Thermo-Hydraulic Behaviour of Coolant in Nuclear Reactor VVER-440 Under Refuelling Conditions
Journal Title: Strojnicky casopis - Journal of Mechanical Engineering - Year 2017, Vol 67, Issue 1
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.
Authors and Affiliations
Juraj Paulech, Vladimír Kutiš, Gabriel Gálik, Jakub Jakubec and Tibor Sedlár
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