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Vibrational wear of pipe-spacer pair in steam generator with lead coolant

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Abstract

The vibrational wear at the junctions of heat-exchanger pipe and spacer grids is studied experimentally, so as to confirm the shock resistance of hot-water generators in fast reactors with lead coolant. Endurance tests of tube and spacer samples are conducted. Metallographic and profilometric data on samples subjected to vibrational wear are presented. The wear mechanism is described. A preliminary estimate is obtained for the pipe life in the steam generator.

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Authors and Affiliations

  1. Blagonravov Institute of Mechanical Engineering, Russian Academy of Sciences, Moscow, Russia

    Yu. N. Drozdov & V. N. Puchkov

  2. Gidropress Design Bureau, Moscow, Russia

    V. V. Makarov

  3. Nizhni Novgorod State Technical University, Moscow, Russia

    A. V. Beznosov & M. A. Antonenkov

Authors
  1. Yu. N. Drozdov
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  2. V. N. Puchkov
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  3. V. V. Makarov
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  4. A. V. Beznosov
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  5. M. A. Antonenkov
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Additional information

Original Russian Text © Yu.N. Drozdov, V.N. Puchkov, V.V. Makarov, A.V. Beznosov, M.A. Antonenkov, 2009, published in Vestnik Mashinostroeniya, 2009, No. 12, pp. 38–42.

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Drozdov, Y.N., Puchkov, V.N., Makarov, V.V. et al. Vibrational wear of pipe-spacer pair in steam generator with lead coolant. Russ. Engin. Res. 29, 1233–1236 (2009). https://doi.org/10.3103/S1068798X09120089

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  • DOI: https://doi.org/10.3103/S1068798X09120089

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