Yutai Kato Director, Materials Science and Technology Division Contact KATOHY@ORNL.GOV All Publications Design and strategy for next-generation silicon carbide composites for nuclear energy X-Ray Characterization of Atomistic Defects Causing Irradiation Creep of SiC Electron tomography of unirradiated and irradiated nuclear graphite Determination of neutron irradiation temperatures of SiC using electrical resistivity method Effects of HFIR neutron irradiation on fracture toughness properties of standard and Ni-doped F82H... Post-Irradiation Evaluation of Eurofer97 Fracture Toughness Using Miniature Multinotch Bend Bar Specimens Evaluation of the Effects of Neutron Irradiation on First-Generation Corrosion Mitigation Coatings on SiC for Accident-Tolerant Fuel Cladding The effects of neutron and ionizing irradiation on the aqueous corrosion of SiC Perspectives on the FESAC transformative enabling capabilities: Priorities, plans, and Status Protection of graphite from salt and gas permeation in molten salt reactors Electric current–assisted direct joining of silicon carbide... Impact of Control Blade Insertion on the Deformation Behavior of SiC-SiC Channel Boxes in BWRs Progress in development of SiC-based joints resistant to neutron irradiation Protection of graphite from salt and gas permeation in molten salt reactors Neutron irradiation-induced microstructure damage in ultra-high temperature ceramic TiC Neutron irradiation effects on the mechanical properties of powder metallurgical processed tungsten alloys 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... Development of a Modeling Approach to Describe Thermal Conductivity of Prototypic SiC-SiC tubes for LWR Fuel Cladding Master Curve Fracture Toughness Characterization of Eurofer97 Steel Variants Using Miniature Multi-Notch Bend Bar Specimens for Fusion Applications Pagination First page « First Previous page ‹â¶Ä¹ … Page 3 Current page 4 Page 5 … Next page ›â¶Äº Last page Last » Key Links Organizations Physical Sciences Directorate Materials Science and Technology Division
