Kory Linton Sr. Program Manager, Nuclear Fuels and Materials Contact LINTONKD@ORNL.GOV All Publications 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 Assembly of MiniFuel Targets for Irradiation of TRISO Fuel Compacts in the High Flux Isotope Reactor Current Status of HFIR Irradiation Testing Supporting the Transformational Challenge Reactor Microstructure Investigation and Mechanical Properties of Coated Zircaloy Cladding 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 High Temperature Steam Oxidation of Irradiated FeCrAl in the Severe Accident Test Station Mechanical and Thermophysical Properties of 3D-Printed SiC before and after Neutron Irradiation – FY 2021... Capsule and Specimen Geometries for HFIR Irradiation Testing Supporting the Transformational Challenge Reactor Irradiation stability and thermomechanical properties of 3D-printed SiC Disassembly of Capsules after Irradiation of Prototype Metal and Nanocomposite Specimens in the High Flux Isotope Reactor (S)TEM/EDS study of native precipitates and irradiation induced Nb-rich platelets in high-burnup M5® Development of Standardized Property Requirements, Measurement Methods, and Reporting Guidance for Coatings ORNL PIE (LAMDA) Final Report on Characterization of Irradiated Grade 92 Ferritic-Martensitic Steels Post-Irradiation Examination Supporting the Transformational Challenge Reactor Overpower Testing of TCR Fuel in TREAT Integral LOCA fragmentation test on high-burnup fuel Mechanical failure of fresh nuclear grade iron–chromium–aluminum (FeCrAl) cladding under simulated hot zero power reactivity initiated accident conditions STEP Report on Advanced ODS FeCrAl Alloys for Fission Applications Thermal Analysis and Irradiation Growth of Coated Zirconium Alloy Cladding Specimens in HFIR Progress Report on Plane Strain Tension Testing of ATF FeCrAl Cladding HFIR Irradiation Testing Supporting the Transformational Challenge Reactor Characteristics of Fuel Articles for Irradiation Testing in TREAT and MITR Pagination First page « First Previous page ‹‹ … Page 2 Current page 3 Page 4 … 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
