Kory D Linton Sr. Program Manager, Nuclear Fuels and Materials Contact lintonkd@ornl.gov | 865.241.2767 All Publications 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... Report summarizing demonstration of thermal conductivity measurement methods for coated zirconium cladding... Final Status Report Confirming Completion of Mechanical Testing of HFIR Irradiated Nanocomposite Materials... 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... Burst characteristics of advanced accident-tolerant FeCrAl cladding under temperature transient testing... 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... 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... Impact of Coating Defects on Performance of Coated Zirconium Cladding... 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 Fracture Toughness Characterization of Generation II FeCrAl Alloys after ~18 dpa Irradiation... Development and Implementation of Digital Image Correlation for Out-of-Cell Burst Testing... Assembly of MiniFuel Targets for Irradiation of TRISO Fuel Compacts in the High Flux Isotope Reactor... Handbook on the Material Properties of Yttrium Hydride for High Temperature Moderator Applications... Analysis and Design for Irradiation of High Power TRISO Fuel Compact Specimens in HFIR... Performance of FeCrAl Accident Tolerant Fuel Cladding under Reactivity Insertion Accident Condition Testing... Current Status of HFIR Irradiation Testing Supporting the Transformational Challenge Reactor... Microstructure Investigation and Mechanical Properties of Coated Zircaloy Cladding... Capsule and Specimen Geometries for HFIR Irradiation Testing Supporting the Transformational Challenge Reactor... High Temperature Steam Oxidation of Irradiated FeCrAl in the Severe Accident Test Station... Pagination First page « First Previous page ‹‹ Page 1 Current page 2 Page 3 … Next page ›› Last page Last » Key Links Google Scholar ORCID LinkedIn Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division