CFD Analysis of Downcomer of Nuclear Reactor VVER 440
Vladimír Kutiš, Jakub Jakubec, Juraj Paulech, Gálik Gálik, Tibor Sedlár
Influence of Bypass on Thermo-Hydraulics of VVER 440 Fuel Assembly
Jakub Jakubec, Juraj Paulech, Vladimír Kutiš, Gabriel Gálik
Thermo-Hydraulic Behaviour of Coolant in Nuclear Reactor VVER-440 Under Refuelling Conditions
Juraj Paulech, Vladimír Kutiš, Gabriel Gálik, Jakub Jakubec, Tibor Sedlár
Modeling of Coolant Flow Within the Spent Fuel Storage Pool of a VVER 440 Reactor
Gabriel Gálik, Vladimír Kutiš, Jakub Jakubec, Juraj Paulech, Tibor Sedlár