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Compatibility of Structural Materials with Sodium According to Data from the Experience Gained in 40 Years of Operation of the BR-5/BR-10 Reactor

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Abstract

The results of investigations of the corrosion characteristics of samples of structural materials cut from the main sodium loops of a BR-5/BR-10 sodium-cooled research reactor during operation over the period 1959–1999 are presented. Analysis of the results of the materials-engineering investigations show that the sodium coolant has good corrosion characteristics and that the operating lifetime of sodium equipment in commercial fast reactors can be increased to 60 yr and longer.

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Authors and Affiliations

  1. State Science Center of the Russian Federation – A. I. Leipunskii Physics and Power-Engineering Institute, Russia

    A. V. Karpov, M. Kh. Kononyuk, L. I. Mamaev & Yu. L. Kulikov

Authors
  1. A. V. Karpov
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  2. M. Kh. Kononyuk
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  3. L. I. Mamaev
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  4. Yu. L. Kulikov
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Karpov, A.V., Kononyuk, M.K., Mamaev, L.I. et al. Compatibility of Structural Materials with Sodium According to Data from the Experience Gained in 40 Years of Operation of the BR-5/BR-10 Reactor. Atomic Energy 91, 951–955 (2001). https://doi.org/10.1023/A:1014274009267

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  • DOI: https://doi.org/10.1023/A:1014274009267

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