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Electron cyclotron power management for control of neoclassical tearing modes in the ITER baseline scenario

机译:在ITER基准情景中控制新古典撕裂模式的电子回旋加速器功率管理

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摘要

Time-dependent simulations are used to evolve plasma discharges in combination with a modified Rutherford equation for calculation of neoclassical tearing mode (NTM) stability in response to electron cyclotron (EC) feedback control in ITER. The main application of this integrated approach is to support the development of control algorithms by analyzing the plasma response with physics-based models and to assess how uncertainties in the detection of the magnetic island and in the EC alignment affect the ability of the ITER EC system to fulfill its purpose. Simulations indicate that it is critical to detect the island as soon as possible, before its size exceeds the EC deposition width, and that maintaining alignment with the rational surface within half of the EC deposition width is needed for stabilization and suppression of the modes, especially in the case of modes with helicity (2,1). A broadening of the deposition profile, for example due to wave scattering by turbulence fluctuations or not well aligned beams, could even be favorable in the case of the (2,1)-NTM, by relaxing an over-focussing of the EC beam and improving the stabilization at the mode onset. Pre-emptive control reduces the power needed for suppression and stabilization in the ITER baseline discharge to a maximum of 5 MW, which should be reserved and available to the upper launcher during the entire flattop phase. Assuming continuous triggering of NTMs, with preemptive control ITER would be still able to demonstrate a fusion gain of Q = 10.
机译:随时间变化的模拟被用于与改良的Rutherford方程相结合来产生等离子体放电,以响应ITER中的电子回旋加速器(EC)反馈控制来计算新古典撕裂模式(NTM)的稳定性。这种集成方法的主要应用是通过基于物理模型分析等离子体响应来支持控制算法的开发,并评估磁岛检测和EC对准中的不确定性如何影响ITER EC系统的能力达到目的仿真表明,在岛的大小超过EC沉积宽度之前,尽快检测岛是至关重要的,并且为了使模式稳定和抑制,需要在EC沉积宽度的一半范围内与合理表面保持对准。对于具有螺旋度(2,1)的模式。在(2,1)-NTM的情况下,通过放宽EC光束和提高模式开始时的稳定性。先发制人的控制将抑制和稳定ITER基线放电所需的功率降低到最大5 MW,应保留该功率,并在整个平顶阶段将其提供给上部发射器。假设连续触发NTM,在先发制人控制下,ITER仍然能够证明Q = 10的融合增益。

著录项

  • 来源
    《Nuclear fusion》 |2018年第1期|016007.1-016007.15|共15页
  • 作者单位

    Princeton Plasma Physics Laboratory, Princeton, NJ 08543, United States of America;

    Princeton Plasma Physics Laboratory, Princeton, NJ 08543, United States of America;

    ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St. Paul lez Durance Cedex, France;

    ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St. Paul lez Durance Cedex, France;

    Princeton Plasma Physics Laboratory, Princeton, NJ 08543, United States of America;

    Max-Planck-Institute for Plasma Physics, 85748 Garching, Germany;

    Istituto di Fisica del Plasma, Consiglio Nazionale delle Ricerche (IFP CNR), Milano, Italy;

    Istituto di Fisica del Plasma, Consiglio Nazionale delle Ricerche (IFP CNR), Milano, Italy;

  • 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

    NTM; electron cyclotron; ITER; control;

    机译:NTM;电子回旋加速器ITER;控制;

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