Behaviour of coolant in VVER-440 under major outage conditions

The paper presents the numerical simulation of thermo-hydraulic behaviour of coolant in nuclear reactor VVER-440 under major outage conditions. Heating-up and the flow of coolant between the reactor pressure vessel and spent fuel storage pool are discussed.

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Bibliographic Details
Main Authors: Paulech, Juraj, Murín, Jstín, Kutiš, Vladimír, Gálik, Gabriel, Uličný, Michal Miloslav
Format: Conference Proceeding
Language:English
Subjects:
Coolants
Fuel storage
Nuclear reactors
Outages
Pressure vessels
Spent nuclear fuels
Online Access:Get full text
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Description
Summary:The paper presents the numerical simulation of thermo-hydraulic behaviour of coolant in nuclear reactor VVER-440 under major outage conditions. Heating-up and the flow of coolant between the reactor pressure vessel and spent fuel storage pool are discussed.
ISSN:0094-243X
1551-7616
DOI:10.1063/5.0137657