Thermo-Hydraulic Behaviour of Coolant in Nuclear Reactor VVER-440 Under Refuelling Conditions
, , , y | 03 may 2017
Acerca de este artículo
Publicado en línea: 03 may 2017
Páginas: 87 - 92
DOI: https://doi.org/10.1515/scjme-2017-0009
Palabras clave
© 2017
This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 License.
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.