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Wear of frictional surfaces in high-temperature lead and lead—bismuth coolants

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Russian Engineering Research Aims and scope

Abstract

The wear of frictional steel and cast-iron surfaces in high-temperature (400–550°C) liquid-metal coolants in BREST and SVBR nuclear-power units is studied experimentally. It is shown that long life of the surfaces in reactor operation may be ensured by applying and maintaining protective oxide coatings.

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Authors and Affiliations

  1. Alekseev Nizhegorodsk State Technical University, Nizhny Novgorod, Russia

    A. V. Beznosov, T. A. Bokova, M. A. Antonenkov & K. A. Makhov

  2. Blagonravov Institute of Mechanical Engineering, Moscow, Russia

    Yu. N. Drozdov & V. N. Puchkov

  3. OAO OKB Gidropress, Moscow, Russia

    V. V. Makarov

Authors
  1. A. V. Beznosov
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  2. T. A. Bokova
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  3. M. A. Antonenkov
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  4. K. A. Makhov
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  5. Yu. N. Drozdov
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  6. V. N. Puchkov
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  7. V. V. Makarov
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Corresponding author

Correspondence to A. V. Beznosov.

Additional information

Original Russian Text © A.V. Beznosov, T.A. Bokova, M.A. Antonenkov, K.A. Makhov, Yu.N. Drozdov, V.N. Puchkov, V.V. Makarov, 2010, published in Vestnik Mashinostroeniya, 2010, No. 2, pp. 34–39.

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Beznosov, A.V., Bokova, T.A., Antonenkov, M.A. et al. Wear of frictional surfaces in high-temperature lead and lead—bismuth coolants. Russ. Engin. Res. 30, 128–132 (2010). https://doi.org/10.3103/S1068798X10020073

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  • DOI: https://doi.org/10.3103/S1068798X10020073

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