中国科学院机构知识库网格
Chinese Academy of Sciences Institutional Repositories Grid
Experimental study of stratification behavior of the steady two-liquid corium pool

文献类型:期刊论文

作者Xue, Baoquan1,3,4; Yang, Yaqian3,4; Liang, Tian3,4; Chen, Bo3,4; Ma, Yingche3,4; Liu, Kui3,4; Shan, Hongyi2; Kang, Taifeng2; Gu, Peiwen5
刊名NUCLEAR ENGINEERING AND DESIGN
出版日期2022-05-01
卷号391页码:8
ISSN号0029-5493
关键词Severe accident In-vessel melt retention Stratification behavior Sub-oxidized corium Layer inversion
DOI10.1016/j.nucengdes.2022.111727
通讯作者Chen, Bo(bchen@imr.ac.cn) ; Ma, Yingche(ycma@imr.ac.cn)
英文摘要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.
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
语种英语
出版者ELSEVIER SCIENCE SA
WOS记录号WOS:000782569900003
资助机构Major projects of Science and Technology of China - China government (National Energy Administration) ; CAS Key Laboratory of Nuclear Materials and Satety Assessment
源URL[http://ir.imr.ac.cn/handle/321006/172812]  
专题金属研究所_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.CNNC North Nucl Fuel Components Co Ltd, Baotou 014000, Peoples R China
3.Chinese Acad Sci, Inst Met Res, Shi Changxu Innovat Ctr Adv Mat, Shenyang 110016, Peoples R China
4.IMR NMSA, CAS Key Lab Nucl Mat & Satety Assessment, Shenyang 110016, 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.

入库方式: OAI收割

来源:金属研究所

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