Yutai Kato Director, Materials Science and Technology Division Contact KATOHY@ORNL.GOV All Publications Processing of Tungsten Through Electron Beam Melting The status of the Japanese material properties handbook and the challenge to facilitate structural design criteria for DEMO in-vessel components HFIR SiC-SiC Composite Clad Tube Bowing Test: Pre-Irradiation Characterization... ASME Code Rules and ASTM Standards Integration for Ceramic Composite Core Materials and Components 1 Atomic and microstructural origins of stored energy release in neutron-irradiated silicon carbide Technological aspects in blanket design: Effects of micro-alloying and thermo-mechanical treatments of EUROFER97 type steels after neutron irradiation Summary Report on the Refined User Requirements for U.S. Fusion Prototypic Neutron Source In Situ Nano-Indentation Techniques for Post-Irradiation Examinations Fusion Materials Semiannual Progress Report for the Period Ending December 31, 2020... X-ray characterization of anisotropic defect formation in SiC under irradiation with applied stress Conceptual design of HFIR irradiation experiment for material compatibility study on liquid Sn divertor... Segregation behavior and phase instability of Eurofer97 after neutron irradiation to 72 dpa HFIR SiC Bowing Test Ready to Insert Downselection of Cladding Materials for Zirconium Hydride Moderator Effects of helium on irradiation response of reduced-activation ferritic-martensitic steels: Using nickel isotopes to simulate fusion neutron response Adhesion, structure, and mechanical properties of Cr HiPIMS and cathodic arc deposited coatings on SiC Hydrothermal Corrosion of First-Generation Dual-Purpose Coatings on Silicon Carbide for Accident-Tolerant Fuel Cladding Additive manufacturing of silicon carbide for nuclear applications Thermal diffusivity of irradiated tungsten and tungsten-rhenium alloys Helium effects on the surface and subsurface evolutions in single-crystalline tungsten Advanced synchrotron characterization techniques for fusion materials science Fusion Materials Research at 91°µÍø in Fiscal Year 2020 Tensile properties of powder-metallurgical-processed tungsten alloys after neutron irradiation near recrystallization temperatures Design and strategy for next-generation silicon carbide composites for nuclear energy X-Ray Characterization of Atomistic Defects Causing Irradiation Creep of SiC Pagination First page « First Previous page ‹â¶Ä¹ … Page 2 Current page 3 Page 4 … Next page ›â¶Äº Last page Last » Key Links Organizations Physical Sciences Directorate Materials Science and Technology Division
