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Development of High Irradiation Resistant and Corrosion Resistant Oxide Dispersion Strengthened Austenitic Stainless Steels

  • Takahiro Ishizaki
  • Yusaku Maruno
  • Kiyohiro Yabuuchi
  • Sosuke Kondo
  • Akihiko Kimura
Conference paper
Part of the The Minerals, Metals & Materials Series book series (MMMS)

Abstract

The next generation of light water reactors, resource renewable BWR (RBWR), which can be burned trans uranium (TRU) is currently under development at Hitachi. The RBWR requires a high flux of fast neutron for efficient burning of the TRU, which is four times as large as that of the ABWR. Therefore, structural materials require both a high resistance to corrosion and to irradiation. In this study, oxide dispersion strengthened austenitic stainless steels (ODS-ASUS) with high corrosion resistance have been developed. The objective of this research is to evaluate irradiation resistance and SCC susceptibility in a simulated reactor water environment for the ODS-ASUS. The materials were irradiated with 6.4 MeV Fe3+ at 673 K up to 8.0 dpa using the DuET facility at Kyoto University. The creviced bent beam (CBB) test is conducted to assess the SCC susceptibility in the hot water, 288 °C, 8 MPa with a dissolved oxygen of 8 ppm.

Keywords

ODS Stainless steel IASCC SCC RIS Ion irradiation test 

References

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    T. Hino et al., Core Designs of RBWR (Resource-renewable BWR) for Recycling and Transmutation of Transuranium Elements—an Overview, in Proceedings of ICAPP 2014 Paper 14271 (2014) Google Scholar
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    R. Takeda et al., RBWRs for fissioning almost all uranium and transuraniums. Trans. Am. Nucl. Soc. 107, 853 (2012)Google Scholar
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    M. Kodama et al., IASCC Susceptibility of Austenitic Stainless Steels Irradiated to High Neutron Fluence, in Proceedings of 6th International Symposium on Environmental Degradation of Materials in Nuclear Power System Water Reactors, pp. 583–589 (1993)Google Scholar
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    M. Kodama et al., Effect of Pre-Irradiation Grain Boundary Chemistry on IASCC, in Proceedings of 9th International Symposium on Environmental Degradation of Materials in Nuclear Power System Water Reactors, pp. 923–929 (1999)Google Scholar

Copyright information

© The Minerals, Metals & Materials Society 2019

Authors and Affiliations

  • Takahiro Ishizaki
    • 1
  • Yusaku Maruno
    • 1
  • Kiyohiro Yabuuchi
    • 2
  • Sosuke Kondo
    • 2
  • Akihiko Kimura
    • 2
  1. 1.Research & Development GroupHitachi Ltd.Hitachi-shiJapan
  2. 2.Kyoto University, Institute of Advanced EnergyUji-shiJapan

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