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Analysis of features of hydrodynamics and heat transfer in the fuel assembly of prospective sodium reactor with a high rate of reproduction in the uranium-plutonium fuel cycle

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Abstract

The fast sodium reactor fuel assembly (FA) with U–Pu–Zr metallic fuel is described. In comparison with a “classical” fast reactor, this FA contains thin fuel rods and a wider fuel rod grid. Studies of the fluid dynamics and the heat transfer were carried out for such a new FA design. The verification of the ANSYS CFX code was provided for determination of the velocity, pressure, and temperature fields in the different channels. The calculations in the cells and in the FA were carried out using the model of shear stress transport (SST) selected at the stage of verification. The results of the hydrodynamics and heat transfer calculations have been analyzed.

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Authors and Affiliations

  1. National Research Center Kurchatov Institute, pl. Akademika Kurchatova 1, Moscow, 123182, Russia

    A. S. Lubina, A. S. Subbotin, A. A. Sedov & A. A. Frolov

Authors
  1. A. S. Lubina
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  2. A. S. Subbotin
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  3. A. A. Sedov
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  4. A. A. Frolov
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Corresponding author

Correspondence to A. S. Lubina.

Additional information

Original Russian Text © A.S. Lubina, A.S. Subbotin, A.A. Sedov, A.A. Frolov, 2015, published in Voprosy Atomnoi Nauki i Tekhniki, Seriya: Fizika Yadernykh Reaktorov, 2015, No. 1, pp. 37–49.

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Lubina, A.S., Subbotin, A.S., Sedov, A.A. et al. Analysis of features of hydrodynamics and heat transfer in the fuel assembly of prospective sodium reactor with a high rate of reproduction in the uranium-plutonium fuel cycle. Phys. Atom. Nuclei 79, 1315–1324 (2016). https://doi.org/10.1134/S1063778816080111

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  • DOI: https://doi.org/10.1134/S1063778816080111

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