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Thermohydraulic Calculation of VVER and SCWR Reactor Channels

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The results of a comparative thermohydraulic calculation of the core channels of two types of nuclear reactors – VVER and VVER-SKD, differing in the coolant parameters at the inlet to the core channel – are presented. It was established that at the identical thermal power the maximum temperature at the center of a VVER-SKD fuel element is lower than that of a VVER fuel element.

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Authors and Affiliations

  1. National Research Tomsk Polytechnic University, Tomsk, Russia

    A. G. Korotkikh & F. C. Parimala Rangan

Authors
  1. A. G. Korotkikh
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  2. F. C. Parimala Rangan
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Corresponding author

Correspondence to A. G. Korotkikh.

Additional information

Translated from Atomnaya Énergiya, Vol. 131, No. 3, pp. 138–142, September, 2021.

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Korotkikh, A.G., Rangan, F.C.P. Thermohydraulic Calculation of VVER and SCWR Reactor Channels. At Energy 131, 140–143 (2022). https://doi.org/10.1007/s10512-022-00855-7

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  • DOI: https://doi.org/10.1007/s10512-022-00855-7

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