previous page ‹‹ … Page 2 Current page 3 Page 4 Next page ›› Last page Last » Key Links Curriculum Vitae Google Scholar ORCID LinkedIn IMPACT@ORNL Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Fuel Development Section Nuclear Fuel Element Performance Group
