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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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
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creator Paulech, Juraj
Murín, Jstín
Kutiš, Vladimír
Gálik, Gabriel
Uličný, Michal Miloslav
description 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.
doi_str_mv 10.1063/5.0137657
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source American Institute of Physics:Jisc Collections:Transitional Journals Agreement 2021-23 (Reading list)
subjects Coolants
Fuel storage
Nuclear reactors
Outages
Pressure vessels
Spent nuclear fuels
title Behaviour of coolant in VVER-440 under major outage conditions
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