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Oxidation Kinetics of Austenitic Stainless Steels as SCWR Fuel Cladding Candidate Materials in Supercritical Water

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Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors

Part of the book series: The Minerals, Metals & Materials Series ((MMMS))

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Abstract

The oxidation kinetics of supercritical-water-cooled reactor (SCWR) fuel cladding candidate materials, e.g. 15Cr-20Ni stainless steel (1520 SS) in supercritical water at 650 and 700 °C under 24 MPa has been investigated. Characteristics of oxide layers and its relation to oxidation behaviors are also studied. The applicability of the candidate materials for the fuel cladding of SCWR from oxidation kinetics, spalling susceptibility of oxide layer, and breakdown of Cr2O3 layer points of view has been discussed. The results indicate that the threshold condition for spalling of oxide layer is different at 650 and 700 °C. The decrease in oxidation kinetics of 1520 SS with time correspond to the change in rate-limiting process of oxidation from mass transfer through an Fe oxides to mass transfer through a Cr rich oxide layer with time. Based on the oxidation kinetics obtained in this study, 1520 SS is considered suitable for a fuel cladding of SCWR in combination with appropriate CW process. However, detailed evaluation and countermeasures for the degradation due to nodular oxidation are needed before application of tube-shaped 1520 SS in supercritical water at 700 °C. On the other hand, it is estimated that the use of that at 650 °C is acceptable because the weight gain after long-term exposure was considered to be much less than the threshold condition of the spalling.

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Acknowledgements

Present study includes the result of “Research and Development of the Super Fast Reactor” entrusted to The University of Waseda by the Ministry of Education, Culture, Sports, Science and Technology of Japan (MEXT).

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Authors and Affiliations

  1. Graduate School of Engineering, Tohoku University, 6-6-01-2 Aoba, Aramaki, Aoba-ku, Sendai, 980-8579, Japan

    Hiroshi Abe, Ryuichi Suzuki & Yutaka Watanabe

Authors
  1. Hiroshi Abe
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  2. Ryuichi Suzuki
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  3. Yutaka Watanabe
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Corresponding author

Correspondence to Hiroshi Abe .

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Editors and Affiliations

  1. Idaho National Laboratory, Idaho Falls, ID, USA

    John H. Jackson

  2. Naval Nuclear Laboratory, Pittsburgh, PA, USA

    Denise Paraventi

  3. Chalk River Laboratories, Canadian Nuclear Laboratories, Chalk River, ON, Canada

    Michael Wright

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© 2019 The Minerals, Metals & Materials Society

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Abe, H., Suzuki, R., Watanabe, Y. (2019). Oxidation Kinetics of Austenitic Stainless Steels as SCWR Fuel Cladding Candidate Materials in Supercritical Water. In: Jackson, J., Paraventi, D., Wright, M. (eds) Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The Minerals, Metals & Materials Series. Springer, Cham. https://doi.org/10.1007/978-3-030-04639-2_75

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