Yutai Kato Director, Materials Science and Technology Division Contact KATOHY@ORNL.GOV All Publications A Survey: The Chemical Compatibility of Silicon Carbide with Molten Fluoride Salts Surface morphology of Tungsten-F82H after high-heat flux testing using plasma-arc lamps Recent Development in SiC Composite Technologies for Nuclear Energy Applications Microstructural Evolution of 3C-SiC Exposed to Simultaneous Neutron Irradiation and Helium Implantation Interlaboratory Round Robin Testing of SiC/SiC Composite Tubes L An F82H steel pressurized tube creep capsule for irradiation in HFIR Interlaboratory round robin study on axial tensile properties of SiC-SiC CMC tubular test specimens Advanced manufacturing—A transformative enabling capability for fusion... Japan-US Joint Research Project PHENIX (2013–2018); Heat Transfer Tests, Neutron Irradiation and Post-Irradiation Examinations for Development of He-Cooled Tungsten Divertor Irradiation stability and thermo-mechanical properties of NITE-SiC irradiated to 10 dpa Dimensional stability and anisotropy of SiC and SiC-based composites in transition swelling regime Ceramic composites: A review of toughening mechanisms and demonstration of micropillar compression for interface property extraction Micro-mechanical evaluation of SiC-SiC composite interphase properties and debond mechanisms Mechanical property degradation of high crystalline SiC fiber–reinforced SiC matrix composite neutron irradiated to ∼100 ... Evaluating the irradiation effects on the elastic properties of miniature monolithic SiC tubular specimens Viewpoint Set on Nuclear Materials Science Progress in the U.S./Japan PHENIX Project for the Technological Assessment of Plasma Facing Components for DEMO Reactors Oxidation Behavior of Matrix Graphite and Its Effect on Compressive Strength Materials challenges for the fusion nuclear science facility Mechanical properties of SiC composites neutron irradiated under light water reactor relevant temperature and dose conditions Post Irradiation Examination of SiC Tube Subjected to Simultaneous Irradiation and Radial High Heat Flux Accident Tolerant Fuel Cladding Tube Irradiations in the HFIR... JECS - Microstructure and mechanical properties of titanium aluminum carbides neutron irradiated at 400–700°C Experimental Design and Analysis for Irradiation of SiC/SiC Composite Tubes under a Prototypic High Heat Flux Microstructure and hydrothermal corrosion behavior of NITE-SiC with various sintering additives in LWR coolant environments... Pagination First page « First Previous page ‹‹ … Page 6 Current page 7 Page 8 … Next page ›› Last page Last » Key Links Google Scholar ORCID Organizations Physical Sciences Directorate Materials Science and Technology Division
