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Profile controlling technologies in ITER BTCC U-shaped case manufacturing process 期刊论文
FUSION ENGINEERING AND DESIGN, 2022, 卷号: 179
作者:  Feng, Siqing;  Song, Yuntao;  Wei, Jing;  Yin, Dapeng;  Liu, Peng
收藏  |  浏览/下载：31/0  |  提交时间：2022/12/23
BTCC U-shaped case  Profile controlling  Segmenting  Welding  Residual stress treatment  
Structural Design and Analysis of the BCC Temporary Supports 期刊论文
IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2021, 卷号: 31
作者:  Yu, Chao;  Wang, Qiqi;  Guo, Liang;  Wu, Yu;  Jin, Jing
收藏  |  浏览/下载：66/0  |  提交时间：2021/11/29
Structural analysis  engineering calculation  bottom correction coils  seismic load  
Test System Upgrade for ITER Current Lead Series Production at ASIPP 期刊论文
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2019, 卷号: 47, 期号: 1, 页码: 795-798
作者:  Ding, Kaizhong;  Liu, C.;  Du, Q.;  Dong, Y.;  Wang, J.;  Lu, K.;  Song, Y.;  Niu, E.;  Bauer, P.
浏览  |  Adobe PDF(1273Kb)  |  收藏  |  浏览/下载：71/39  |  提交时间：2020/03/31
Control system  cryogenics  current lead  high-temperature superconductors  test facilities  
Development of welding and processing technologies of helium inlet for ITER Correction Coil 期刊论文
FUSION ENGINEERING AND DESIGN, 2018, 卷号: 137, 期号: 无, 页码: 268-273
作者:  Xin, Jijun;  Fang, Chao;  Wei, Jing;  Wang, Lin;  Du, Shuangsong;  Huang, Chuanjun;  Song, Yuntao;  Li, Laifeng
浏览  |  Adobe PDF(5856Kb)  |  收藏  |  浏览/下载：79/34  |  提交时间：2020/03/31
ITER correction coil  Helium inlet  Metallography  X-ray examination  Fatigue test  Leak test  
Qualification of ITER Correction Coil Superconducting Joint 期刊论文
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 9, 页码: 3223-3228
作者:  Wang, Lin;  Wu, Weiyue;  Wei, Jing;  Ilyin, Yuri;  Dolgetta, Nello;  Simon, Fabrice;  Libeyre, Paul;  Santillana, Ignacio Aviles;  Langeslag, Stefanie;  Sgobba, Stefano;  Bernard, Turck
收藏  |  浏览/下载：37/0  |  提交时间：2019/12/11
Correction coil (CC)  ITER  lap joint  manufacturing procedures  qualification  
Magnetic polarization measurements of the multi-modal plasma response to 3D fields in the EAST tokamak 期刊论文
NUCLEAR FUSION, 2018, 卷号: 58, 期号: 7, 页码: 12
作者:  Logan, N. C.;  Cui, L.;  Wang, H.;  Sun, Y.;  Gu, S.;  Li, G.;  Nazikian, R.;  Paz-Soldan, C.
浏览  |  Adobe PDF(2899Kb)  |  收藏  |  浏览/下载：142/95  |  提交时间：2019/08/23
tokamak  resonant magnetic perturbations  edge localized modes  GPEC  reluctance  
Structural Stress Analysis of the CFETR Central Solenoid Model Coil 期刊论文
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 5, 页码: 1512-1516
作者:  Xu, Aihua;  Wu, Yu;  Yin, Dapeng;  Jin, Jing;  Qin, Jingang
浏览  |  Adobe PDF(1958Kb)  |  收藏  |  浏览/下载：68/33  |  提交时间：2019/08/23
China Fusion Engineering Test Reactor (CFETR) central solenoid (CS) model coil (CSMC)  stress analysis  superconductor  
ITER PF6 Dummy Double Pancake Winding 期刊论文
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 5, 页码: 1503-1506
作者:  Wen, Wei;  Du, Shuangsong;  Readman, Peter;  Wu, Weiyue;  Shen, Guang;  Chen, Jin
浏览  |  Adobe PDF(1625Kb)  |  收藏  |  浏览/下载：70/33  |  提交时间：2019/06/03
Dummy double pancake  ITER PF6  magnets  winding  
Test Results About Simple CDA plus MIK Quench Detection Method on EAST for ITER Superconducting CS Coils 期刊论文
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 5, 页码: 1484-1488
作者:  Hu, Yanlan;  Xiao, Yezheng;  Xiao, B. J.;  Shen, Biao;  Wang, Teng
浏览  |  Adobe PDF(1297Kb)  |  收藏  |  浏览/下载：85/44  |  提交时间：2019/06/10
Central difference average (CDA) plus MIK  ITER device  plasma scenarios  quench detection  
Geometry and Physics Design of Lower Divertor Upgrade in EAST 期刊论文
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 5, 页码: 1412-1416
作者:  Xu, Houchang;  Yao, Damao;  Zhou, Zibo;  Cao, Lei;  Li, Lei;  Han, Le;  Xu, Guosheng;  Wang, Liang;  Si, Hang;  Chen, Yiping;  Liu, Xiaoju;  Yang, Zhongshi;  Sang, Chaofeng;  Du, Hailong
浏览  |  Adobe PDF(2968Kb)  |  收藏  |  浏览/下载：69/36  |  提交时间：2019/06/03
Detachment  divertor  experimental advanced superconducting tokamak (EAST)  geometry and physics  tungsten