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Experimental vertical stability studies for ITER performance and design guidance

机译:针对ITER性能的实验性垂直稳定性研究和设计指导

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摘要

Operating experimental devices have provided key inputs to the design process for ITER axisymmetric control. In particular, experiments have quantified controllability and robustness requirements in the presence of realistic noise and disturbance environments, which are difficult or impossible to characterize with modelling and simulation alone. This kind of information is particularly critical for ITER vertical control, which poses the highest demands on poloidal field system performance, since the consequences of loss of vertical control can be severe. This work describes results of multi-machine studies performed under a joint ITPA experiment (MDC-13) on fundamental vertical control performance and controllability limits. We present experimental results from Alcator C-Mod, DIII-D, NSTX, TCV and JET, along with analysis of these data to provide vertical control performance guidance to ITER. Useful metrics to quantify this control performance include the stability margin and maximum controllable vertical displacement. Theoretical analysis of the maximum controllable vertical displacement suggests effective approaches to improving performance in terms of this metric, with implications for ITER design modifications. Typical levels of noise in the vertical position measurement and several common disturbances which can challenge the vertical control loop are assessed and analysed.
机译:运行中的实验装置为ITER轴对称控制的设计过程提供了关键的输入。特别是,在现实的噪声和干扰环境下,实验对量化的可控性和鲁棒性要求进行了量化,而仅通过建模和仿真就很难或不可能对它们进行表征。这种信息对于ITER垂直控制尤为重要,因为对ITER垂直控制的损失可能会很严重,因此对极场系统的性能提出了最高要求。这项工作描述了在基本IT控制性能和可控性极限的联合ITPA实验(MDC-13)下进行的多机研究结果。我们介绍了Alcator C-Mod,DIII-D,NSTX,TCV和JET的实验结果,以及对这些数据的分析,以为ITER提供垂直控制性能指导。量化此控制性能的有用指标包括稳定性裕度和最大可控垂直位移。对最大可控垂直位移的理论分析提出了一种有效的方法来提高此指标的性能,这对ITER设计进行了修改。评估并分析了垂直位置测量中的典型噪声水平以及可能挑战垂直控制回路的几种常见干扰。

著录项

  • 来源
    《Nuclear fusion》 |2009年第11期|32-41|共10页
  • 作者单位

    General Atomics, PO Box 85608, San Diego, CA 92186-5608, USA;

    Lawrence Livermore National Laboratory, Livermore, CA 94550, USA;

    General Atomics, PO Box 85608, San Diego, CA 92186-5608, USA;

    Massachusetts Institute of Technology, Cambridge, MA 02139, USA;

    Princeton Plasma Physics Laboratory, Princeton. NJ, USA;

    Massachusetts Institute of Technology, Cambridge, MA 02139, USA;

    General Atomics, PO Box 85608, San Diego, CA 92186-5608, USA;

    Princeton Plasma Physics Laboratory, Princeton. NJ, USA;

    General Atomics, PO Box 85608, San Diego, CA 92186-5608, USA;

    EPFL CRPP-Lausanne, Lausanne, Switzerland;

    Lawrence Livermore National Laboratory, Livermore, CA 94550, USA;

    Lawrence Livermore National Laboratory, Livermore, CA 94550, USA;

    Lawrence Livermore National Laboratory, Livermore, CA 94550, USA;

    Fusion for Energy, Barcelona, Spain;

    Euratom/UKAEA Fusion Association, Culham Science Centre, Abingdon. UK;

    General Atomics, PO Box 85608, San Diego, CA 92186-5608, USA;

    General Atomics, PO Box 85608, San Diego, CA 92186-5608, USA;

    Massachusetts Institute of Technology, 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

    tokamaks, spherical tokamaks; ideal and resistive MHD modes; kinetic modes; control theory; nuclear fusion power;

    机译:托卡马克;球形托卡马克;理想和电阻MHD模式;动力学模式控制理论核聚变动力;

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