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Mechanical Properties of Fuel Cladding Candidate Alloys for Canadian SCWR Concept

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Abstract

An assessment of tensile and creep of five representative candidate fuel cladding alloys for a Canadian Gen IV super-critical water reactor concept was performed based on database development work and complementary experiments including a transmission electron microscopy study of creep in stainless steels. The limiting property would be creep strength of candidate alloys for the “free-standing” fuel cladding design with a hot-spot peak temperature range of 1073–1123 K (800–850°C).

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References

  1. S. Xu, S.-M. Jin, and P. Le Dreff-Kerwin (Paper presented at ASME Pressure Vessels and Piping Conference (PVP2013), Paris, France, 14–18 July 2013).

  2. S. Xu, W. Zheng, and L. Yang, CMAT Open Technical Report, 2014-2480-RT, 2015.

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Acknowledgements

This work forms part of the CanmetMATERIALS (CMAT) Project on high-temperature mechanical properties of reactor materials supported by the Next Generation Nuclear Program in the Canadian Federal Program of Energy Research and Development (PERD). Dr. Wenyue Zheng and the PERD committee are gratefully acknowledged for their comments and guidance. We would like to gratefully acknowledge Mr. J. Liang for performing mechanical tests, as well as Ms. C. Bibby for the TEM sample preparation. We would also like to thank Mr. P. Le Dreff-Kerwin and Ms. S.-M. Jin for their assistance in database development work during their internships at CanmetMATERIALS. Finally, we would like to thank a reviewer’s comments on the article.

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Authors and Affiliations

  1. CanmetMATERIALS, Natural Resources Canada, Hamilton, ON, Canada

    Su Xu & Babak Shalchi Amirkhiz

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  1. Su Xu
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  2. Babak Shalchi Amirkhiz
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Correspondence to Su Xu.

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Xu, S., Amirkhiz, B.S. Mechanical Properties of Fuel Cladding Candidate Alloys for Canadian SCWR Concept. JOM 68, 469–474 (2016). https://doi.org/10.1007/s11837-015-1725-9

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  • DOI: https://doi.org/10.1007/s11837-015-1725-9

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