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

[1] N.E. Todreas, M.S. Kazimi. Nuclear Systems Volume I: Thermal Hydraulic Fundamentals. CRC Press; 2 edition, 2011. ISBN 1439808872.10.1201/b14887Search in Google Scholar

[2] H. Versteeg, W. Malalasekera. An Introduction to Computational Fluid Dynamics: The Finite Volume Method. Prentice Hall; 2 edition, 2007. ISBN 0131274988Search in Google Scholar

[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, 2006Search in Google Scholar

[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.Search in Google Scholar

[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 - 62.10.1515/scjme-2016-0018Search in Google Scholar