Evaluation of the effects of neutron irradiation on first -generation corrosion mitigation coatings on SiC for accident -tolerant fuel cladding *

著录项

• 来源
  《Journal of Nuclear Materials: Materials Aspects of Fission and Fusion》 |2020年第1期|共14页
• 作者

  Doyle Peter J.; Koyanagi Takaaki; Ang Caen; Snead Lance; Mouche Peter; Katoh Yutai; Raiman Stephen S.;

  展开▼
• 作者单位

  Univ Tennessee Knoxville TN 37996 USA;

  Oak Ridge Natl Lab Mat Sci &

  Technol Div Oak Ridge TN USA;

  Univ Tennessee Knoxville TN 37996 USA;

  SUNY Stony Brook Stony Brook NY 11794 USA;

  Oak Ridge Natl Lab Mat Sci &

  Technol Div Oak Ridge TN USA;

  Univ Tennessee Knoxville TN 37996 USA;

  Oak Ridge Natl Lab Mat Sci &

  Technol Div Oak Ridge TN USA;

  展开▼
• 收录信息
• 原文格式 PDF
• 正文语种 eng
• 中图分类 原子能技术;
• 关键词