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Multi-machine analysis of termination scenarios with comparison to simulations of controlled shutdown of ITER discharges

机译：与终止ITER排放的受控停机模拟进行比较的多机分析终止情景

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摘要

To improve our understanding of the dynamics and control of ITER terminations, a study has been carried out on data from existing tokamaks. The aim of this joint analysis is to compare the assumptions for ITER terminations with the present experience basis. The study examined the parameter ranges in which present day devices operated during their terminations, as well as the dynamics of these parameters. The analysis of a database, built using a selected set of experimental termination cases, showed that, the H-mode density decays slower than the plasma current ramp-down. The consequential increase in f_(GW) limits the duration of the H-mode phase or result in disruptions. The lower temperatures after the drop out of H-mode will allow the plasma internal inductance to increase. But vertical stability control remains manageable in ITER at high internal inductance when accompanied by a strong elongation reduction. This will result in ITER terminations remaining longer at low q (q_(95) ～ 3) than most present-day devices during the current ramp-down. A fast power ramp-down leads to a larger change in β_p at the H-L transition, but the experimental data showed that these are manageable for the ITER radial position control. The analysis of JET data shows that radiation and impurity levels significantly alter the H-L transition dynamics. Self-consistent calculations of the impurity content and resulting radiation should be taken into account when modelling ITER termination scenarios. The results from this analysis can be used to better prescribe the inputs for the detailed modelling and preparation of ITER termination scenarios.
机译：为了增进我们对ITER终端动态和控制的了解，已经对现有托卡马克的数据进行了研究。这项联合分析的目的是将ITER终止的假设与目前的经验基础进行比较。这项研究检查了当今设备在终止期间的工作参数范围，以及这些参数的动态性。使用一组选定的实验终止案例建立的数据库分析表明，H模式密度的衰减比等离子电流的下降要慢。 f_（GW）的相应增加会限制H模式阶段的持续时间或导致中断。 H模式退出后的较低温度将使等离子体内部电感增加。但是，当伴随着强烈的伸长率降低时，在高内部电感下，ITER中的垂直稳定性控制仍可控制。在当前的下降期间，这将导致ITER终端在低q（q_（95）〜3）处的停留时间比大多数当今设备更长。快速功率下降会导致在H-L过渡时β_p的较大变化，但实验数据表明，对于ITER径向位置控制而言，这些参数是可控的。对JET数据的分析表明，辐射和杂质水平显着改变了H-L跃迁动力学。在对ITER终端场景进行建模时，应考虑杂质含量和产生的辐射的自洽计算。分析的结果可用于更好地规定ITER终止方案的详细建模和准备工作的输入。

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  • 来源
    《Nuclear fusion》 |2018年第2期|026019.1-026019.13|共13页
  • 作者

    P.C. de Vries; T.C. Luce; Y.S. Bae; S. Gerhardt; X. Gong; Y. Gribov; D. Humphreys; A. Kavin; R.R. Khayrutdinov; C. Kessel; S.H. Kim; A. Loarte; V.E. Lukash; E. de la Luna; I. Nunes; F. Poli; J. Qian; M. Reinke; O. Sauter; A.C.C. Sips; J.A. Snipes; J. Stober; W. Treutterer; A.A. Teplukhina; I. Voitsekhovitch; M.H. Woo; S. Wolfe; L. Zabeo;

  • 作者单位

    ITER Organization, Route de Vinon sur Verdon, 13067 St Paul Lez Durance, France;

    General Atomics, PO Box 85608, San Diego, CA 92186-5608, United States of America;

    National Fusion Research Institute, Daejeon, Republic of Korea;

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

    Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, People's Republic of China;

    ITER Organization, Route de Vinon sur Verdon, 13067 St Paul Lez Durance, France;

    General Atomics, PO Box 85608, San Diego, CA 92186-5608, United States of America;

    D.V. Efremov Institute of Electrophysical Apparatus, Saint Petersburg, Russian Federation;

    National Research Center Kurchatov Institute, Moscow, Russian Federation;

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

    ITER Organization, Route de Vinon sur Verdon, 13067 St Paul Lez Durance, France;

    ITER Organization, Route de Vinon sur Verdon, 13067 St Paul Lez Durance, France;

    National Research Center Kurchatov Institute, Moscow, Russian Federation;

    EUROfusion Consortium, JET, Culham Science Centre, Abingdon, OX14 3DB, United Kingdom ,Laboratorio Nacional de Fusion, CIEMAT, 28040 Madrid, Spain;

    EUROfusion Consortium, JET, Culham Science Centre, Abingdon, OX14 3DB, United Kingdom ,Associacao EURATOM-IST, Institute de Plasmas e Fusao Nuclear, Lisboa, Portugal;

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

    Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, People's Republic of China;

    Oak Ridge National Laboratory, 1 Bethel Valley Rd., Oak Ridge, TN 37830, United States of America;

    General Atomics, PO Box 85608, San Diego, CA 92186-5608, United States of America;

    EUROfusion Consortium, JET, Culham Science Centre, Abingdon, OX14 3DB, United Kingdom ,European Commission, Brussels, Belgium;

    ITER Organization, Route de Vinon sur Verdon, 13067 St Paul Lez Durance, France;

    Max-Planck-Institut fuer Plasmaphysik, 85748 Garching, Germany;

    Max-Planck-Institut fuer Plasmaphysik, 85748 Garching, Germany;

    Ecole Polytechnique Federale de Lausanne, Swiss Plasma Center (SPC), CH-1015, Switzerland;

    CCFE, Culham Science Centre, OX14 3DB Abingdon, United Kingdom;

    National Fusion Research Institute, Daejeon, Republic of Korea;

    Plasma Science and Fusion Center, MIT, Cambridge, MA, United States of America;

    ITER Organization, Route de Vinon sur Verdon, 13067 St Paul Lez Durance, France;

  • 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

    plasma control; termination scenario; tokamak operation; ITER;

    机译：等离子控制终止方案;托卡马克行动国际热核实验堆;

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