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
Mechanical Analysis of Clamp for Powerline Conductors
Paulech, Juraj, Kutiš, Vladimír, Gálik, Gabriel, Murín, Justín
Software for Model Preparation of Transmission Lattice Construction
Paulech, Juraj, Gálik, Gabriel, Kutiš, Vladimír, Murín, Justín
CFD Analysis of Dry Cask Nuclear Fuel Storage
Kutiš, Vladimír, Gálik, Gabriel, Paulech, Jauraj, Murín, Justín, Goga, Vladimír