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Corrosion resistance of fuel element steel cladding in a lead coolant

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Abstract

The corrosion resistance of experimental and industrial steels considered as possible materials for fuel element cladding in the BREST reactor is investigated. Static corrosion tests in lead at 750°C lasting up to 1000 h, as well as metallographic and x-ray analysis, have been performed. Data are provided on the composition and relative width of a diffusion barrier in the form of complex oxides arising in the corrosion interaction zone and impeding the diffusion of oxygen into steel, as well as the values of the averaged oxygen diffusion coefficient. The corrosion resistance in lead of the newly developed steel Kh18S2VBFMAYu and steel 16Kh12MVSFBR (ÉP 823) proposed as cladding for fuel elements in the BREST reactor is analyzed.

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Authors and Affiliations

  1. A. A. Bochvar All-Russia Research Institute of Inorganic Materials, Moscow, Russia

    G. K. Zelenskii, A. G. Ioltukhovskii, M. V. Leont’eva-Smirnova, I. A. Naumenko & S. A. Tolkachenko

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  1. G. K. Zelenskii
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  2. A. G. Ioltukhovskii
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  3. M. V. Leont’eva-Smirnova
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  4. I. A. Naumenko
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  5. S. A. Tolkachenko
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Translated from Metallovedenie i Termicheskaya Obrabotka Metallov, No. 11, pp. 34–39, November, 2007.

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Zelenskii, G.K., Ioltukhovskii, A.G., Leont’eva-Smirnova, M.V. et al. Corrosion resistance of fuel element steel cladding in a lead coolant. Met Sci Heat Treat 49, 533–538 (2007). https://doi.org/10.1007/s11041-007-0098-2

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  • DOI: https://doi.org/10.1007/s11041-007-0098-2

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