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

Autor:	Paulech Juraj, Kutiš Vladimír, Gálik Gabriel, Jakubec Jakub, Sedlár Tibor
Jazyk:	angličtina
Rok vydání:	2017
Předmět:	cfd analysis ansys cfx nuclear reactor vver-440 refuelling Engineering (General). Civil engineering (General) TA1-2040
Zdroj:	Journal of Mechanical Engineering, Vol 67, Iss 1, Pp 87-92 (2017)
Druh dokumentu:	article
ISSN:	2450-5471 2017-0009
DOI:	10.1515/scjme-2017-0009
Popis:	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.
Databáze:	Directory of Open Access Journals
Externí odkaz:	https://doaj.org/article/1ae197a261904317a92677f75cad1167 Zobrazit plný text záznamu View record in DOAJ