Interface design of the blanket system for CFETR
文献类型:期刊论文
作者 | Lei, Mingzhun1; Song, Yuntao1; Ni, Xiaojun1; Wu, Xinghua2; Shen, Junsong1; Liu, Sumei1; Liu, Songlin1; Wang, Xiaoyu2; Cheng, Yong1; Xie, Yuanlai1 |
刊名 | NUCLEAR FUSION |
出版日期 | 2020-12-01 |
卷号 | 60 |
ISSN号 | 0029-5515 |
关键词 | CFETR interface design blanket system integration |
DOI | 10.1088/1741-4326/abb1f7 |
通讯作者 | Song, Yuntao(songyt@ipp.ac.cn) |
英文摘要 | The China Fusion Engineering Test Reactor (CFETR) aims to bridge the gaps between fusion experimental reactor ITER and demonstration fusion power reactor. Blanket, one of the key components of the CFETR, is of great importance to achieve the functions of tritium breeding, heat extraction and radiation shielding. As for the next device for fusion energy research in China, two blanket candidate options have been developing in parallel to decrease the risk of both physical and technical issues. Apart from the research and design work on the breeding blanket module itself, the interfaces definition and integration of the blanket system is vital, particularly due to the system interdependencies. The interface design of the blanket system is a challenge due to several factors, such as the thermal expansion, the electromagnetic loads, the feasibility of remote maintenance. In this paper, a preliminary interface definition and integration design of the CFETR blanket system has been presented, based on the design with R = 7.2 m and a = 2.2 m. The purpose is to complete the interface definition and integrated design of the blanket and other components or systems. The vacuum vessel has 16 sectors, and each sector has two inboard and three outboard blanket segments. The blanket segment will be installed and removed by remote maintenance tools through the upper ports. The work addresses the interfaces between the blanket and other system, such as diagnostic system and heating system. Preliminary assessment of the impact on tritium breeding ratio (TBR) for the candidate water cooled ceramic breeder blanket integration scheme has been presented highlighting the influence of the auxiliary interfaces system to TBR. |
WOS关键词 | CONCEPTUAL DESIGN ; FUSION ; MAINTENANCE |
资助项目 | National Key R&D Program of China[2017YFE0300503] ; National Key R&D Program of China[2017YFE0300604] ; Collaborative Innovation Program of Hefei Science Center, CAS[2019HSC-CIP006] |
WOS研究方向 | Physics |
语种 | 英语 |
出版者 | IOP PUBLISHING LTD |
WOS记录号 | WOS:000577944400001 |
资助机构 | National Key R&D Program of China ; Collaborative Innovation Program of Hefei Science Center, CAS |
源URL | [http://ir.hfcas.ac.cn:8080/handle/334002/104651] |
专题 | 中国科学院合肥物质科学研究院 |
通讯作者 | Song, Yuntao |
作者单位 | 1.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China 2.Southwest Inst Phys, Chengdu 610041, Peoples R China |
推荐引用方式 GB/T 7714 | Lei, Mingzhun,Song, Yuntao,Ni, Xiaojun,et al. Interface design of the blanket system for CFETR[J]. NUCLEAR FUSION,2020,60. |
APA | Lei, Mingzhun.,Song, Yuntao.,Ni, Xiaojun.,Wu, Xinghua.,Shen, Junsong.,...&Lu, Kun.(2020).Interface design of the blanket system for CFETR.NUCLEAR FUSION,60. |
MLA | Lei, Mingzhun,et al."Interface design of the blanket system for CFETR".NUCLEAR FUSION 60(2020). |
入库方式: OAI收割
来源:合肥物质科学研究院
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