Experimental study of stratification behavior of the steady two-liquid corium pool

doi:10.1016/j.nucengdes.2022.111727

IMR OpenIR

	Experimental study of stratification behavior of the steady two-liquid corium pool
	Xue, Baoquan 1,2,3; Yang, Yaqian 2,3; Liang, Tian 2,3; Chen, Bo 2,3; Ma, Yingche 2,3; Liu, Kui 2,3; Shan, Hongyi 4; Kang, Taifeng 4; Gu, Peiwen 5
通讯作者	Chen, Bo(bchen@imr.ac.cn) ; Ma, Yingche(ycma@imr.ac.cn)
	2022-05-01
发表期刊	NUCLEAR ENGINEERING AND DESIGN
ISSN	0029-5493
卷号	391 页码:8
摘要	The prototypic materials have been used to investigate the stratification behavior of the steady molten pool at 3100 K in the context of the IVR condition. Induction heating in a cold crucible was used for melting of the 2 kg scale UO2-ZrO2-Zr-Fe. A post-test examination of SEM, EDS, and XRD has been performed to investigate the metallic and oxide layers for all ingots. The effects of M-Fe/M sigma-ary sumation (initial iron to corium ratio) and Cn (initial degree of zirconium oxidation) on the configuration of the molten pool were studied. The results indicate that structure of the molten pools consists of the top light metallic layer and oxide layer. Nevertheless, a layer inversion may occur when the density of the metallic layer increased. The synergistic effect of MFe/M n-ary sumation and Cn on redistribution of the corium components leads to a significant increase of the uranium concentration for the metallic phase, which can explain why the layer inversion of the molten pool occurred.
关键词	Severe accident In-vessel melt retention Stratification behavior Sub-oxidized corium Layer inversion
资助者	Major projects of Science and Technology of China - China government (National Energy Administration) ; CAS Key Laboratory of Nuclear Materials and Satety Assessment
DOI	10.1016/j.nucengdes.2022.111727
收录类别	SCI
语种	英语
资助项目	Major projects of Science and Technology of China - China government (National Energy Administration)[2018ZX06002004] ; CAS Key Laboratory of Nuclear Materials and Satety Assessment[2021NMSAKF04]
WOS研究方向	Nuclear Science & Technology
WOS类目	Nuclear Science & Technology
WOS记录号	WOS:000782569900003
出版者	ELSEVIER SCIENCE SA
引用统计
文献类型	期刊论文
条目标识符	http://ir.imr.ac.cn/handle/321006/172813
专题	中国科学院金属研究所
通讯作者	Chen, Bo; Ma, Yingche
作者单位	1.Univ Sci & Technol China, Sch Mat Sci & Engn, Shenyang 110016, Peoples R China 2.Chinese Acad Sci, Inst Met Res, Shi Changxu Innovat Ctr Adv Mat, Shenyang 110016, Peoples R China 3.IMR NMSA, CAS Key Lab Nucl Mat & Satety Assessment, Shenyang 110016, Peoples R China 4.CNNC North Nucl Fuel Components Co Ltd, Baotou 014000, Peoples R China 5.Shanghai Nucl Engn Res & Design Inst Co Ltd, Shanghai 200233, Peoples R China
推荐引用方式 GB/T 7714	Xue, Baoquan,Yang, Yaqian,Liang, Tian,et al. Experimental study of stratification behavior of the steady two-liquid corium pool[J]. NUCLEAR ENGINEERING AND DESIGN,2022,391:8.
APA	Xue, Baoquan.,Yang, Yaqian.,Liang, Tian.,Chen, Bo.,Ma, Yingche.,...&Gu, Peiwen.(2022).Experimental study of stratification behavior of the steady two-liquid corium pool.NUCLEAR ENGINEERING AND DESIGN,391,8.
MLA	Xue, Baoquan,et al."Experimental study of stratification behavior of the steady two-liquid corium pool".NUCLEAR ENGINEERING AND DESIGN 391(2022):8.