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Secondary Flows and Transverse Exchange in Cylindrical Fuel Element Bundles

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Abstract

The problem of the possibility of an analysis of the flow structure and heat transfer based on the results of numerical modeling of coolant flow and heat exchange in smooth fuel rod bundles is discussed. The bundles are made in various versions, differing in the number of rods and the duct geometry. The distributions of axial and transverse velocities in bundles under stabilized flow conditions are described. An analysis of the mechanisms determining the exchange of mass and momentum between individual subchannels (cells) of the rod bundle is conducted. For the Reynolds number Re = 6.84 × 104, the coefficients of hydraulic friction resistance in various bundles are calculated and compared with the coefficient of hydraulic friction resistance of an infinite rod lattice obtained under similar conditions. The values of the heat exchange coefficient, a value used in one-dimensional models of thermal10.1134-hydraulic calculations of nuclear reactor cores, are calculated.

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This work was supported by ongoing institutional funding. No additional grants to carry out or direct this particular research were obtained.

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  1. Bauman Moscow State Technical University, 105005, Moscow, Russia

    P. V. Markov & V. I. Solonin

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  1. P. V. Markov
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  2. V. I. Solonin
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Correspondence to P. V. Markov.

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Translated by A. Kolemesin

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Markov, P.V., Solonin, V.I. Secondary Flows and Transverse Exchange in Cylindrical Fuel Element Bundles. J. Mach. Manuf. Reliab. 52 (Suppl 2), S180–S186 (2023). https://doi.org/10.1134/S1052618823100096

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  • DOI: https://doi.org/10.1134/S1052618823100096

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