Robert Morris Senior Researcher Contact MORRISRN1@ORNL.GOV All Publications NON-DESTRUCTIVE POST IRRADIATION EXAMINATION OF FIRST CYCLE ACCIDENT TOLERANT AND ADVANCED ZIRCONIUM ALLOY HIGH BURNUP FUEL RODS DEVELOPMENT OF TRANSIENT FISSION GAS RELEASE CAPABILITIES TO STUDY HIGH BURNUP COMMERCIAL FUEL PERFORMANCE UNDER LOSS OF COOLANT ACCIDENT CONDITIONS Sister Rod Destructive Examinations (FY23) Appendix D: Fission Gas, Fuel Burnup, and Fuel Isotopic Measurements Sister Rod Destructive Examinations (FY23) Appendix C: Rod Internal Pressure, Void Volume, and Gas Transmission Tests SATS Transient Fission Gas Release Test with Irradiated Fuel under Loss of Coolant Accident Conditions UPGRADE OF CORE CONDUCTION COOLDOWN TEST FACILITY CONTROL SYSTEM... Plutonium-238 Production Program Results, Implications, and Projections from Irradiation and Examination of Initial NpO2 Test Targets for Improved Production Sister Rod Destructive Examinations (FY21) Appendix C: Rod Internal Pressure, Void Volume, and Gas Transmission Tests Upgrade of Gamma Spectrometry Systems for ORNL TRISO Fuel PIE Post Irradiation Examination of Candidate NpO2 Targets for Pu-238 Production Postirradiation Examination from Separate Effects Irradiation Testing of Uranium Nitride Kernels and Coated Particles Redistribution of radionuclides in irradiated AGR-1 UCO TRISO fuel after 1800 °C safety testing... Sister Rod Destructive Examinations (FY20) Appendix D, Fission Gas Analysis, Fuel Rod Burnup and Isotopic Measurements Sister Rod Destructive Examinations (FY20) Appendix C: Rod internal Pressure, void volume, and gas transmission tests Sister Rod Destructive Examinations (FY20) Appendix B: Segmentation, Defueling, Metallography, and Total Cladding Hydrogen Me... Destructive PIE and Safety Testing of Six AGR-2 UO2 Capsule 3 Compacts AGR-2 Loose Particle Heating Tests in the Furnace for Irradiated TRISO Testing Analysis of Fission Product Distribution and Composition in the TRISO Layers of AGR-2 Fuel Summary of the Postirradiation Examination of the First Samples from a MiniFuel Irradiation Safety Testing and Destructive Examination of AGR-2 UO2 Compact 3-1-1 Post-irradiation Examination Results of Miniature Fuel Specimens Irradiated in the High Flux Isotope Reactor Sister Rod Destructive Test Results (FY19) Transient Temperature Safety Testing of AGR-2 UCO Compacts 5-1-1, 5-1-2, and 5-3-1 Destructive Examinations of High Burnup Pressurized Water Reactor Fuel Rods Measurement and modeling of the gas permeability of high burnup pressurized water reactor fuel rods Pagination Current page 1 Page 2 Page 3 … Next page ›â¶Äº Last page Last » Key Links Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Fuel Development Section
