Numerical evaluation of hypothetical core disruptive accident in full- scale model of sodium-cooled fast reactor

doi:10.1016/j.net.2021.12.005

IMECH-IR > 非线性力学国家重点实验室

	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)
发表期刊	NUCLEAR ENGINEERING AND TECHNOLOGY
	2022-06
卷号	54 期号:6 页码:2120
ISSN	1738-5733
摘要	A 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.
关键词	Hypothetical core destructive accidents Sodium-cooled fast reactors Multi-material arbitrary Lagrangian-Eulerian (MMALE) method Fluid-structure interactions
学科领域	Nuclear Science & Technology
DOI	10.1016/j.net.2021.12.005
收录类别	SCI
语种	英语
WOS记录号	WOS:000822928600008
项目资助者	National Natural Science Foundation of China [11772343] ; Beijing Institute of Technology Research Fund Program for Young Scholars
论文分区	一类
力学所作者排名	1
RpAuthor	Chen, XD (corresponding author), Beijing Inst Technol, Sch Aerosp Engn, Beijing 100081, Peoples R China.
引用统计
文献类型	期刊论文
条目标识符	http://dspace.imech.ac.cn/handle/311007/90200
专题	非线性力学国家重点实验室
作者单位	1.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
推荐引用方式 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.
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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