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浏览/检索结果: 共11条，第1-10条 帮助 限定条件 发表日期：2021     已选(0)清除 条数/页：5101520253035404550556065707580859095100   排序方式：请选择作者升序作者降序题名升序题名降序发表日期升序发表日期降序提交时间升序提交时间降序 Prototype Development of Pulsed Power Supply for HT-6M Tokamak 期刊论文 IEEE TRANSACTIONS ON PLASMA SCIENCE, 2021 作者:  Guan, Rui;  Zhang, Jian;  Huang, Yiyun;  Gao, Zongqiu;  Zhou, Yu 收藏  |  浏览/下载：65/0  |  提交时间：2022/02/14 Capacitors  Power supplies  Voltage  Switches  Prototypes  Inductors  Thyristors  Capacitor energy storage pulsed power supply  HT-6M tokamak  toroidal field   A study on nuclear analysis of the divertor region of the CFETR 期刊论文 PLASMA SCIENCE & TECHNOLOGY, 2021, 卷号: 23 作者:  Saidahmed, Rayyan;  Yao, Damao;  Wu, Qiuran;  Liu, Songlin;  Xu, Tiejun 收藏  |  浏览/下载：25/0  |  提交时间：2021/11/15 CFETR  fusion reactor  divertor  nuclear analysis  divertor region   Effects of resonant magnetic perturbations on neutral beam heating in a tokamak 期刊论文 PHYSICS OF PLASMAS, 2021, 卷号: 28 作者:  Hu, Youjun;  Xu, Yingfeng;  Hao, Baolong;  Li, Guoqiang;  He, Kaiyang 收藏  |  浏览/下载：38/0  |  提交时间：2022/01/25 Optimization of the cooling design of TF coil case on CFETR 期刊论文 FUSION ENGINEERING AND DESIGN, 2021, 卷号: 172 作者:  Sang, Aiguo;  Li, Junjun;  Wen, Xinghao;  Ren, Yong;  Liu, Xiaogang 收藏  |  浏览/下载：37/0  |  提交时间：2022/01/10 CFETR  TF coil case  Nuclear heat load  Thermal analysis  Orthogonal theory   Investigation on the Tritium Self-Sufficiency and Neutron Shielding Based on a Water-Cooled Blanket for CFETR at 1.5 GW 期刊论文 IEEE TRANSACTIONS ON PLASMA SCIENCE, 2021, 卷号: 49 作者:  Li, Jie;  Zhang, Jie;  Liu, Changle;  Liu, Xiaogang;  Gao, Xiang 收藏  |  浏览/下载：55/0  |  提交时间：2021/11/15 Neutrons  Plasmas  Solid modeling  Inductors  Production  Optimization  Loading  China Fusion Engineering Test Reactor (CFETR)  neutronics study  neutron wall loading (NWL)  tritium breeding ratio (TBR)  water-cooled ceramic breeder (WCCB)   Assessment of Mechanical Properties of Welding Joints for ITER Correction Coils Cases at Cryogenic Temperature 期刊论文 IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2021, 卷号: 31 作者:  Huang, Chuanjun;  Xin, Jijun;  Wei, Jing;  Zhang, Hengcheng;  Huang, Rongjin 收藏  |  浏览/下载：89/0  |  提交时间：2021/11/15 Cryogenic  ITER correction coil (CC) case  mechanical property  microstructures  welding joints   Penetration of n = 2 resonant magnetic field perturbations in EAST 期刊论文 NUCLEAR FUSION, 2021, 卷号: 61 作者:  Ren, Jie;  Sun, You-Wen;  Wang, Hui-Hui;  Gu, Shuai;  Qian, Jin-Ping 收藏  |  浏览/下载：111/0  |  提交时间：2021/05/31 tokamak  field penetration  intrinsic error field  phasing scan  mode coupling   Penetration of n? =? 2 resonant magnetic field perturbations in EAST 期刊论文 Nuclear Fusion, 2021, 卷号: 61 作者:  Ren,Jie;  Sun,You-Wen;  Wang,Hui-Hui;  Gu,Shuai;  Qian,Jin-Ping 收藏  |  浏览/下载：79/0  |  提交时间：2021/05/24 tokamak  field penetration  intrinsic error field  phasing scan  mode coupling   Quench Analysis of the CFETR TF Coil Using the Gandalf Code 期刊论文 IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2021, 卷号: 31 作者:  Wen, Xinghao;  Li, Junjun;  Sang, Aiguo;  Ren, Yong;  Liu, Xiaogang 收藏  |  浏览/下载：57/0  |  提交时间：2021/04/26 China fusion engineering test reactor (CFETR)  quench  superconducting magnet  thermal-hydraulic   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 NUCLEAR FUSION, 2021, 卷号: 61 作者:  Dai, Chao;  Wu, Yu;  Li, Jiangang;  Guo, Zichuan;  Qin, Jinggang 收藏  |  浏览/下载：101/0  |  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