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Influence of Bypass on Thermo-Hydraulics of VVER 440 Fuel Assembly Cover

Influence of Bypass on Thermo-Hydraulics of VVER 440 Fuel Assembly

Open Access
|May 2017

References

  1. [1] N.E. Todreas, M.S. Kazimi. Nuclear Systems Volume I: Thermal Hydraulic Fundamentals. CRC Press; 2 edition, 2011. ISBN 1439808872.
  2. [2] H. Versteeg, W. Malalasekera. An Introduction to Computational Fluid Dynamics: The Finite Volume Method. Prentice Hall; 2 edition, 2007. ISBN 0131274988
  3. [3] D.A. Oleksyuk L.L. Kobzar. "Experiments on simulation of coolant mixing in fuel assembly head and core exit channel of VVER-440 reactor," Kurchatov Institute, Moscow, 2006
  4. [4] J. Jakubec, V. Kutiš, G. Gálik, J. Paulech. Coolant mixing processes simulations of nuclear reactor VVER440 fuel assembly. SVSFEM ANSYS User’s Group Meeting, 2015.
  5. [5] V. Kutiš, J. Jakubec, J. Paulech, G. Gálik, T. Sedlár. CFD Analysis of Downcomer of Nuclear Reactor VVER 440. Journal of Mechanical Engineering - Strojnícky časopis, 2016 (66), No. 2, 55 - 62.
DOI: https://doi.org/10.1515/scjme-2017-0007 | Journal eISSN: 2450-5471 | Journal ISSN: 0039-2472
Language: English
Page range: 69 - 76
Published on: May 3, 2017
Published by: Slovak University of Technology in Bratislava
In partnership with: Paradigm Publishing Services
Publication frequency: 2 issues per year

© 2017 Jakub Jakubec, Juraj Paulech, Vladimír Kutiš, Gabriel Gálik, published by Slovak University of Technology in Bratislava
This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 License.