机构

• 合肥物质科学研究院 [5]
• 高能物理研究所 [1]
• 中国科学院大学 [1]

采集方式

• OAI收割 [6]
• iSwitch采集 [1]

内容类型

• 期刊论文 [7]

发表日期

• 2022 [2]
• 2021 [1]
• 2020 [1]
• 2017 [1]
• 2015 [1]
• 2009 [1]
• 更多

学科主题

• Thermodyna... [1]

筛选

浏览/检索结果: 共7条，第1-7条 帮助 条数/页： 5101520253035404550556065707580859095100 排序方式： 请选择题名升序题名降序提交时间升序提交时间降序作者升序作者降序发表日期升序发表日期降序 Design and Development of Turn Insulation Automatic Wrapping System for CRAFT TF 期刊论文  OAI收割 IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2022, 卷号: 32 作者:  He, Jian;  Wu, Jiefeng;  Wen, Wei;  Yan, Zhaohui;  Wu, Yu   |  收藏  |  浏览/下载：37/0  |  提交时间：2022/12/23 Wrapping  Conductors  Insulation  Fixtures  Windings  Rails  Magnetic heads  Comprehensive Research Facility for Fusion Technology (CRAFT)  Denavit-Hartenberg (D-H) method  motion control  toroidal field coil  turn insulation wrapping   Updates on CEA Design and Experimental Activities on EU DEMO TF System 期刊论文  OAI收割 IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2022, 卷号: 32 作者:  Zani, L.;  Bonne, F.;  Corato, V.;  Decool, P.;  Hertout, P.   |  收藏  |  浏览/下载：41/0  |  提交时间：2022/12/23 Conductors  Stress  Superconducting magnets  Toroidal magnetic fields  Europe  Costs  Windings  DEMO  LTS  Nb3Sn  nuclear fusion  super- conducting magnets  TF coils   Performance test and analysis of the first large-scale cable-in-conduit conductor with high J(c) Nb3Sn strand for fusion reactor 期刊论文  OAI收割 NUCLEAR FUSION, 2021, 卷号: 61 作者:  Dai, Chao;  Wu, Yu;  Li, Jiangang;  Guo, Zichuan;  Qin, Jinggang   |  收藏  |  浏览/下载：42/0  |  提交时间：2021/04/26 CFETR  fusion conductors  high current superconducting cables  high magnetic field  high-J(c) Nb3Sn strand  STP cable pattern   Development and Test Results of a Full-Size Joint Sample for the CFETR Central Solenoid Model Coil 期刊论文  OAI收割 IEEE TRANSACTIONS ON PLASMA SCIENCE, 2020, 卷号: 48 作者:  Ma, Guanghui;  Wu, Yu;  Qin, Jinggang;  Liu, Huajun;  Hao, Qiangwang   |  收藏  |  浏览/下载：55/0  |  提交时间：2020/10/26 Conductors  Welding  Cable shielding  Resistance  Steel  Soldering  Silver  Cable-in-conduit conductor (CICC)  central solenoid model coil (CSMC)  Chinese Fusion Engineering Testing Reactor (CFETR)  dc resistance  joint   New design of cable-in-conduit conductor for application in future fusion reactors 期刊论文  OAI收割 SUPERCONDUCTOR SCIENCE & TECHNOLOGY, 2017, 卷号: 30, 期号: 11, 页码: 11 作者:  Qin, Jinggang;  Wu, Yu;  Li, Jiangang;  Liu, Fang;  Dai, Chao   |  收藏  |  浏览/下载：23/0  |  提交时间：2019/02/28 CFETR  Cable-in-conduit conductors  magnetic cycling loading  copper wound superconducting strand  nuclear fusion   Study on mitigation of pulsed heat load for ITER cryogenic system 期刊论文  OAI收割 CRYOGENICS, 2015, 卷号: 66, 页码: 1-5 作者:  Peng, N;  Xiong, LY 收藏  |  浏览/下载：79/0  |  提交时间：2016/04/18 Cable in conduit conductors  Thermodynamics  Fusion magnets   Thermo-hydraulic analysis of the gradual cool-down to 80 k of the iter toroidal field coil 期刊论文  iSwitch采集 Cryogenics, 2009, 卷号: 49, 期号: 8, 页码: 402-406 作者:  Peng, N.;  Liu, L. Q.;  Serio, L.;  Xiong, L. Y.;  Zhang, L. 收藏  |  浏览/下载：32/0  |  提交时间：2019/05/10 Cable in conduit conductors  Thermodynamics  Fusion magnets