Yutai Kato Director, Materials Science and Technology Division Contact katohy@ornl.gov | 865.341.0004 All Publications Fusion Materials Research at Oak Ridge National Laboratory in Fiscal Year 2019... Plasma-Arc Lamp High Heat Flux Cycling Exposure of Neutron Irradiated Tungsten Materials... Pair distribution function analysis of neutron-irradiated silicon carbide... Silicon carbide and its composites for nuclear applications – Historical overview... Characterization of PVD Cr, CrN, and TiN coatings on SiC... High temperature steam oxidation of Cr-coated SiCf/SiC composite for LWR cladding applications... Evaluation of the Corrosion Kinetics of SiC with and without Mitigation Coatings in LWR Chemistries Master Curve Fracture Toughness Characterization of Eurofer97 Steel Variants Using Miniature Multi-Notch Bend Bar Specimens f... Chemical compatibility of silicon carbide in molten fluoride salts for the fluoride salt-cooled high temperature reactor... Development of a Modeling Approach to Describe Thermal Conductivity of Prototypic SiC-SiC tubes for LWR Fuel Cladding... X-Ray Computed Tomography Analysis of Neutron-Irradiated SiC Composite Tube... Elastic moduli reduction in SiC-SiC tubular specimen after high heat flux neutron irradiation measured by resonant ultrasound... A 6 MW/m 2 High Heat Flux Testing Facility of Irradiated Materials Using Infrared Plasma-Arc Lamps... Mechanical properties of single-crystal tungsten irradiated in a mixed spectrum fission reactor... PHENIX U.S.-Japan Collaboration Investigation of Thermal and Mechanical Properties of Thermal Neutron–Shielded Irradiated T... Report on Hydrogen Isotope Permeability/Hermeticity of SiC-based Cladding... Systematic Technology Evaluation Program for SiC based BWR Channel Box... In-pile tensile creep of chemical vapor deposited silicon carbide at 300 °C... Mechanical properties and microstructure characterization of Eurofer97 steel variants in EUROfusion program... Deuterium retention in advanced steels for fusion reactor structural application... Evaluation of the continuous dilatometer method of silicon carbide thermometry for passive irradiation temperature determinat... Multiscale experimental characterization of coatings on ceramics: A case study of tungsten on SiC... Response of unalloyed tungsten to mixed spectrum neutrons... High-dose, intermediate-temperature neutron irradiation effects on silicon carbide composites with varied fiber/matrix interf... High throughput crystal structure and composition mapping of crystalline nanoprecipitates in alloys by transmission Kikuchi d... Pagination First page « First Previous page ‹‹ … Page 3 Current page 4 Page 5 … Next page ›› Last page Last » Key Links ORCID Organizations Physical Sciences Directorate Materials Science and Technology Division