Thermo-Hydraulic Behaviour of Coolant in Nuclear Reactor VVER-440 Under Refuelling Conditions

Thermo-Hydraulic Behaviour of Coolant in Nuclear Reactor VVER-440 Under Refuelling Conditions

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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Bibliographische Detailangaben
Veröffentlicht in:Strojnícky casopis - Journal of Mechanical Engineering 2017-04, Vol.67 (1), p.87-92
Hauptverfasser: Paulech, Juraj, Kutiš, Vladimír, Gálik, Gabriel, Jakubec, Jakub, Sedlár, Tibor
Format: Artikel
Sprache:eng
Schlagworte:
ANSYS CFX
CFD analysis
Nuclear Reactor
refuelling
VVER-440
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Beschreibung
Zusammenfassung: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.
ISSN:2450-5471
2450-5471
DOI:10.1515/scjme-2017-0009