Jason M Harp Contact harpjm@ornl.gov | 865.341.0221 All Publications Post-irradiation examination of low burnup U3Si5 and UN-U3Si5 composite fuels Non-Destructive Assay of Spent Nuclear Fuel Using Gamma-Ray Mirrors as a Narrow Band Pass Filter The Complex, Unique, and Powerful Imaging Instrument for Dynamics (CUPI2D) at the Spallation Neutron Source (invited)... Sister Rod Destructive Examinations (FY22) Appendix B: Segmentation, Defueling, Metallographic Data and Total Cladding Hydrogen Testing fast reactor fuels in a thermal reactor: Comparison of transmutation metallic fuel alloys behavior by scanning electron microscopy Nuclear fuel irradiation testbed for nuclear security applications Accelerated fission rate irradiation design, pre-irradiation characterization, and adaptation of conventional PIE methods for U-10Mo and U-17Mo Transmission electron microscopy characterization of the fuel-cladding chemical interactions in HT9 cladded U-10Zr fuel Accident Tolerant and High Burnup Hotcell PIE at ORNL... Evaluation of the Effect of Burnup Acceleration on UO2 Microstructure Evolution 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 fu... High-temperature compressive creep tests of U3Si2 with spark plasma sintering: Experiments and finite element modeling... High-burnup fuel stress analysis prior to and during a LOCA transient... 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... Pagination First page « First Previous page ‹‹ Page 1 Current 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