Robert N Morris Senior Researcher Contact morrisrn1@ornl.gov | 865.241.4237 All Publications 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 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... Sister Rod Destructive Examinations (FY20) Appendix D, Fission Gas Analysis, Fuel Rod Burnup and Isotopic Measurements... AGR-2 Loose Particle Heating Tests in the Furnace for Irradiated TRISO Testing... Destructive PIE and Safety Testing of Six AGR-2 UO2 Capsule 3 Compacts... 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... Destructive Examinations of High Burnup Pressurized Water Reactor Fuel Rods 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... Measurement and modeling of the gas permeability of high burnup pressurized water reactor fuel rods SAFETY TESTING AND DESTRUCTIVE EXAMINATION OF AGR-2 UCO COMPACT 2-1-2... SAFETY TESTING AND DESTRUCTIVE EXAMINATION OF AGR-2 UCO COMPACT 6-4-3... Fission Gas Composition, Rod Internal Pressure, and Rod Free Volume of High Burnup Pressurized Water Reactor Fuel Rods Pagination Current page 1 Page 2 Page 3 … Next page ›› Last page Last » Key Links ORCID Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Fuel Development Section
