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Pedestal stability comparison and ITER pedestal prediction

机译:基座稳定性比较和ITER基座预测

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摘要

The pressure at the top of the edge transport barrier (or 'pedestal height') strongly impacts fusion performance, while large edge localized modes (ELMs), driven by the free energy in the pedestal region, can constrain material lifetimes. Accurately predicting the pedestal height and ELM behavior in ITER is an essential element of prediction and optimization of fusion performance. Investigation of intermediate wavelength MHD modes (or 'peeling-ballooning' modes) has led to an improved understanding of important constraints on the pedestal height and the mechanism for ELMs. The combination of high-resolution pedestal diagnostics, including substantial recent improvements, and a suite of highly efficient stability codes, has made edge stability analysis routine on several major tokamaks, contributing both to understanding, and to experimental planning and performance optimization. Here we present extensive comparisons of observations to predicted edge stability boundaries on several tokamaks, both for the standard (Type I) ELM regime, and for small ELM and ELM-free regimes. We further discuss a new predictive model for the pedestal height and width (EPED1), developed by self-consistently combining a simple width model with peeling-ballooning stability calculations. This model is tested against experimental measurements, and used in initial predictions of the pedestal height for ITER.
机译:边缘传输屏障顶部的压力(或“基座高度”)强烈影响融合性能,而在基座区域中的自由能驱动的大边缘局部模式(ELM)可能会限制材料寿命。准确预测ITER中的基座高度和ELM行为是预测和优化融合性能的基本要素。对中等波长MHD模式(或“剥离-气球”模式)的研究已导致对基座高度和ELM机理的重要约束有了更好的理解。高分辨率基座诊断程序(包括近期的重大改进)和一整套高效的稳定性代码的结合,使在几个主要托卡马克上的边缘稳定性分析成为例行程序,有助于理解,实验计划和性能优化。在这里,我们针对标准(I型)ELM方案以及小型ELM和无ELM方案,对几种托卡马克的预测边缘稳定性边界进行了广泛的观察比较。我们进一步讨论了一种新的基座高度和宽度预测模型(EPED1),该模型通过将简单的宽度模型与剥离-气球稳定性计算自洽地结合在一起而开发。该模型针对实验测量值进行了测试,并用于ITER基座高度的初始预测。

著录项

  • 来源
    《Nuclear fusion》 |2009年第8期|343-350|共8页
  • 作者单位

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

    Fusion Research and Development Directorate, JAEA, Naka, Ibaraki, Japan;

    EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon, UK;

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

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

    MIT Plasma Science and Fusion Center, Cambridge, MA, USA;

    MIT Plasma Science and Fusion Center, Cambridge, MA, USA;

    Association Euratom/CEA, Cadarache, St Paul-lez-Durance, France;

    Fusion Research and Development Directorate, JAEA, Naka, Ibaraki, Japan;

    EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon, UK;

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

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

    EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon, UK;

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

    Oak Ridge National Laboratory, Oak Ridge, TN, USA;

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

    Fusion Research and Development Directorate, JAEA, Naka, Ibaraki, Japan;

    Department of Physics, Lehigh University, Bethlehem, PA, USA;

    EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon, UK;

    EFDA Close Support Unit-Garching, Garching, Germany;

    MIT Plasma Science and Fusion Center, Cambridge, MA, USA;

    Fusion Research and Development Directorate, JAEA, Naka, Ibaraki, Japan;

    Department of Physics, University of York, York, UK;

  • 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; magnetohydrodynamic and fluid equation; gyrofluid and gyrokinetic simulations; theory; design; and computerized simulation;

    机译:托卡马克球形托卡马克理想和电阻MHD模式;动力学模式磁流体动力学和流体方程;旋流和动力学模拟;理论;设计;和计算机模拟;

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