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Atomic Energy

, Volume 125, Issue 3, pp 172–177 | Cite as

Transverse Transport and Heat Transfer in Smooth VVER Fuel-Rod Bundle with Cellular Spacer Grid

  • P. V. Markov
  • V. I. Solonin
Article
  • 4 Downloads

The results of the numerical modeling of flow and heat transfer in a bundle of smooth fuel rods spaced by a cellular grid in application to VVER are presented. The results are analyzed and compared with computational-experimental studies in the homegrown and foreign nuclear power industries. The computational region simulating a VVER FA fragment, a mathematical model, and the boundary conditions are described. The results of a calculation of the coolant flow velocity field and the temperature field for the fuel-rod cladding under conditions of stabilized heat transfer in the bundle and on a section of stabilization beyond the cellular spacer grid are presented. Flow in the bundle and the mechanisms of interchannel transfer are described. Recommendations are given for taking account of the grid effect on intensification of heat transfer in the bundle, and a comparison is made with data obtained for plate-shaped spacer grids in PWR.

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References

  1. 1.
    V. P. Spasskov, Yu. G. Dragunov, S. B. Ryzhov, et al., Computational Validation for the Thermohydraulic Characteristics of a VVER Reactor and Reactor Facilities, Akademkniga, Moscow (2004).Google Scholar
  2. 2.
    P. L. Kirillov, V. P. Bobkov, A. V. Zhukov, and Yu. S. Yur’ev, Handbook of Thermal Calculations in the Nuclear Power Industry, Vol. 1, Thermohydraulic Processes in Nuclear Power Facilities, IzdAt, Moscow (2010).Google Scholar
  3. 3.
    I. A. Belov and S. A. Isaev, Simulation of Turbulent Flows: Teach. Aid, Balt. Gos. Tekhn. Universitet, St. Petersburg (2001).Google Scholar
  4. 4.
    G. A.Simakov, V. G. Vereshchak, Yu. N. Babenko, et al., Patent 2256960 RF, “The spacer grid and method of manufacturing same,” Byull. Izobret. Polezn. Modeli, No. 20, 2592–2600 (2005).Google Scholar
  5. 5.
    V. D. Shmelev, Yu. G. Dragunov, V. P. Denisov, and I. N. Vasilchenko, VVER Cores for Nuclear Power Plants, Akademkniga, Moscow (2004).Google Scholar
  6. 6.
    S. Yang and M. Chung, “Spacer grid effects on turbulent flow in rod bundles,” J. Korean Nucl. Soc., No. 1, 56 (1996).Google Scholar
  7. 7.
    I. Ya. Emel’yanov, V. I. Mikhan, and V. I. Solonin, Design of Nuclear Reactors, N. A. Dollezhal (ed.), Energoizdat, Moscow (1982).Google Scholar
  8. 8.
    X. Cui and K. Kim, “Three-dimensional analysis of turbulent heat transfer and flow through mixing vane in a subchannel of nuclear reactor,” J. Nucl. Sci. Technol., No. 10, 719–724 (2003).CrossRefGoogle Scholar
  9. 9.
    V. N. Smolin, Study of the Thermohydraulics of Nuclear Reactor Cores on Model Stands, NIKIET, Moscow (2005).Google Scholar

Copyright information

© Springer Science+Business Media, LLC, part of Springer Nature 2018

Authors and Affiliations

  • P. V. Markov
    • 1
  • V. I. Solonin
    • 1
  1. 1.Bauman Moscow State Technical University (BMSTU)MoscowRussia

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