Kory Linton Sr. Program Manager, Nuclear Fuels and Materials Contact LINTONKD@ORNL.GOV All Publications Characteristics of Fuel Articles for Irradiation Testing in TREAT and MITR Post-Irradiation-Examination of the ORNL and LANL Samples Assembly of Capsules for Irradiation of Silicon Carbide Joint Specimens in the High Flux Isotope Reactor Demonstration of the Coating Analysis Capabilities in BISON Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys LOCA Fragmentation Test with High Burnup HBR Fuel Rod Length Dependence of Severe Accident Test Station Integral Testing Thermal and Neutronic Analysis for Irradiation of Advanced Neutron Absorbing Material in the High Flux Isotope Reactor Assembly and Delivery of Capsules for Irradiation of Absorber Material Specimens in the High Flux Isotope Reactor Assembly and Delivery of Rabbit Capsules for Irradiation of Prototype Metal and Nanocomposite Specimens in the High Flux Isot... Progress Report on Measurement of Fission Gas Release from Irradiated Fuel During Temperature Transient Infrastructure Investments in LAMDA: SEM Mill and Vault NSUF 2019 Milestone Report Tensile Testing and Characterization of Irradiated Grade 92 Ferritic-Martensitic Steels at the IMET Hot Cell and Lambda Facilities Progress Report on Modified Burst Testing and Alternative Test Methodologies Mechanical properties and microstructure characterization of Eurofer97 steel variants in EUROfusion program First annual progress report on the procurement and post-irradiation examination of the selected samples of alloy 800H and Grade 92 and 91 steels Identification and shipment progress of the INL and LANL samples to be received at ORNL Transportation Planning for Irradiated Fuel-Clad and Integral FeCrAl Experiments Radiation Induced Segregation at Grain Boundaries in Steels: NSUF 2018 Milestone Report An advanced experimental design for modified burst testing of nuclear fuel cladding materials during transient loading Tensile Strength and Steam Oxidation Resistance of ODS FeCrAl Sheet and Tubes ORNL: Providing access to nuclear infrastructure, expertise ORNL: Providing access to nuclear infrastructure, expertise Transient Mechanical Test Development for Accident Tolerant Cladding Candidates to Simulate PCMI-like Conditions Results from In-cell Integral LOCA Testing at ORNL Pagination First page « First Previous page ‹‹ … Page 3 Current page 4 Page 5 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
