Yutai Katoh

ORCID: 0000-0001-9494-5862
Publications
Citations
Views
---
Saved
---
About
Contact & Profiles
Research Areas
  • Advanced ceramic materials synthesis
  • Fusion materials and technologies
  • Nuclear Materials and Properties
  • Advanced materials and composites
  • Aluminum Alloys Composites Properties
  • Silicon Carbide Semiconductor Technologies
  • Graphite, nuclear technology, radiation studies
  • Metal and Thin Film Mechanics
  • Nuclear reactor physics and engineering
  • Nuclear materials and radiation effects
  • Nuclear and radioactivity studies
  • Semiconductor materials and devices
  • High-Velocity Impact and Material Behavior
  • Ion-surface interactions and analysis
  • Nuclear Physics and Applications
  • Microstructure and Mechanical Properties of Steels
  • Fiber-reinforced polymer composites
  • Boron and Carbon Nanomaterials Research
  • Silicon and Solar Cell Technologies
  • Metal Alloys Wear and Properties
  • Additive Manufacturing and 3D Printing Technologies
  • Medical Imaging Techniques and Applications
  • Radiation Shielding Materials Analysis
  • Advanced Surface Polishing Techniques
  • Digital Radiography and Breast Imaging

Oak Ridge National Laboratory
2015-2024

Government of the United States of America
2022-2023

Tokyo Metropolitan University
1998-2020

University of Tennessee at Knoxville
2008-2020

National Technical Information Service
2008-2018

Office of Scientific and Technical Information
2008-2018

UT-Battelle
2017

Lawrence Berkeley National Laboratory
2017

University of California, Berkeley
2017

Naval Research Laboratory Materials Science and Technology Division
2016

10.1016/j.cossms.2012.03.005 article EN Current Opinion in Solid State and Materials Science 2012-04-04

Growth and microstructure of a protective or nonprotective SiO 2 scale the subsequent volatilization formed on high‐purity chemical vapor deposited ( CVD ) SiC nuclear‐grade / composites have been studied during high‐temperature 100% steam exposure. The environmental parameters interest were temperature from 1200°C to 1700°C, pressure 0.1 MPa flow velocities 0.23 145 cm/s. Scale was characterized via electron microscopy X‐ray diffractometry. Arrhenius dependence parabolic oxidation linear...

10.1111/jace.13094 article EN Journal of the American Ceramic Society 2014-07-04

10.1016/j.jnucmat.2019.151849 article EN publisher-specific-oa Journal of Nuclear Materials 2019-10-18

Radiation tolerance is determined by how effectively the microstructure can remove point defects produced irradiation. Engineered nanocrystalline SiC with a high-density of stacking faults (SFs) has significantly enhanced recombination interstitials and vacancies, leading to self-healing irradiation-induced defects. While single crystal readily undergoes an crystalline amorphous transformation at room temperature, nano-engineered SFs exhibits more than order magnitude increase in radiation...

10.1039/c2cp42342a article EN Physical Chemistry Chemical Physics 2012-01-01
Coming Soon ...