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

doi:10.1016/j.jnucmat.2010.12.300

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

Research output: Contribution to journal › Article › peer-review

270 Citations (Scopus)

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.

Original language	English
Pages (from-to)	176-179
Number of pages	4
Journal	Journal of Nuclear Materials
Volume	417
Issue number	1-3
DOIs	https://doi.org/10.1016/j.jnucmat.2010.12.300
Publication status	Published - 2011 Oct 1
Externally published	Yes

ASJC Scopus subject areas

Nuclear and High Energy Physics
Materials Science(all)
Nuclear Energy and Engineering

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Kimura, A., Kasada, R., Iwata, N., Kishimoto, H., Zhang, C. H., Isselin, J., Dou, P., Lee, J. H., Muthukumar, N., Okuda, T., Inoue, M., Ukai, S., Ohnuki, S., Fujisawa, T., & Abe, T. F. (2011). Development of Al added high-Cr ODS steels for fuel cladding of next generation nuclear systems. Journal of Nuclear Materials, 417(1-3), 176-179. https://doi.org/10.1016/j.jnucmat.2010.12.300

Kimura, A, Kasada, R, Iwata, N, Kishimoto, H, Zhang, CH, Isselin, J, Dou, P, Lee, JH, Muthukumar, N, Okuda, T, Inoue, M, Ukai, S, Ohnuki, S, Fujisawa, T & Abe, TF 2011, 'Development of Al added high-Cr ODS steels for fuel cladding of next generation nuclear systems', Journal of Nuclear Materials, vol. 417, no. 1-3, pp. 176-179. https://doi.org/10.1016/j.jnucmat.2010.12.300

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AU - Zhang, C. H.

AU - Isselin, J.

AU - Dou, P.

AU - Lee, J. H.

AU - Muthukumar, N.

AU - Okuda, T.

AU - Inoue, M.

AU - Ukai, S.

AU - Ohnuki, S.

AU - Fujisawa, T.

AU - Abe, T. F.

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AB - 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.

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

Abstract

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