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首页> 外文期刊>Nuclear fusion >Lower hybrid heating and current drive on the Alcator C-Mod tokamak
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Lower hybrid heating and current drive on the Alcator C-Mod tokamak

机译：降低Alcator C-Mod托卡马克上的混合动力加热和电流驱动

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摘要

On the Alcator C-Mod tokamak, lower hybrid current drive (LHCD) is being used to modify the current profile with the aim of obtaining advanced tokamak (AT) performance in plasmas with parameters similar to those that would be required on ITER. To date, power levels in excess of 1 MW at a frequency of 4.6 GHz have been coupled into a variety of plasmas. Experiments have established that LHCD on C-Mod behaves globally as predicted by theory. Bulk current drive efficiencies, n_(20)I_(1h)R/P_(1h) ～ 0.25, inferred from magnetics and MSE are in line with theory. Quantitative comparisons between local measurements, MSE, ECE and hard x-ray bremsstrahlung, and theory/simulation using the GENRAY, TORIC-LH CQL3D and TSC-LSC codes have been performed. These comparisons have demonstrated the off-axis localization of the current drive, its magnitude and location dependence on the launched n_‖ spectrum, and the use of LHCD during the current ramp to save volt-seconds and delay the peaking of the current profile. Broadening of the x-ray emission profile during ICRF heating indicates that the current drive location can be controlled by the electron temperature, as expected. In addition, an alteration in the plasma toroidal rotation profile during LHCD has been observed with a significant rotation in the counter-current direction. Notably, the rotation is accompanied by peaking of the density and temperature profiles on a current diffusion time scale inside of the half radius where the LH absorption is taking place.
机译：在Alcator C-Mod托卡马克上，较低的混合电流驱动器（LHCD）用于修改电流曲线，目的是获得等离子中先进的托卡马克（AT）性能，其参数与ITER所需的参数相似。迄今为止，在4.6 GHz频率上超过1 MW的功率已耦合到各种等离子体中。实验已经确定，C-Mod上的LHCD可以像理论所预测的那样具有全局性。从磁学和MSE推论得出的大电流驱动效率n_（20）I_（1h）R / P_（1h）〜0.25与理论相符。已经进行了局部测量，MSE，ECE和硬X射线致辐射之间的定量比较，以及使用GENRAY，TORIC-LH CQL3D和TSC-LSC代码进行的理论/模拟。这些比较证明了电流驱动器的离轴定位，其大小和位置对发射的n_''频谱的依赖性，以及在电流斜坡期间使用LHCD来节省伏特秒并延迟电流曲线的峰值。如预期的那样，在ICRF加热过程中X射线发射曲线的变宽表明，当前的驱动位置可以由电子温度控制。另外，已经观察到在LHCD期间血浆环形旋转轮廓的改变，并且在逆流方向上有明显的旋转。值得注意的是，旋转伴随着在发生LH吸收的半半径内的电流扩散时间尺度上密度和温度分布达到峰值。

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  • 来源
    《Nuclear fusion》 |2009年第11期|135-142|共8页
  • 作者

    J.R. Wilson; R. Parker; M. Bitter; P.T. Bonoli; C. Fiore; R.W. Harvey; K. Hill; A.E. Hubbard; J.W. Hughes; A. Ince-Cushman; C. Kessel; J.S. Ko; O. Meneghini; C.K. Phillips; M. Porkolab; J. Rice; A.E. Schmidt; S. Scott; S. Shiraiwa; E. Valeo; G. Wallace; J.C. Wright;

  • 作者单位

    Princeton Plasma Physics Laboratory, Princeton University, Princeton, NJ 08543, USA;

    Plasma Science and Fusion Center, MIT, Cambridge, MA 02139, USA;

    Princeton Plasma Physics Laboratory, Princeton University, Princeton, NJ 08543, USA;

    Plasma Science and Fusion Center, MIT, Cambridge, MA 02139, USA;

    Plasma Science and Fusion Center, MIT, Cambridge, MA 02139, USA;

    CompX, PO Box 2672, Del Mar, CA 92014-5672, USA;

    Princeton Plasma Physics Laboratory, Princeton University, Princeton, NJ 08543, USA;

    Plasma Science and Fusion Center, MIT, Cambridge, MA 02139, USA;

    Plasma Science and Fusion Center, MIT, Cambridge, MA 02139, USA;

    Plasma Science and Fusion Center, MIT, Cambridge, MA 02139, USA;

    Princeton Plasma Physics Laboratory, Princeton University, Princeton, NJ 08543, USA;

    Plasma Science and Fusion Center, MIT, Cambridge, MA 02139, USA;

    Plasma Science and Fusion Center, MIT, Cambridge, MA 02139, USA;

    Princeton Plasma Physics Laboratory, Princeton University, Princeton, NJ 08543, USA;

    Plasma Science and Fusion Center, MIT, Cambridge, MA 02139, USA;

    Plasma Science and Fusion Center, MIT, Cambridge, MA 02139, USA;

    Plasma Science and Fusion Center, MIT, Cambridge, MA 02139, USA;

    Princeton Plasma Physics Laboratory, Princeton University, Princeton, NJ 08543, USA;

    Plasma Science and Fusion Center, MIT, Cambridge, MA 02139, USA;

    Princeton Plasma Physics Laboratory, Princeton University, Princeton, NJ 08543, USA;

    Plasma Science and Fusion Center, MIT, Cambridge, MA 02139, USA;

    Plasma Science and Fusion Center, MIT, Cambridge, MA 02139, USA;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    plasma heating by microwaves; ECR, LH, collisional heating; current drive; helicity injection;

    机译：微波等离子体加热;ECR;LH;碰撞加热;当前驱动器;螺旋注射;

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