Journal of Mechanical Engineering (Apr 2017)

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

  • Paulech Juraj,
  • Kutiš Vladimír,
  • Gálik Gabriel,
  • Jakubec Jakub,
  • Sedlár Tibor

DOI
https://doi.org/10.1515/scjme-2017-0009
Journal volume & issue
Vol. 67, no. 1
pp. 87 – 92

Abstract

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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.

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