Super ODS steels R&D for fuel cladding of next generation nuclear systems 1) Introduction and alloy design

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: Chapter in Book/Report/Conference proceedingConference contribution

7 Citations (Scopus)

Abstract

Cladding material development is essential for realization of highly efficient high burn-up operation of next generation nuclear systems, where high performance is required for the materials, that is, high strength at elevated temperature, high resistance to corrosion and high resistance to irradiation. Oxide dispersion strengthening (ODS) ferritic steels are considered to be most adequate for the cladding material because of their high strength at elevated temperature. In this work, "Super ODS steel" that has better corrosion resistance than 9Cr-ODS steel, has been developed for application to cladding of a variety of next generation nuclear systems. In the following ten papers, the recent experimental results of "Super ODS steel" R&D will be presented, indicating that many unexpected preferable features were found in the mechanical properties of nano-sized oxide dispersion high-Cr ODS ferritic steel. A series of paper begins with alloy design of "Super ODS steel". Corrosion issue requires Cr concentration more than 14wt.%, but aging embrittlement issue requires less than 16wt.%. An addition of 4wt.%Al is effective to improve corrosion resistance of 16wt.%Cr-ODS steel in supercritical water (SCW) and lead-bismuth eutectic (LBE), while it is detrimental to high-temperature strength. Additions of 2wt.%W and 0.1wt.%Ti are necessary to keep high strength at elevated temperatures. An addition of small amount of Zr or Hf results in a significant increase in creep strength at 700 °C in Al added ODS steels. Tube manufacturing was successfully done for the super ODS steel candidates. "Super ODS steel" is promising for the fuel cladding material of next generation nuclear systems, and the R&D is now ready to proceed to the next stage of empirical verification.

Original languageEnglish
Title of host publicationInternational Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009
PublisherAtomic Energy Society of Japan
Pages2187-2194
Number of pages8
ISBN (Electronic)9781617386084
Publication statusPublished - 2009 Jan 1
Externally publishedYes
EventInternational Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009 - Shinjuku, Tokyo, Japan
Duration: 2009 May 102009 May 14

Publication series

NameInternational Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009
Volume3

Other

OtherInternational Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009
CountryJapan
CityShinjuku, Tokyo
Period09/5/1009/5/14

ASJC Scopus subject areas

  • Energy Engineering and Power Technology
  • Nuclear Energy and Engineering

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  • Cite this

    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. (2009). Super ODS steels R&D for fuel cladding of next generation nuclear systems 1) Introduction and alloy design. In International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009 (pp. 2187-2194). (International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009; Vol. 3). Atomic Energy Society of Japan.