Interface design of the blanket system for CFETR

doi:10.1088/1741-4326/abb1f7

	Interface design of the blanket system for CFETR
	Lei, Mingzhun 1; Song, Yuntao 1; Ni, Xiaojun 1; Wu, Xinghua 2; Shen, Junsong 1; Liu, Sumei 1; Liu, Songlin 1; Wang, Xiaoyu 2; Cheng, Yong 1; Xie, Yuanlai 1
刊名	NUCLEAR FUSION
	2020-12-01
卷号	60
关键词	CFETR interface design blanket system integration
ISSN号	0029-5515
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.
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关键词	CONCEPTUAL DESIGN ; FUSION ; MAINTENANCE
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
内容类型	期刊论文
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).