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DIAGNOSIS OF ST PLASMAS IN NSTX Challenges and Opportunities

机译:NSTX挑战和机遇中的ST等离子体的诊断

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During the past decade, considerable experimental and theoretical progress has been made in the development of the Spherical Torus (ST) configuration. A second generation of 'proof of principal' devices, including GLOBUS-M, MAST and NSTX, are now operating with plasma currents in the 1 -2 MA range. The ST has already been the basis of a reactor study, and the concept has also been considered in the context of a volume neutron source. As the aspect ratio of a conventional circular tokamak is reduced towards one, the cross-section naturally assumes a shape with high elongation and triangularity, with only modest requirements for shaping fields. This configuration can sustain high plasma current with high values of edge q, meaning that the toroidal field can be much lower than that in a conventional tokamak. Compared to a standard tokamak, the magnetic field pitch can be very large (pitch angles > 50° at outer midplane). High values of toroidal beta can reached, and the combination of high β, high κ, and high q(a) leads to the potential for a large bootstrap current sustainment. The National Spherical Torus Experiment (NSTX) is a low-aspect-ratio torus (R/a≤1.3) designed to produce and study high β_T (25-40%) plasmas that are non-inductively sustained with high bootstrap fraction (≤70%). Heating and current drive is done with a 3-source neutral beam (5 MW) and a 12 strap, high-harmonic-fast-wave (HHFW) antenna (6 MW). In addition, coaxial-helicity-injection (CHI) is used for non-inductive plasma current initiation. Basic device capabilities are R=0.85 m, a=0.68 m, I_P≤1.4 MA, B_T≤0.45 T with elongation ≤ 2.0 and triangularity ≤ 0.5. Central plasma parameters in the range of n_e=4-5x10~(19) m~(-3) and T_e,T_i=3-4 keV are obtained for high power heating experiments, which began in late 2000. This paper will highlight some of the challenges and opportunities present in the diagnosis of ST plasmas on NSTX, and discuss the corresponding diagnostic development that is currently underway. After a brief description of diagnostic systems currently installed, examples of ST-specific diagnostic challenges will be highlighted, as will another case, where the ST configuration offers opportunities for new measurements.
机译:在过去十年中,在球形圆环(ST)配置的发展中,已经进行了相当大的实验和理论进展。第二代“主体”设备(包括Globus-M,MAST和NSTX)的验证,现在在1 -2 mA系列中使用等离子电流运行。 ST已经是反应堆研究的基础,并且在卷中子源的上下文中也被认为是该概念。随着传统圆形Tokamak的纵横比减小朝向一个,横截面自然地具有高伸长率和三角形的形状,仅具有适度的整形领域的要求。该配置可以维持具有高值Q值的高等离子体电流,这意味着环形场可以远低于传统Tokamak中的环形场。与标准Tokamak相比,磁场间距可以非常大(外层板处的俯仰角> 50°)。可以达到环形β的高值,以及高β,高κ和高Q(a)的组合导致大型举动力的潜力。国家球环实验(NSTX)是低纵横比的环面(R /a≤1.3)设计成产生和研究高β_T(25-40%),其为无感具有高的自举分数持续等离子体(≤70 %)。采用3源中性光束(5mW)和12带,高谐波 - 快波(HHFW)天线(6 MW)完成加热和电流驱动器。另外,同轴螺旋 - 注射(CHI)用于非感应等离子体电流引发。基本装置能力是r = 0.85 m,a = 0.68 m,i_p≤1.4ma,b_t≤0.45t,伸长率≤2.0,三角形≤0.5。在n_e = 4-5x10〜(19)米〜(-3)和T_e的范围中心等离子体参数,T_i = 3-4千电子伏的高功率加热实验,其开始于2000年后期获得本文将突出一些NSTX上ST等离子体诊断中存在的挑战和机遇,讨论目前正在进行的相应诊断发展。在目前安装了诊断系统的简要说明后,将突出显示ST特定的诊断挑战的示例,而另一种情况,ST配置为新测量提供了机会。

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