Takaaki Koyanagi Senior R&D Staff Contact 865.341.1927 | KOYANAGIT@ORNL.GOV All Publications Electric current–assisted direct joining of silicon carbide... Mechanical and Thermophysical Properties of 3D-Printed SiC-FY20... Progress in development of SiC-based joints resistant to neutron irradiation Neutron irradiation-induced microstructure damage in ultra-high temperature ceramic TiC Pair distribution function analysis of neutron-irradiated silicon carbide Characterization of PVD Cr, CrN, and TiN coatings on SiC High temperature steam oxidation of Cr-coated SiCf/SiC composite for LWR cladding applications Handbook of advanced manufactured material properties from TCR structure builds at ORNL – FY19 Assessment of Pre-Irradiation SiC CMC Joint Performance in Representative Cladding Geometries Revealing irradiation damage along with the entire damage range in ion-irradiated SiC/SiC composites using Raman spectroscopy High-Temperature Creep Properties of SiC Fibers with Different Compositions 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 spectroscopy Overview of General Atomics SiGA™ SiC-SiC Composite Development for Accident Tolerant Fuel Report on Hydrogen Isotope Permeability/Hermeticity of SiC-based Cladding PHENIX U.S.-Japan Collaboration Investigation of Thermal and Mechanical Properties of Thermal Neutron–Shielded Irradiated Tungsten Systematic Technology Evaluation Program for SiC based BWR Channel Box In-pile tensile creep of chemical vapor deposited silicon carbide at 300 °C Multiscale experimental characterization of coatings on ceramics: A case study of tungsten on SiC Response of unalloyed tungsten to mixed spectrum neutrons Influence of dynamic annealing of irradiation defects on the deuterium retention behaviors in tungsten irradiated with neutron High-dose, intermediate-temperature neutron irradiation effects on silicon carbide composites with varied fiber/matrix interf... Fully Ceramic Microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Sensitivity of reactor behavior during design basis accidents to fuel properties and the potential impact of the SiC defect annealing process Pagination First page « First Previous page ‹‹ … Page 2 Current page 3 Page 4 … Next page ›› Last page Last » Key Links Curriculum Vitae Google Scholar ORCID Organizations Physical Sciences Directorate Materials Science and Technology Division Materials in Extremes Section Radiation Effects and Microstructural Analysis Group
