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