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EN
Safety terms play the most significant role during designing process and exploitation of a nuclear power plant. The safety analysis is conducted according to the definition of the design-basis accident. A scenario of such accident Jn case of a pressurized water reactor usually assumes a rupture of the main pipeline of the primary cooling circuit and a leakage of the coolant into the reactor building. To prevent progression of the accident and potential contamination of the power plant environment the nuclear reactor with all the primary circuit and safety systems are enclosed within a hermetic building of a containment. The whole is often called as the accident localization system. A review of the contemporary constructions of the accident localization systems for the WER 440 nuclear reactors operating near to Polish borders has been done. Simulations of the containment response during the design-basis accident have been realized using a model of thermodynaimc processes taking place within the containment. On the basis of the results of the simulations for a loss-of-coolant accident (LOCA) a comparative analysis of the effectiveness of operation of the considered systems has been carried out. The most interesting outcomes of calculations and conclusions are presented in the paper.
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