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

doi:10.1016/j.net.2021.12.005

CORC > 力学研究所 > 中国科学院力学研究所 > 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)
刊名	NUCLEAR ENGINEERING AND TECHNOLOGY ; 6
	2022-06
卷号	54 页码:2120
关键词	Hypothetical core destructive accidents Sodium-cooled fast reactors Multi-material arbitrary Lagrangian-Eulerian (MMALE) method Fluid-structure interactions
ISSN号	1738-5733
DOI	10.1016/j.net.2021.12.005
英文摘要	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.
学科主题	Nuclear Science & Technology
分类号	一类
语种	英语
WOS记录号	WOS:000822928600008
资助机构	National Natural Science Foundation of China [11772343] ; Beijing Institute of Technology Research Fund Program for Young Scholars
其他责任者	Chen, XD (corresponding author), Beijing Inst Technol, Sch Aerosp Engn, Beijing 100081, Peoples R China.
内容类型	期刊论文
源URL	[http://dspace.imech.ac.cn/handle/311007/90200]
专题	力学研究所_非线性力学国家重点实验室
作者单位	1.Univ Chinese Acad Sci, Sch Engn Sci, Beijing 100049, Peoples R China 2.Chinese Acad Sci, Inst Mech, State Key Lab Nonlinear Mech, Beijing 100190, Peoples R China 3.Zhejiang Univ, Dept Engn Mech, Hangzhou 310027, Peoples R China 4.Beijing Inst Technol, Sch Aerosp Engn, Beijing 100081, 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, 6,2022,54:2120.
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,54,2120.
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(2022):2120.