Jason M Harp Contact harpjm@ornl.gov All Publications 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... 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 The Complex, Unique, and Powerful Imaging Instrument for Dynamics (CUPI2D) at the Spallation Neutron Source (invited) 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 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 Pagination First page « First Previous page ‹â¶Ä¹ Page 1 Current page 2 Page 3 … Next page ›â¶Äº Last page Last » Key Links Curriculum Vitae Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Fuel Development Section Nuclear Fuel Element Performance Group
