Jason M Harp Contact harpjm@ornl.gov All Publications Parallel Irradiation Testing to Support Accelerated Down-Selection of Advanced Fuels High-temperature steam oxidation study of irradiated FeCrAl defueled specimens... Sister Rod Destructive Examinations (FY23) Appendix B: Segmentation, Defueling, Metallographic Data and Total Cladding Hydrogen 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 tub... Thermal Conductivity Degradation Due to Radiation-Induced Amorphization in U3Si2: A Pilot Study... FeCrAl fuel/clad chemical interaction in light water reactor environments 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 iron-chromium-aluminum samples exposed to accident conditions followed by quench in the QUENCH-19 experiment Analysis of orientation-dependent deformation mechanisms in additively manufactured Zr using in-situ micromechanical testing: Twinning and orientation gradient 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 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 Evaluation of the Effect of Burnup Acceleration on UO2 Microstructure Evolution 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 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
