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Numerical evaluation of hypothetical core disruptive accident in full- scale model of sodium-cooled fast reactor
Guo ZH(郭志鸿); Chen XD(陈晓东); Hu GQ(胡国庆)
Source PublicationNUCLEAR ENGINEERING AND TECHNOLOGY
2022-06
Volume54Issue:6Pages:2120
ISSN1738-5733
AbstractA hypothetical core destructive accident (HCDA) has received widespread attention as one of the most serious accidents in sodium-cooled fast reactors. This study combined recent advantages in numerical methods to realize realistic modeling of the complex fluid-structure interactions during HCDAs in a fullscale sodium-cooled fast reactor. The multi-material arbitrary Lagrangian-Eulerian method is used to describe the fluid-structure interactions inside the container. Both the structural deformations and plug rises occurring during HCDAs are evaluated. Two levels of expansion energy are considered with two different reactor models. The simulation results show that the container remains intact during an accident with small deformations. The plug on the top of the container rises to an acceptable level after the sealing between the it and its support is destroyed. The methodology established in this study provides a reliable approach for evaluating the safety feature of a container design.
KeywordHypothetical core destructive accidents Sodium-cooled fast reactors Multi-material arbitrary Lagrangian-Eulerian (MMALE) method Fluid-structure interactions
Subject AreaNuclear Science & Technology
DOI10.1016/j.net.2021.12.005
Indexed BySCI
Language英语
WOS IDWOS:000822928600008
Funding OrganizationNational Natural Science Foundation of China [11772343] ; Beijing Institute of Technology Research Fund Program for Young Scholars
Classification一类
Ranking1
ContributorChen, XD (corresponding author), Beijing Inst Technol, Sch Aerosp Engn, Beijing 100081, Peoples R China.
Citation statistics
Cited Times:3[WOS]   [WOS Record]     [Related Records in WOS]
Document Type期刊论文
Identifierhttp://dspace.imech.ac.cn/handle/311007/90200
Collection非线性力学国家重点实验室
Affiliation1.Beijing Inst Technol, Sch Aerosp Engn, Beijing 100081, Peoples R China
2.Zhejiang Univ, Dept Engn Mech, Hangzhou 310027, Peoples R China
3.Chinese Acad Sci, Inst Mech, State Key Lab Nonlinear Mech, Beijing 100190, Peoples R China
4.Univ Chinese Acad Sci, Sch Engn Sci, Beijing 100049, Peoples R China
Recommended Citation
GB/T 7714
Guo ZH,Chen XD,Hu GQ. Numerical evaluation of hypothetical core disruptive accident in full- scale model of sodium-cooled fast reactor[J]. NUCLEAR ENGINEERING AND TECHNOLOGY,2022,54,6,:2120.Rp_Au:Chen, XD (corresponding author), Beijing Inst Technol, Sch Aerosp Engn, Beijing 100081, Peoples R China.
APA 郭志鸿,陈晓东,&胡国庆.(2022).Numerical evaluation of hypothetical core disruptive accident in full- scale model of sodium-cooled fast reactor.NUCLEAR ENGINEERING AND TECHNOLOGY,54(6),2120.
MLA 郭志鸿,et al."Numerical evaluation of hypothetical core disruptive accident in full- scale model of sodium-cooled fast reactor".NUCLEAR ENGINEERING AND TECHNOLOGY 54.6(2022):2120.
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