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Plasma models for real-time control of advanced tokamak scenarios

机译：等离子模型可实时控制高级托卡马克方案

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摘要

An integrated plasma profile control strategy, ARTAEMIS, is being developed for extrapolating present-day advanced tokamak (AT) scenarios to steady-state operation. The approach is based on semi-empirical modelling and was initially explored on JET (Moreau et al 2008 Nucl. Fusion 48 106001). This paper deals with the general applicability of this strategy for simultaneous magnetic and kinetic control on various tokamaks. The determination of the device-specific, control-oriented models that are needed to compute optimal controller matrices for a given operation scenario is discussed. The methodology is generic and can be applied to any device, with different sets of heating and current drive actuators, controlled variables and profiles. The system identification algorithms take advantage of the large ratio between the magnetic and thermal diffusion time scales and have been recently applied to both JT-60U and DIII-D data. On JT-60U, an existing series of high bootstrap current (～70%), 0.9 MA non-inductive AT discharges was used. The actuators consisted of four groups of neutral beam injectors aimed at perpendicular injection (on-axis and off-axis), and co-current tangential injection (also on-axis and off-axis). On DIII-D, dedicated system identification experiments were carried out in the loop voltage (V_(ext)) control mode (as opposed to current control) to avoid feedback in the response data from the primary circuit. The reference plasma state was that of a 0.9 MA AT scenario which had been optimized to combine non-inductive current fractions near unity with 3.5 <βn < 3.9, bootstrap current fractions larger than 65% and H_(98(y,2)) = 1.5. Actuators other than V_(ext) were co-current, counter-current and balanced neutral beam injection, and electron cyclotron current drive. Power and loop voltage modulations resulted in dynamic variations of the plasma current between 0.7 and 1.2 MA. It is concluded that the response of essential plasma parameter profiles to specific actuators of a given device can be satisfactorily identified from a small set of experiments. This provides, for control purposes, a readily available alternative to first-principles plasma modelling.
机译：正在开发一种集成的等离子体轮廓控制策略ARTAEMIS，以将当今的先进托卡马克（AT）情景推算到稳态操作。该方法基于半经验建模，最初在JET上进行了探索（Moreau等人，2008 Nucl。Fusion 48 106001）。本文讨论了该策略在各种托卡马克上同时进行磁和动力学控制的一般适用性。讨论了确定针对给定操作方案计算最佳控制器矩阵所需的特定于设备的，面向控制的模型。该方法是通用的，可以应用于具有不同组的加热和电流驱动执行器，受控变量和曲线的任何设备。系统识别算法利用了磁和热扩散时标之间的较大比率，并且最近已应用于JT-60U和DIII-D数据。在JT-60U上，使用了现有的一系列高自举电流（〜70％），0.9 MA非感应AT放电。执行器由四组中性束注入器组成，分别用于垂直注入（同轴和离轴）和顺流切向注入（同轴和离轴）。在DIII-D上，以环路电压（V_（ext））控制模式（与电流控制相反）进行了专用的系统识别实验，以避免来自主电路的响应数据反馈。参考等离子体状态是0.9 MA AT方案的状态，该方案已进行优化，以将非统一电流分量合并为统一的3.5 <βn<3.9，自举电流分量大于65％且H_（98（y，2））= 1.5。 V_（ext）以外的执行器是并流，逆流和平衡中性束注入，以及电子回旋加速器电流驱动。功率和环路电压调制导致等离子电流在0.7和1.2 MA之间动态变化。结论是，可以从一小组实验中令人满意地确定基本血浆参数曲线对给定设备的特定致动器的响应。出于控制目的，这为第一原理等离子体建模提供了一种容易获得的替代方法。

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  • 来源
    《Nuclear fusion》 |2011年第6期|p.11.1-11.14|共14页
  • 作者

    D. Moreau; D. Mazon; M.L. Walker; J.R. Ferron; K.H. Burrell; S.M. Flanagan; P. Gohil; R.J. Groebner; A.W. Hyatt; R J. La Haye; J. Lohr; F. Turco; E. Schuster; Y. Ou; C. Xu; Y. Takase; Y. Sakamoto; S. We; T. Suzuki;

  • 作者单位

    CEA, IRFM, 13108 Saint-Paul-lez-Durance, France;

    CEA, IRFM, 13108 Saint-Paul-lez-Durance, France;

    General Atomics, San Diego, CA 92186, USA;

    General Atomics, San Diego, CA 92186, USA;

    General Atomics, San Diego, CA 92186, USA;

    General Atomics, San Diego, CA 92186, USA;

    General Atomics, San Diego, CA 92186, USA;

    General Atomics, San Diego, CA 92186, USA;

    General Atomics, San Diego, CA 92186, USA;

    General Atomics, San Diego, CA 92186, USA;

    General Atomics, San Diego, CA 92186, USA;

    General Atomics, San Diego, CA 92186, USA;

    Department of Mechanical Engineering and Mechanics, Lehigh University, Bethlehem, PA 18015, USA;

    Department of Mechanical Engineering and Mechanics, Lehigh University, Bethlehem, PA 18015, USA;

    Department of Mechanical Engineering and Mechanics, Lehigh University, Bethlehem, PA 18015, USA;

    Graduate School of Frontier Sciences, The University of Tokyo, 277-8561, Kashiwa, Japan;

    Japan Atomic Energy Agency, Naka, Ibaraki 311-0193, Japan;

    Japan Atomic Energy Agency, Naka, Ibaraki 311-0193, Japan;

    Japan Atomic Energy Agency, Naka, Ibaraki 311-0193, Japan;

  • 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);
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