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Reflectometry-based plasma position feedback control demonstration at ASDEX Upgrade

机译:在ASDEX升级中基于反射法的等离子体位置反馈控制演示

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摘要

In fusion experiments, real-time feedback control of the plasma position plays a vital role for machine protection and disruption avoidance. This control task is presently performed using magnetic measurements that, in future long pulse tokamak devices of the ITER class, may be affected by drifting integrators or radiation induced voltages in the magnetic pickup coils. These effects could have an impact on the magnetic equilibrium reconstruction, causing potential losses of position control and, consequently, leading to premature discharge termination or plasma-facing component damage. Frequency modulated continuous wave 0-mode reflectometry, a non-magnetic dependent technique used to measure the density profile, was proposed to backup or complement the standard magnetic-based control in such devices. This new control scheme has just been successfully demonstrated for the first time on the ASDEX Upgrade (AUG) tokamak. The location of the plasma boundary, used in the control of the plasma column position, was tracked in real-time (RT) using dedicated algorithms and a new approach that combines the reflectometry edge profile and a scaled line integrated density measurement from interferometry. Although feasibility studies on the viability of this method had been previously conducted at AUG, the capabilities required to produce this on-line demonstration were only incorporated in the diagnostic after a recent upgrade of its data acquisition and processing hardware. The results herein presented show the first successful demonstration of the reflectometry plasma position application as proposed for ITER.
机译:在融合实验中,等离子体位置的实时反馈控制对于机器保护和避免干扰至关重要。当前使用磁测量来执行该控制任务,在将来的ITER类的长脉冲托卡马克装置中,磁拾取线圈中的漂移积分器或辐射感应电压可能会影响该测量任务。这些影响可能会对磁平衡的重建产生影响,从而导致位置控制的潜在损失,并因此导致过早放电终止或等离子体组件的损坏。提出了调频连续波0模式反射法,一种用于测量密度分布的非磁性相关技术,用于备份或补充此类设备中基于磁性的标准控制。这种新的控制方案刚刚在ASDEX升级(AUG)托卡马克上首次成功演示。使用专用算法和一种新方法实时跟踪(RT)跟踪用于控制等离子柱位置的等离子边界位置,该新方法结合了反射法边缘轮廓和干涉法中的缩放线积分密度测量。尽管以前在AUG进行过关于此方法可行性的可行性研究,但只有在最近对其数据采集和处理硬件进行升级之后,才能将产生此在线演示所需的功能纳入诊断。本文介绍的结果显示了针对ITER提出的反射法等离子体位置应用的首次成功演示。

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  • 来源
    《Nuclear fusion》 |2012年第3期|p.032003.1-032003.6|共6页
  • 作者单位

    Associacao EURATOM/IST, Instituto de Plasmas e Fusao Nuclear - Laboratorio Associado,Instituto Superior Tecnico, Universidade Tecnica de Lisboa, 1049-001, Lisboa, Portugal;

    Associacao EURATOM/IST, Instituto de Plasmas e Fusao Nuclear - Laboratorio Associado,Instituto Superior Tecnico, Universidade Tecnica de Lisboa, 1049-001, Lisboa, Portugal;

    Max-Planck Institut fuer Plasmaphysik, EURATOM Association, D-85748 Garching,Germany;

    Max-Planck Institut fuer Plasmaphysik, EURATOM Association, D-85748 Garching,Germany;

    Associacao EURATOM/IST, Instituto de Plasmas e Fusao Nuclear - Laboratorio Associado,Instituto Superior Tecnico, Universidade Tecnica de Lisboa, 1049-001, Lisboa, Portugal;

  • 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

  • 入库时间 2022-08-18 00:43:58

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