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Determination of the Coefficients of Heat Transfer and Friction in Supercritical-Pressure Nuclear Reactors with Account of the Intensity and Scale of Flow Turbulence on the Basis of the Theory of Stochastic Equations and Equivalence of Measures

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Journal of Engineering Physics and Thermophysics Aims and scope

New dependences of the coefficients of heat transfer and friction have been presented which are used for calculations in the reactor core at a supercritical water pressure by taking account of the parameters of perturbation in the coolant flow: of the intensity and scale of flow turbulence. These solutions have been obtained based on stochastic systems of equations for the turbulence and the equivalence of measures between deterministic (laminar) and random (turbulent) flows.

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Authors and Affiliations

  1. National Research Nuclear University [Moscow Engineering Physics Institute (MEPhI)], 31 Kashirskoe Highway, Moscow, 115409, Russia

    A. V. Dmitrenko

  2. Russian University of Transport [Moscow State University of Railway Engineering (MIIT)], 9 Obraztsov Str., Moscow, 12794, Russia

    A. V. Dmitrenko

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  1. A. V. Dmitrenko
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Correspondence to A. V. Dmitrenko.

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Translated from Inzhenerno-Fizicheskii Zhurnal, Vol. 90, No. 6, pp. 1356–1363, November–December, 2017.

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Dmitrenko, A.V. Determination of the Coefficients of Heat Transfer and Friction in Supercritical-Pressure Nuclear Reactors with Account of the Intensity and Scale of Flow Turbulence on the Basis of the Theory of Stochastic Equations and Equivalence of Measures. J Eng Phys Thermophy 90, 1288–1294 (2017). https://doi.org/10.1007/s10891-017-1685-8

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  • DOI: https://doi.org/10.1007/s10891-017-1685-8

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