• Title of article

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

  • Author/Authors

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

  • Issue Information
    روزنامه با شماره پیاپی سال 2011
  • Pages
    4
  • From page
    176
  • To page
    179
  • Abstract
    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.
  • Journal title
    Journal of Nuclear Materials
  • Serial Year
    2011
  • Journal title
    Journal of Nuclear Materials
  • Record number

    1358520