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Microstructure Instability of Candidate Fuel Cladding Alloys: Corrosion and Stress Corrosion Cracking Implications

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Abstract

This paper addresses some of the overarching aspects of microstructure instability expected from both high temperature and radiation exposure that could affect the corrosion and stress corrosion cracking (SCC) resistance of the candidate austenitic Fe-Cr-Ni alloys being considered for the fuel cladding of the Canadian supercritical water-cooled reactor (SCWR) concept. An overview of the microstructure instability expected by both exposures is presented prior to turning the focus onto the implications of such instability on the corrosion and SCC resistance. Results from testing conducted using pre-treated (thermally-aged) Type 310S stainless steel to shed some light on this important issue are included to help identify the outstanding corrosion resistance assessment needs.

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Acknowledgements

Funding to Canada Gen-IV National Program was provided by Natural Resources Canada through the Office of Energy Research and Development, Canadian Nuclear Laboratories (formerly Atomic Energy of Canada Limited), and Natural Sciences and Engineering Research Council of Canada.

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Authors and Affiliations

  1. Department of Materials Science & Engineering, McMaster University, Hamilton, ON, L8S 4L7, Canada

    Yinan Jiao & Joseph Kish

  2. CanmetMATERIALS, Natural Resources Canada, Hamilton, ON, L8P 0A5, Canada

    Wenyue Zheng

  3. Canadian Nuclear Laboratories, Calk River, ON, K0J 1J0, Canada

    David Guzonas

Authors
  1. Yinan Jiao
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  2. Wenyue Zheng
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  3. David Guzonas
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  4. Joseph Kish
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Correspondence to Joseph Kish.

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Jiao, Y., Zheng, W., Guzonas, D. et al. Microstructure Instability of Candidate Fuel Cladding Alloys: Corrosion and Stress Corrosion Cracking Implications. JOM 68, 485–489 (2016). https://doi.org/10.1007/s11837-015-1739-3

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  • DOI: https://doi.org/10.1007/s11837-015-1739-3

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