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Edge loss of high-harmonic fast-wave heating power in NSTX: a cylindrical model

机译:NSTX中高谐波快波加热功率的边缘损耗:圆柱模型

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摘要

Efficient high-harmonic fast-wave (HHFW) heating in the National Spherical Torus Experiment Upgrade (NSTX-U) would facilitate experiments in turbulence, transport, fast-ion studies, and more. However, previous HHFW operation in NSTX exhibited a large loss of fast-wave power to the divertor along the scrape-off layer field lines for edge densities above the fast-wave cutoff. It was postulated that the wave amplitude is enhanced in the scrape-off layer due to cavity-like modes, and that these enhanced fields drive sheath losses through RF rectification. As part of ongoing work to confirm this hypothesis, we have developed a cylindrical cold-plasma model to identify and understand scenarios where a substantial fraction of wave power is confined to the plasma periphery. We previously identified a peculiar class of modes, named annulus resonances, that conduct approximately half of their wave power in the periphery and can also account for a significant fraction of the total wave power. Here, we study the influence of annulus resonances on wave field reconstructions and find instances where annulus-resonant modes dominate the spectrum and trap over half of the total wave power at the edge. The work is part of an ongoing effort to determine the mechanism underlying these scrape-off layer losses in NSTX, identify optimal conditions for operation in NSTX-U, and predict whether similar losses occur for the ion-cyclotron minority heating scheme for both current experiments and future devices such as ITER.
机译:国家球形圆环实验升级版(NSTX-U)中高效的高谐波快速波(HHFW)加热将有助于进行湍流,运输,快速离子研究等方面的实验。但是,先前在NSTX中进行的HHFW操作对沿快波截止点上方的边缘密度沿刮除层场线向分流器显示了很大的快波功率损失。据推测,由于腔状模态,刮除层中的波幅增加,并且这些增强的场通过射频整流驱动鞘层损耗。作为证实这一假设的工作的一部分,我们已经开发出了圆柱形冷等离子体模型,以识别和理解将大部分波功率限制在等离子体外围的情况。先前我们确定了一种奇特的模式,称为环形共振,该模式在外围传导其波功率的大约一半,并且也可以占总波功率的很大一部分。在这里,我们研究了环形共振对波场重构的影响,并发现了环形共振模式主导频谱并在边缘捕获超过总波功率一半的情况。这项工作是正在进行的工作的一部分,该工作旨在确定NSTX中这些刮除层损失的机制,确定NSTX-U中运行的最佳条件,并预测在两个当前实验中离子回旋加速器少数加热方案是否会发生类似的损失以及未来的设备,例如ITER。

著录项

  • 来源
    《Nuclear fusion》 |2017年第11期|116062.1-116062.13|共13页
  • 作者单位

    Princeton Plasma Physics Laboratory, Princeton, NJ 08540, United States of America;

    Princeton Plasma Physics Laboratory, Princeton, NJ 08540, United States of America;

    Princeton Plasma Physics Laboratory, Princeton, NJ 08540, United States of America;

    Princeton Plasma Physics Laboratory, Princeton, NJ 08540, United States of America;

    Princeton Plasma Physics Laboratory, Princeton, NJ 08540, United States of America;

  • 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

    ICRF; heating; tokamaks; edge loss;

    机译:ICRF;加热;托卡马克边缘损失;
  • 入库时间 2022-08-18 00:41:37

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