Safety analysis of the 100 kA HTS current lead for CFETR
文献类型:期刊论文
作者 | Han, Quan; Ding, Kaizhong![]() ![]() ![]() ![]() ![]() ![]() |
刊名 | FUSION ENGINEERING AND DESIGN
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出版日期 | 2020-04-01 |
卷号 | 153 |
关键词 | CFETR HTS Current lead Safety analysis LOFA |
ISSN号 | 0920-3796 |
DOI | 10.1016/j.fusengdes.2020.111481 |
通讯作者 | Ding, Kaizhong(kzding@ipp.ac.cn) |
英文摘要 | Based on the Agreement of Institute of Plasma Physics Chinese Academy of Sciences (ASIPP) and Ministry of Science and Technology of China during the Thirteen Five-Years Plan (so called 13.5 plan), a dedicated test facility of superconducting magnet for China Fusion Engineering Test Reactor (CFETR) will be constructed in Hefei, China. A pair of high temperature superconducting (HTS) current leads rated at 100 kA for the CFETR magnet test facility is being designed at ASIPP. Because magnetic energy stored in the toroidal field magnet is 134 Giga Joules which are 3 times higher than the ITER case, HTS current leads must work at nominal current without performance degradation during the HTS current lead quench. In order to verify the safety and reliability of HTS current lead, the analysis of static magnetic field is done by ANSYS iteration to predict the maximum current carrying capacity of HTS module. This paper also give the numerical calculation of loss of flow accident(LOFA) of HTS current lead and temperature margin analysis of HTS module. The analysis results indicate that the HTS module has a current carrying capacity of 165 kA without external field at 65 K and a current carrying capacity of 149 kA with external 30 mT vertical field at 65 K. The LOFA time is about 580 s and the burnout time is about 30 s, which is better than the requirement of the toroidal field coil fast discharge time of 24 s. |
资助项目 | National Magnetic Confinement Fusion Science Program of China[2017YFE0300503] ; ITER feeder Procurement package[1.1.P5A.CN.01] |
WOS研究方向 | Nuclear Science & Technology |
语种 | 英语 |
WOS记录号 | WOS:000518408500029 |
出版者 | ELSEVIER SCIENCE SA |
资助机构 | National Magnetic Confinement Fusion Science Program of China ; ITER feeder Procurement package |
源URL | [http://ir.hfcas.ac.cn:8080/handle/334002/103775] ![]() |
专题 | 中国科学院合肥物质科学研究院 |
通讯作者 | Ding, Kaizhong |
作者单位 | Chinese Acad Sci, Inst Plasma Phys, Hefei, Anhui, Peoples R China |
推荐引用方式 GB/T 7714 | Han, Quan,Ding, Kaizhong,Lu, Kun,et al. Safety analysis of the 100 kA HTS current lead for CFETR[J]. FUSION ENGINEERING AND DESIGN,2020,153. |
APA | Han, Quan.,Ding, Kaizhong.,Lu, Kun.,Liu, Chenglian.,Liu, Chen.,...&Song, Yuntao.(2020).Safety analysis of the 100 kA HTS current lead for CFETR.FUSION ENGINEERING AND DESIGN,153. |
MLA | Han, Quan,et al."Safety analysis of the 100 kA HTS current lead for CFETR".FUSION ENGINEERING AND DESIGN 153(2020). |
入库方式: OAI收割
来源:合肥物质科学研究院
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