Yutai Kato Director, Materials Science and Technology Division Contact KATOHY@ORNL.GOV All Publications Computational materials assessment of the D/Li-stripping neutron source as a prototypical facility for fusion materials testing Deuterium Trapping Mechanisms in Reduced Activation Ferritic Martensitic Steels and Their Correlation with Mechanical Strengthening Simultaneous exposure to neutron radiation and hydrogen environment: Effect on hydrogen retention Simultaneous Exposure of Tungsten and Tungsten - Rhenium Alloy to Neutron Irradiation and Hydrogen Environment Electron microscopy data on irradiation effects in glassy carbon, nuclear graphite, pyrolytic carbon, and carbon fibers Perspectives and challenges of ultra-high temperature ceramics for fusion plasma-facing applications Materials property changes in ETU-10 graphite due to neutron irradiation at elevated temperatures Corrosion characteristics of silicon carbide fiber-reinforced composites in beryllium-bearing molten fluoride salt Determining reference standard strength for neutron-irradiated reduced activation ferritic/martensitic steel F82H by Bayesian method Comprehensive characterization of the irradiation effects of glassy carbon ☆ FUSION MATERIALS SEMIANNUAL PROGRESS REPORT FOR THE PERIOD ENDING JUNE 30, 2024 Microstructure, electrical resistivity, and tensile properties of neutron-irradiated Cu–Cr–Nb–Zr Response of 11B enriched ZrB2 ultra-high temperature ceramic to neutron irradiation at elevated temperatures FUSION MATERIALS RESEARCH AT OAK RIDGE NATIONAL LABORATORY IN FISCAL YEAR 2023 Emerging continuous SiC fibers for high-temperature applications Simulations of radiation damage accumulation in Fe-9Cr under pulsed irradiation conditions representative of inertial fusion energy Mechanical degradation of duplex SiC-fiber reinforced SiC matrix composite tubes under a controlled high-temperature steam environment Detecting Trace Boron Doped in Tungsten Plates Using ToF-SIMS, Raman, and SEM FUSION MATERIALS SEMIANNUAL PROGRESS REPORT FOR THE PERIOD ENDING DECEMBER 31, 2023 Microstructure and thermal stability of a structurally graded tungsten and reduced activation ferritic/martensitic steel joint Phase separation during the direct powder bed fusion of SiC Hermeticity of SiC/SiC composite and monolithic SiC tubes irradiated under radial high-heat flux FUSION MATERIALS SEMIANNUAL PROGRESS REPORT FOR THE PERIOD ENDING JUNE 30, 2023 Degradation of electrical resistivity of tungsten following shielded neutron irradiation Sintered nanostructured alloys for advanced fusion energy applications Pagination Current page 1 Page 2 Page 3 … Next page ›› Last page Last » Key Links Google Scholar ORCID Organizations Physical Sciences Directorate Materials Science and Technology Division
