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ZHENG Jinxing(郑金星), SONG Yuntao(宋云涛), YANG Qingxi(杨庆喜), LIU Wandong(刘万东), DING Weixing(丁卫星), LIU Xufeng(刘旭峰), YANG Lei(杨雷). Design of a Wedge-Shaped Toroidal Field Winding for KTX Device[J]. Plasma Science and Technology, 2014, 16(9): 878-883. DOI: 10.1088/1009-0630/16/9/13
Citation: ZHENG Jinxing(郑金星), SONG Yuntao(宋云涛), YANG Qingxi(杨庆喜), LIU Wandong(刘万东), DING Weixing(丁卫星), LIU Xufeng(刘旭峰), YANG Lei(杨雷). Design of a Wedge-Shaped Toroidal Field Winding for KTX Device[J]. Plasma Science and Technology, 2014, 16(9): 878-883. DOI: 10.1088/1009-0630/16/9/13

Design of a Wedge-Shaped Toroidal Field Winding for KTX Device

Funds: supported by the National ITER Special Support for R&D on Science and Technology for ITER, “Research on Reversed Field Pinch Magnetic Confinement Configuration”, CN Schedule Task (No. 2011GB106000)
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  • Received Date: February 26, 2013
  • The KTX device is a reversed field pinch (RFP) device currently under construction. Its maximum plasma current is designed as 1 MA with a discharge time longer than 100 ms. Its major radius is 1.4 m and its minor radius is 0.55 m. One of the most important problems in the magnet system design is how to reduce the TF magnetic field ripple and error field. A new wedge- shaped TF coil is put forward for the KTX device and its electromagnetic properties are compared with those of rectangular-shaped TF coils. The error field B n /B t of wedge-shaped TF coils with 6.4 degrees is about 6% as compared with 8% in the case of a rectangular-shaped TF coil. Besides, the wedge-shaped TF coils have a lower magnetic field ripple at the edge of the plasma region, which is smaller than 7.5% at R=1.83 m and 2% at R=1.07 m. This means that the tokamak operation mode may be feasible for this device when the plasma area becomes smaller, because the maximum ripple in the plasma area of the tokamak model is always required to be smaller than 0.4%. Detailed analysis of the results shows that the structure of the wedged-shape TF coil is reliable. It can serve as a reference for TF coil design of small aspect ratio RFPs or similar torus devices.
  • 1 Mao Wenzhe. 2011, 53rd Annual Meeting of the APS Division of Plasma Physics Volume 56, Number 16, November 14-18; Salt Lake City, Utah.
    2 Rostagni G. 1995, Fusion Engineering and Design, 25:301.
    3 Dexter R N, Kerst D W, Lovell T W. 1991, Fusion Technology, 19: 131.
    4 Bellina F, Guarnieri M, Stella A. 1988, IEEE Trans.Magnetics, 2: 1252.
    5 Hirano Y, Yagi Y, Shimada T. 1999, Bulletin of the Electrotechnical Laboratory, 5: 137.
    6 Najmabadi Farrokh, Conn Robert W, Krakowski Robert A. 1993, Fusion Engineering and Design, 23:69.
    7 Stella A, Guarnieri M, Bellina F. 1995, Fusion Engineering and Design, 25: 373.
    8 Taylor J B. 1974, Proc. of the 5th IAEA Int. Conf., Tokyo (Japan), 1: 164.
    9 Richard J Thome, John M Tarrh. 1982, Magnetohy-drodynamic and Fusion Magnets: Field and Force Design Concepts. New York, USA, 108-118.
    10 Weissenburger D W, Christensen U R, Bialek J. 1977, The Pure Tension Shape of a Thick Torus. Princeton Plasma Physics Laboratory, Princeton.

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