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Upgrade of Separator-Superheaters in Nuclear Power Plants with Pressurized Water and Boiling Water Reactors by Physical-Modeling Based Modernization

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Abstract

Russian systems of intermediate separation and superheating of steam, operated as part of steam turbines of all nuclear power plants, operate with an insufficient level of reliability and efficiency. Design temperatures of overheating steam are not reached in most cases. The paper analyzes the characteristics of the working processes occurring in the apparatus: the flow of superheated wet steam in the separator and the superheater stages, dehumidification and subsequent flow of the separation in the separators, the intensity of heat exchange between the condensing heating steam of high pressure and the heated steam of low pressure, as well as the condensate flow of heating steam. Proposals are formulated to create more reliable and efficient devices, taking into account half a century of domestic and international experience in their design and operation.

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Authors and Affiliations

  1. St. Petersburg State University of Aerospace Instrumentation, 190000, St. Petersburg, Russia

    M. Egorov

  2. Peter the Great St. Petersburg Polytechnic University, 195251, St. Petersburg, Russia

    M. Egorov

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  1. M. Egorov
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Correspondence to M. Egorov.

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Egorov, M. Upgrade of Separator-Superheaters in Nuclear Power Plants with Pressurized Water and Boiling Water Reactors by Physical-Modeling Based Modernization. J. Surf. Investig. 14 (Suppl 1), S31–S34 (2020). https://doi.org/10.1134/S1027451020070113

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  • DOI: https://doi.org/10.1134/S1027451020070113

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