Development of Al added high-Cr ODS steels for fuel cladding of next generation nuclear systems

A. Kimura, R. Kasada, N. Iwata, H. Kishimoto, C. H. Zhang, J. Isselin, P. Dou, J. H. Lee, N. Muthukumar, T. Okuda, M. Inoue, S. Ukai, S. Ohnuki, T. Fujisawa, T. F. Abe

研究成果: Article査読

223 被引用数 (Scopus)

抄録

A successful example of high-Cr oxide dispersion strengthened (ODS) steels development is introduced with showing key technologies to overcome the issues to meet material requirements for next generation nuclear systems as well as fusion blanket systems. Corrosion issue requires Cr concentration more than 14 wt.%, but aging embrittlement issue requires it less than 16 wt.%. An addition of 4 wt.%Al is effective to improve corrosion resistance of 16 wt.%Cr-ODS steel in supercritical water (SCW) and lead-bismuth eutectics (LBE), while it is detrimental to high-temperature strength. An addition of small amount of Zr or Hf results in a significant increase in creep strength at 973 K in Al-added ODS steels. Feasibility of high-Cr ODS steel without Al addition is assessed for fusion application in terms of corrosion resistance in SCW.

本文言語English
ページ(範囲)176-179
ページ数4
ジャーナルJournal of Nuclear Materials
417
1-3
DOI
出版ステータスPublished - 2011 10 1
外部発表はい

ASJC Scopus subject areas

  • 核物理学および高エネルギー物理学
  • 材料科学(全般)
  • 原子力エネルギーおよび原子力工学

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