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The thermal circuit of a nuclear power station’s unit built around a supercritical-pressure water-cooled reactor

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Abstract

Main results obtained from calculations of the steam generator and thermal circuit of the steam turbine unit for a nuclear power unit with supercritical-pressure water coolant and integral layout are presented. The obtained characteristics point to the advisability of carrying out further developments of this promising nuclear power technology.

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References

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Authors and Affiliations

  1. Russian Scientific Centre Kurcharov Institute, pl. Akademika Kurchatova 1, Moscow, 123182, Russia

    V. A. Silin

  2. Moscow Power Engineering Institute, ul. Krasnokazarmennaya 14, Moscow, 111250, Russia

    V. M. Zorin, A. M. Tagirov, O. I. Tregubova, I. V. Belov & P. V. Povarov

Authors
  1. V. A. Silin
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  2. V. M. Zorin
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  3. A. M. Tagirov
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  4. O. I. Tregubova
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  5. I. V. Belov
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  6. P. V. Povarov
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Additional information

Original Russian Text © V.A. Silin, V.M. Zorin, A.M. Tagirov, O.I. Tregubova, I.V. Belov, P.V. Povarov, 2010, published in Teploenergetika.

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Silin, V.A., Zorin, V.M., Tagirov, A.M. et al. The thermal circuit of a nuclear power station’s unit built around a supercritical-pressure water-cooled reactor. Therm. Eng. 57, 1028–1034 (2010). https://doi.org/10.1134/S0040601510120062

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  • DOI: https://doi.org/10.1134/S0040601510120062

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