Study on the influences of RPV deformation on CHF under IVR conditions

After the reactor core melt, the thermal impact of high temperature molten mixture to the lower head of reactor pressure vessel (RPV) will cause the shape change of cooling channel constituted by reactor pressure vessel outer surface and other supporting structures. This phenomenon may lead to local...

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Main Authors: Shuang Wen, Xinli Gao, Rui Zhang, Kebin Fan, Bin Jia, Jianping Jing, Fudong Liu, Xinlu Tian
Format: Article
Language:English
Published: Frontiers Media S.A. 2023-02-01
Series:Frontiers in Energy Research
Subjects:
Online Access:https://www.frontiersin.org/articles/10.3389/fenrg.2023.1087135/full
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author Shuang Wen
Shuang Wen
Xinli Gao
Xinli Gao
Rui Zhang
Kebin Fan
Bin Jia
Bin Jia
Jianping Jing
Fudong Liu
Fudong Liu
Xinlu Tian
Xinlu Tian
Xinlu Tian
author_facet Shuang Wen
Shuang Wen
Xinli Gao
Xinli Gao
Rui Zhang
Kebin Fan
Bin Jia
Bin Jia
Jianping Jing
Fudong Liu
Fudong Liu
Xinlu Tian
Xinlu Tian
Xinlu Tian
author_sort Shuang Wen
collection DOAJ
description After the reactor core melt, the thermal impact of high temperature molten mixture to the lower head of reactor pressure vessel (RPV) will cause the shape change of cooling channel constituted by reactor pressure vessel outer surface and other supporting structures. This phenomenon may lead to local heat transfer deterioration and then cause the failure of in-vessel retention (IVR). Therefore, it is necessary to study the reactor pressure vessel deformation under in-vessel retention conditions. This paper proposes a numerical method for the CHF of the outer wall of reactor pressure vessel using ANSYS and FLUENT. The geometry of coolant channel is modeled by ANSYS with the coupling of temperature and mechanical field analysis in ANSYS, and the critical heat flux (CHF) of reactor pressure vessel outer surface is further predicted by FLUENT. With the comparing between test data and calculation, the calculation methods are verified. The results show that the CHF will be decreased by the deformation of PRV caused by the core melt.
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spelling doaj.art-db4602946939427a91f8f08fd2e58b142023-02-09T04:35:45ZengFrontiers Media S.A.Frontiers in Energy Research2296-598X2023-02-011110.3389/fenrg.2023.10871351087135Study on the influences of RPV deformation on CHF under IVR conditionsShuang Wen0Shuang Wen1Xinli Gao2Xinli Gao3Rui Zhang4Kebin Fan5Bin Jia6Bin Jia7Jianping Jing8Fudong Liu9Fudong Liu10Xinlu Tian11Xinlu Tian12Xinlu Tian13Nuclear and Radiation Safety Center, Ministry of Environmental Protection, Beijing, ChinaState Environmental Protection Key Laboratory of Nuclear and Radiation Safety Regulatory Simulation and Validation, Beijing, ChinaNuclear and Radiation Safety Center, Ministry of Environmental Protection, Beijing, ChinaState Environmental Protection Key Laboratory of Nuclear and Radiation Safety Regulatory Simulation and Validation, Beijing, ChinaCollege of Nuclear Science and Technology, Harbin Engineering University, Harbin, ChinaNuclear and Radiation Safety Center, Ministry of Environmental Protection, Beijing, ChinaNuclear and Radiation Safety Center, Ministry of Environmental Protection, Beijing, ChinaState Environmental Protection Key Laboratory of Nuclear and Radiation Safety Regulatory Simulation and Validation, Beijing, ChinaNuclear and Radiation Safety Center, Ministry of Environmental Protection, Beijing, ChinaNuclear and Radiation Safety Center, Ministry of Environmental Protection, Beijing, ChinaState Environmental Protection Key Laboratory of Nuclear and Radiation Safety Regulatory Simulation and Validation, Beijing, ChinaNuclear and Radiation Safety Center, Ministry of Environmental Protection, Beijing, ChinaState Environmental Protection Key Laboratory of Nuclear and Radiation Safety Regulatory Simulation and Validation, Beijing, ChinaCollege of Nuclear Science and Technology, Harbin Engineering University, Harbin, ChinaAfter the reactor core melt, the thermal impact of high temperature molten mixture to the lower head of reactor pressure vessel (RPV) will cause the shape change of cooling channel constituted by reactor pressure vessel outer surface and other supporting structures. This phenomenon may lead to local heat transfer deterioration and then cause the failure of in-vessel retention (IVR). Therefore, it is necessary to study the reactor pressure vessel deformation under in-vessel retention conditions. This paper proposes a numerical method for the CHF of the outer wall of reactor pressure vessel using ANSYS and FLUENT. The geometry of coolant channel is modeled by ANSYS with the coupling of temperature and mechanical field analysis in ANSYS, and the critical heat flux (CHF) of reactor pressure vessel outer surface is further predicted by FLUENT. With the comparing between test data and calculation, the calculation methods are verified. The results show that the CHF will be decreased by the deformation of PRV caused by the core melt.https://www.frontiersin.org/articles/10.3389/fenrg.2023.1087135/fullIVRCHFCFD analysisRPVcoolant channel
spellingShingle Shuang Wen
Shuang Wen
Xinli Gao
Xinli Gao
Rui Zhang
Kebin Fan
Bin Jia
Bin Jia
Jianping Jing
Fudong Liu
Fudong Liu
Xinlu Tian
Xinlu Tian
Xinlu Tian
Study on the influences of RPV deformation on CHF under IVR conditions
Frontiers in Energy Research
IVR
CHF
CFD analysis
RPV
coolant channel
title Study on the influences of RPV deformation on CHF under IVR conditions
title_full Study on the influences of RPV deformation on CHF under IVR conditions
title_fullStr Study on the influences of RPV deformation on CHF under IVR conditions
title_full_unstemmed Study on the influences of RPV deformation on CHF under IVR conditions
title_short Study on the influences of RPV deformation on CHF under IVR conditions
title_sort study on the influences of rpv deformation on chf under ivr conditions
topic IVR
CHF
CFD analysis
RPV
coolant channel
url https://www.frontiersin.org/articles/10.3389/fenrg.2023.1087135/full
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