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
Keywords
Related Articles
- EP ID EP43907
- DOI https://doi.org/10.1515/scjme-2017-0009
- Views 205
- Downloads 0
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