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Burning plasma projections using drift-wave transport models and scalings for the H-mode pedestal

机译:使用漂移波传输模型和H模式基座的缩放比例燃烧等离子体投影

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摘要

The GLF23 and multi-mode core transport models are used along with models for the H-mode pedestal to predict the fusion performance for the International Thermonuclear Experimental Reactor, Fusion Ignition Research Experiment, and IGNITOR tokamak designs. Simulations using combinations of core and pedestal models have also been compared with experimental data for H-mode profiles in DIII-D, JET, and Alcator C-Mod. Power-independent (ballooning mode limit) and power-dependent pedestal scalings lead to very different predictions when used with the core models. Although the two drift-wave transport models reproduce the core profiles in a wide variety of tokamak discharges, they differ in their projections to burning plasma experiments for the same pedestal parameters. Differences in the core transport models in their response to the ion temperature gradient (i.e. their stiffness) and impact of the power dependence of the H-mode pedestal on fusion performance predictions are discussed.
机译:GLF23和多模式堆芯传输模型与H模式基座模型一起使用,可以预测国际热核实验反应堆,聚变点火研究实验和IGNITOR托卡马克设计的融合性能。还已将使用核心和基座模型组合的模拟与DIII-D,JET和Alcator C-Mod中H模式配置文件的实验数据进行了比较。与核心模型一起使用时,与功率无关(气球模式极限)和与功率有关的基座缩放比例会导致非常不同的预测。尽管两个漂移波传输模型在各种托卡马克放电中都能再现核心剖面,但对于相同的基座参数,它们的投影与燃烧等离子体实验的投影有所不同。讨论了核心输运模型对离子温度梯度的响应(即其刚度)以及氢模式基座功率依赖性对融合性能预测的影响方面的差异。

著录项

  • 来源
    《Nuclear fusion》 |2003年第12期|p. 1845-1854|共10页
  • 作者单位

    Lehigh University, Bethlehem, PN 18015, USA;

    Lehigh University, Bethlehem, PN 18015, USA;

    Lehigh University, Bethlehem, PN 18015, USA;

    Lehigh University, Bethlehem, PN 18015, USA;

    Lehigh University, Bethlehem, PN 18015, USA;

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

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

  • 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 原子核物理学、高能物理学;
  • 关键词

  • 入库时间 2022-08-18 00:50:21

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