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An experimental substantiation of the emergency cooldown system project for the KLT-40S reactor installation of a floating nuclear cogeneration station

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Abstract

Results from thermal-hydraulic tests of a full-scale module of the emergency cooldown system for a KLT-40S reactor installation are presented. The validity of the solutions adopted in its design is shown. Recommendations for calculating the heat transfer coefficients during steam flow condensation and condensate cooling are given.

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Authors and Affiliations

  1. NPO Central Boiler-Turbine Institute, ul. Atamanskaya 3/6, St. Petersburg, 191167, Russia

    B. F. Balunov, A. A. Shcheglov, V. A. Il’in & E. N. Saikova

  2. Afrikantov Experimental Design Office for Machinery Construction, Burnakovskii proezd 15, Nizhni Novgorod, 603074, Russia

    M. A. Bol’shukhin, O. A. Bykh, A. M. Khizbullin & A. N. Sokolov

Authors
  1. B. F. Balunov
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  2. A. A. Shcheglov
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  3. V. A. Il’in
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  4. E. N. Saikova
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  5. M. A. Bol’shukhin
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  6. O. A. Bykh
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  7. A. M. Khizbullin
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  8. A. N. Sokolov
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Additional information

Original Russian Text © B.F. Balunov, A.A. Shcheglov, V.A. Il’in, E.N. Saikova, M.A. Bol’shukhin, O.A. Bykh, A.M. Khizbullin, A.N. Sokolov, 2011, published in Teploenergetika.

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Balunov, B.F., Shcheglov, A.A., Il’in, V.A. et al. An experimental substantiation of the emergency cooldown system project for the KLT-40S reactor installation of a floating nuclear cogeneration station. Therm. Eng. 58, 418–423 (2011). https://doi.org/10.1134/S0040601511050028

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  • DOI: https://doi.org/10.1134/S0040601511050028

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