Performance test and analysis of the first large-scale cable-in-conduit conductor with high J(c) Nb3Sn strand for fusion reactor
文献类型:期刊论文
作者 | Dai, Chao2; Wu, Yu2; Li, Jiangang2; Guo, Zichuan3; Qin, Jinggang2; Long, Feng2; Nijhuis, Arend1; Bruzzone, Pierluigi4; Stepanov, Boris4; Shi, Yi2 |
刊名 | NUCLEAR FUSION |
出版日期 | 2021-03-01 |
卷号 | 61 |
ISSN号 | 0029-5515 |
关键词 | CFETR fusion conductors high current superconducting cables high magnetic field high-J(c) Nb3Sn strand STP cable pattern |
DOI | 10.1088/1741-4326/abdbcd |
通讯作者 | Li, Jiangang() |
英文摘要 | The Comprehensive Research Facility for Fusion Technology (CRAFT) project has been launched in 2019, for developing the essential engineering technologies for Chinese Fusion Engineering Testing Reactor (CFETR). Within this project, a full-size toroidal field (TF) coil will be built as the prototype coil for CFETR. Based on design of CFETR magnet system, the TF coil will operate at 95.6 kA in a peak field of 14.5 T. The high-J(c) Nb3Sn strand is taken into consideration due to the critical current density of ITER-grade Nb3Sn is too low at 14.5 T. Considering that it will be the first time to apply the high-J(c) Nb3Sn strand in the large-scale cable-in-conduit conductor (CICC) for fusion magnet, a conductor sample made of high-J(c) Nb3Sn strand with short twist pitch (STP) cable pattern was manufactured in ASIPP and tested in SULTAN facility, to investigate the feasibility. The test campaign focuses on the impact of cyclic electromagnetic (EM) loading and warm-up cool-down (WUCD) to the performance of the conductor, the strain distribution of the conductor before and after EM cycles was measured by inductive method to make a deeper insight of the conductor performance evolution. AC losses tests have also been carried out, providing relevant information for further coil design. |
资助项目 | Comprehensive Research Facility for Fusion Technology Program of China[2018-000052-73-01-001228] ; National Key R&D Program of China[2017YFE0301404] ; Fund of Science Foundation of CASHIPS[YZJJ2019QN12] |
WOS研究方向 | Physics |
语种 | 英语 |
出版者 | IOP PUBLISHING LTD |
WOS记录号 | WOS:000621507800001 |
资助机构 | Comprehensive Research Facility for Fusion Technology Program of China ; National Key R&D Program of China ; Fund of Science Foundation of CASHIPS |
源URL | [http://ir.hfcas.ac.cn:8080/handle/334002/120454] |
专题 | 中国科学院合肥物质科学研究院 |
通讯作者 | Li, Jiangang |
作者单位 | 1.Univ Twente, Fac Sci & Technol, Energy Mat & Syst, NL-7500 AE Enschede, Netherlands 2.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China 3.Univ Sci & Technol China, Hefei 230026, Peoples R China 4.EPFL CRPP, Fus Technol, CH-5232 Villigen, Switzerland 5.China Int Nucl Fus Energy Program Execut Ctr, Beijing 100862, Peoples R China 6.CERN, TE Dept, CH-1211 Geneva 23, Switzerland 7.Baiyin Nonferrous Changtong Wire & Cable Co Ltd, Baiyin 730900, Gansu, Peoples R China |
推荐引用方式 GB/T 7714 | Dai, Chao,Wu, Yu,Li, Jiangang,et al. Performance test and analysis of the first large-scale cable-in-conduit conductor with high J(c) Nb3Sn strand for fusion reactor[J]. NUCLEAR FUSION,2021,61. |
APA | Dai, Chao.,Wu, Yu.,Li, Jiangang.,Guo, Zichuan.,Qin, Jinggang.,...&Xiang, Binglun.(2021).Performance test and analysis of the first large-scale cable-in-conduit conductor with high J(c) Nb3Sn strand for fusion reactor.NUCLEAR FUSION,61. |
MLA | Dai, Chao,et al."Performance test and analysis of the first large-scale cable-in-conduit conductor with high J(c) Nb3Sn strand for fusion reactor".NUCLEAR FUSION 61(2021). |
入库方式: OAI收割
来源:合肥物质科学研究院
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