Conceptual Design of 15 Tesla Conductor Test Facility for Future Fusion Reactor
文献类型：期刊论文
| 作者 | Dai, Chao1; Wu, Yu1 ; Qin, Jinggang1; Shi, Yi1; Xu, Aihua4; Wu, Kaihong3; Zhang, Yongliang3; Yu, Xiaopeng1; Hao, Qiangwang1; Nijuis, Arend2
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| 刊名 | IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY
 |
| 出版日期 | 2020-06-01 |
| 卷号 | 30 |
| 关键词 | Conductors Niobium-tin Superconducting magnets Magnetic fields Magnetomechanical effects Test facilities Strain CFETR conductor test facility split magnet electro-magnetic design conductor design |
| ISSN号 | 1051-8223 |
| DOI | 10.1109/TASC.2020.2974951 |
| 通讯作者 | Dai, Chao() |
| 英文摘要 | "China Fusion Engineering Test Reactor (CFETR)" is a new generation of tokamak which aims to bridge the gaps between the fusion experimental reactor ITER and the demonstration reactor (DEMO). The superconducting magnet system is the core component in tokamak and future fusion reactor, and the superconducting magnet system for CFETR will be a big challenge due to the higher magnetic field is required. Based on the current design, the maximum field of Toroidal Field (TF) coil is around 14.5 T, and for Center Solenoid (CS) coil, the maximum field would be even higher. Now the significant work is developing highperformance Cable-in-Conduit Conductor (CICC) for these high field coils. Obviously, a test facility is necessary for developing new CICCs. It is well known that SULTAN facility plays an important and successful role in ITER conductor development, almost all ITER sample conductors were tested at SULTAN. But it's hard to satisfy future test work due to its magnetic field limitation (<12 T). Now in China, a new program has been launched to build a new conductor test facility which has similar functions to SULTAN, but can provide background field up to 15 T. This paper will introduce the concept design of the magnet system of the superconducting conductor test facility. |
| 资助项目 | China Fusion Engineering Experimental Reactor General Integration and Engineering Design[2017YFE0300503] ; Natural Science Foundation of the Jiangsu Higher Education Institutions of China[19KJB470011] |
| WOS研究方向 | Engineering ; Physics |
| 语种 | 英语 |
| WOS记录号 | WOS:000522368100001 |
| 出版者 | IEEE-INST ELECTRICAL ELECTRONICS ENGINEERS INC |
| 资助机构 | China Fusion Engineering Experimental Reactor General Integration and Engineering Design ; Natural Science Foundation of the Jiangsu Higher Education Institutions of China |
| 源URL | [http://ir.hfcas.ac.cn:8080/handle/334002/103627]  |
| 专题 | 中国科学院合肥物质科学研究院 |
| 通讯作者 | Dai, Chao |
| 作者单位 | 1.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China 2.Univ Twente, Energy Mat & Syst, Fac Sci & Technol, NL-7500 AE Enschede, Netherlands 3.Univ Sci & Technol China, Hefei 230026, Peoples R China 4.Changzhou Vocat Inst Mechatron Technol, Changzhou 213164, Jiangsu, Peoples R China |
| 推荐引用方式 GB/T 7714 | Dai, Chao,Wu, Yu,Qin, Jinggang,et al. Conceptual Design of 15 Tesla Conductor Test Facility for Future Fusion Reactor[J]. IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY,2020,30. |
| APA | Dai, Chao.,Wu, Yu.,Qin, Jinggang.,Shi, Yi.,Xu, Aihua.,...&Nijuis, Arend.(2020).Conceptual Design of 15 Tesla Conductor Test Facility for Future Fusion Reactor.IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY,30. |
| MLA | Dai, Chao,et al."Conceptual Design of 15 Tesla Conductor Test Facility for Future Fusion Reactor".IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY 30(2020). |
入库方式： OAI收割
来源：合肥物质科学研究院
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