Juraj Paulech, V. Kutǐs, G. Galik, J. Jakubec, T. Sedlár
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引用次数: 3
Abstract
Abstract The paper presents the numerical simulation of thermo-hydraulic behaviour of coolant in the VVER- 440 nuclear reactor under standard outage conditions. Heating-up and flow of coolant between the reactor pressure vessel and spent fuel storage pool are discussed.
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