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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.

eISSN:
2450-5471
Language:
English
Publication timeframe:
2 times per year
Journal Subjects:
Engineering, Mechanical Engineering, Fundamentals of Mechanical Engineering, Mechanics