Reliability Considerations for the ITER Poloidal Field Coils

被引:12
|
作者
Simon, Fabrice [1 ]
Ilyin, Yuri [1 ]
Lim, Byung Su [1 ]
Cau, Francesca [2 ]
Herzog, Robert [2 ]
Stepanov, Boris [2 ]
机构
[1] ITER Org, F-13067 St Paul Les Durance, France
[2] PSI, EPFL CRPP, Fus Technol, CH-5232 Villigen, Switzerland
关键词
High voltage; insulation; ITER; maintenance; poloidal field coils; MAGNET SYSTEM;
D O I
10.1109/TASC.2010.2040262
中图分类号
TM [电工技术]; TN [电子技术、通信技术];
学科分类号
0808 ; 0809 ;
摘要
Since it is practically impossible to remove the Poloidal Field (PF) coils from the assembled ITER (International Thermonuclear Experimental Reactor) tokamak without major interruption in operation, the design of these coils shall provide their high reliability under high voltage operation. The design of the coil insulation relies on a separation of functions: mechanical function of the load transmission, performed by glass-fiber impregnated with epoxy resin on one side, and the independent electrical barrier made of polyimide tapes on the other side. Numerical simulation has shown that the maximum electrical field in the coil is lower than 4 kV/mm, which is taken as the design criterion for the PF insulator system. In case of a single insulation failure in a coil, its functionality can be recovered by installing a so-called jumper to by-pass the faulty double pancake. The design of the jumpers and their installation procedure are described.
引用
收藏
页码:423 / 426
页数:4
相关论文
共 50 条
  • [41] Optimization of Damavand Tokamak Poloidal Field Coils Positions and Currents with PSO Algorithm
    M. Mohammadi
    F. Dini
    R. Amrollahi
    Journal of Fusion Energy, 2012, 31 : 170 - 174
  • [42] Analysis of Internal and External Bypass Circuit Design for ITER Poloidal Field Converter System
    Yuan, Hongwen
    Song, Zhiquan
    Fu, Peng
    Wang, Peng
    Gao, Ge
    Huang, Liansheng
    Dong, Lin
    Wang, Min
    Fang, Tongzhen
    JOURNAL OF FUSION ENERGY, 2014, 33 (05) : 577 - 581
  • [43] Analysis of Internal and External Bypass Circuit Design for ITER Poloidal Field Converter System
    Hongwen Yuan
    Zhiquan Song
    Peng Fu
    Peng Wang
    Ge Gao
    Liansheng Huang
    Lin Dong
    Min Wang
    Tongzhen Fang
    Journal of Fusion Energy, 2014, 33 : 577 - 581
  • [44] Distortion of magnetic field lines caused by radial displacements of ITER toroidal field coils
    Amoskov, V. M.
    Gribov, Y. V.
    Lamzin, E. A.
    Sytchevsky, S. E.
    FUSION ENGINEERING AND DESIGN, 2017, 118 : 64 - 72
  • [45] Thermal Design of High-Power DC Reactor for ITER Poloidal Field Converter
    Chuan Li
    Zhiquan Song
    P. Fu
    Ming Zhang
    Xiuqing Zhang
    Kexun Yu
    Journal of Fusion Energy, 2014, 33 : 588 - 593
  • [46] Thermal Design of High-Power DC Reactor for ITER Poloidal Field Converter
    Li, Chuan
    Song, Zhiquan
    Fu, P.
    Zhang, Ming
    Zhang, Xiuqing
    Yu, Kexun
    JOURNAL OF FUSION ENERGY, 2014, 33 (05) : 588 - 593
  • [47] Prototype Coil Evaluation for NSTX-U Replacement Inner Poloidal Field Coils
    Zhai, Y.
    Neumeyer, C.
    Dellas, J.
    Greenough, N.
    Kalish, M.
    Petrella, J.
    Que, W.
    Raftopoulos, S.
    FUSION SCIENCE AND TECHNOLOGY, 2019, 75 (08) : 775 - 785
  • [48] Development of the ITER PF Coils
    Lim, B. S.
    Simon, F.
    Ilin, Y.
    Gung, C. Y.
    Boyer, C.
    Beemsterboer, C.
    Valente, P.
    Lelekhov, S.
    Mitchell, N.
    IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2012, 22 (03)
  • [49] Design of the ITER PF Coils
    Lim, B.
    Simon, F.
    Ilyin, Y.
    Gung, C. Y.
    Smith, J.
    Hsu, Y. H.
    Luongo, C.
    Jong, C.
    Mitchell, N.
    IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2011, 21 (03) : 1918 - 1921
  • [50] Contact resistance, coupling and hysteresis loss measurements of ITER poloidal field joint in parallel applied magnetic field
    Huang, J.
    Ilyin, Y.
    Wessel, W. A. J.
    Lubkemann, R.
    Krooshoop, H. J. G.
    Nijhuis, A.
    SUPERCONDUCTOR SCIENCE & TECHNOLOGY, 2022, 35 (02):