Kory Linton Sr. Program Manager, Nuclear Fuels and Materials Contact LINTONKD@ORNL.GOV All Publications A correlation-based approach for evaluating mechanical properties of nuclear fuel cladding tubes Quantifying deformation during Zry-4 burst testing: a comparison of BISON and a combined in-situ digital image correlation and infrared thermography method Post-Irradiation Examination of Yttrium Hydride Specimens at 91°µÍø Sensitivity Analysis of TRISO Fuel Configuration in a MiniFuel Irradiation Experiment Report on Evolution of Inconel 718 Following HFIR Irradiation... BISON Validation and Sensitivity Study of FeCrAl Cladding Burst during Simulated RIA Conditions Separate Effects Testing of TRISO Fuel Particles using the MiniFuel Irradiation Vehicle FY23 Post-LOCA Characterization of Irradiated Fuel - NSUF Award 17-12985 BISON validation of FeCrAl cladding mechanical failure during simulated reactivity-initiated accident conditions TRISO Fuel Performance Pre-test Predictions of HFIR MiniFuel High Power Irradiation MiniFuel Experimental Capability at 91°µÍø In Situ Synchrotron Radiation Diffraction Study of Neutron-Irradiated Yttrium Hydrides During Thermal Treatments... Status Report on Irradiation of MiniFuel Targets bearing TRISO Fuel Compacts Final Status Report Confirming Completion of Mechanical Testing of HFIR Irradiated Nanocomposite Materials Report summarizing demonstration of thermal conductivity measurement methods for coated zirconium cladding Development and Standup Testing of a System to Observe Fission Gas Release During Transient Heating of Nuclear Fuel Element S... Report Summarizing Progress in Digital Image Correlation Analysis of Burst Phenomenon Characterization of radiation damage in 3D printed SiC Irradiation Testing of Silicon Carbide Joint Specimens in the High Flux Isotope Reactor Destructive Examination of a FeCrAl-UO2 Irradiation Test Impact of Coating Defects on Performance of Coated Zirconium Cladding The U.S. Accident Tolerant Fuels Program — Update on a National Initiative POST-TEST EXAMINATIONS OF A LOCA SAMPLE FROM AN IRRADIATED HIGH-BURNUP PWR M5 FUEL ROD FY21 burst activities with coated Zircaloy-4 under accident conditions Mechanical Properties of Additive Manufacturing 316L Stainless Steel Before and After Neutron Irradiation - FY 2021 Pagination First page « First Previous page ‹â¶Ä¹ Page 1 Current 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
