Pressure wave behavior and its effects on structure under In-box LOCA in a helium-cooled lead lithium blanket of hydrogen fusion reactors
Zhang, Shichao; Wang, Zhen; Chen, Chao; Jia, Jiangtao; Chen, Zhibin
刊名INTERNATIONAL JOURNAL OF HYDROGEN ENERGY
2021-02-08
卷号46
关键词Breeding blanket Structural stress Pressure wave propagation Fluid-solid interaction Inbox-LOCA
ISSN号0360-3199
DOI10.1016/j.ijhydene.2020.11.228
通讯作者Wang, Zhen(zhen.wang@inest.cas.cn) ; Jia, Jiangtao(jiangtao.jia@inest.cas.cn)
英文摘要The helium-cooled lead lithium (PbLi) blanket is considered as one of the candidate blanket concepts selected for the hydrogen fusion DEMO reactors and beyond, which has the advantages of simple structure, strong heat removal capacity and high tritium breeding ratio. However, due to the harsh environment such as high-energy neutron irradiation, high thermal load and great pressure gradient, there is a high possibility that one or some of the thousands of coolant channels will break in the breeding zone, which is so-called In-box Loss of Coolant Accident (In-box LOCA). When the accident occurs, the high pressure helium will rapidly inject into the lead lithium flow channel, generating a complex two-phase flow and great pressure shock effect, which may cause the peak pressure to exceed the design limit and threaten the integrity of the blanket structure. Therefore, it is of great significance to perform the transient analysis of in-box LOCA to improve the safety of the blanket and avoid the leakage of radioactive materials. In this paper, a two-way coupling model for fluid-solid interaction was established based on the ANSYS Workbench, and the model were validated through the experimental data obtained by injecting the high pressure helium gas into liquid lithium lead. Then the validated model was applied to the transient pressure wave propagation analysis and structural stress analysis of the Dual-Functional Lithium Lead (DFLL) blanket in order to explore the integrity of blanket structure under In-box LOCA. In addition, the effects of break location on pressure and structural stress was also investigated through six cases. The study found that the transient pressure in the DFLL blanket gone through three stages in any case: step rise, oscillate, and flatten out. Pressure peaks occurred during oscillations and their values were strongly dependent on the break location. The closer to the inlet/outlet, the higher the peak pressure was. The maximum pressure reached more than twice of the inlet pressure (up to similar to 16 MPa). As a result, the structural stress in some local areas has exceeded the allowable limits, and the corresponding suggestions for improvement have also been put forward. This study can provide guidance for safety design, operation and accident mitigation measures of helium-cooled lead lithium blankets. (C) 2020 Hydrogen Energy Publications LLC. Published by Elsevier Ltd. All rights reserved.
资助项目National Key R&D Program of China[2019YFE0191600] ; National Natural Science Foundation of China[51906249]
WOS研究方向Chemistry ; Electrochemistry ; Energy & Fuels
语种英语
出版者PERGAMON-ELSEVIER SCIENCE LTD
WOS记录号WOS:000614913800011
资助机构National Key R&D Program of China ; National Natural Science Foundation of China
内容类型期刊论文
源URL[http://ir.hfcas.ac.cn:8080/handle/334002/120248]  
专题中国科学院合肥物质科学研究院
通讯作者Wang, Zhen; Jia, Jiangtao
作者单位Chinese Acad Sci, Inst Nucl Energy Safety Technol, Hefei Inst Phys Sci, Hefei 230031, Anhui, Peoples R China
推荐引用方式
GB/T 7714
Zhang, Shichao,Wang, Zhen,Chen, Chao,et al. Pressure wave behavior and its effects on structure under In-box LOCA in a helium-cooled lead lithium blanket of hydrogen fusion reactors[J]. INTERNATIONAL JOURNAL OF HYDROGEN ENERGY,2021,46.
APA Zhang, Shichao,Wang, Zhen,Chen, Chao,Jia, Jiangtao,&Chen, Zhibin.(2021).Pressure wave behavior and its effects on structure under In-box LOCA in a helium-cooled lead lithium blanket of hydrogen fusion reactors.INTERNATIONAL JOURNAL OF HYDROGEN ENERGY,46.
MLA Zhang, Shichao,et al."Pressure wave behavior and its effects on structure under In-box LOCA in a helium-cooled lead lithium blanket of hydrogen fusion reactors".INTERNATIONAL JOURNAL OF HYDROGEN ENERGY 46(2021).
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