首页> 外文期刊>Nuclear fusion >The relation between upstream density and temperature widths in the scrape-off layer and the power width in an attached divertor
【24h】

The relation between upstream density and temperature widths in the scrape-off layer and the power width in an attached divertor

机译:刮除层中上游密度和温度宽度与连接的分流器中功率宽度之间的关系

获取原文
获取原文并翻译 | 示例
       

摘要

The target power width λ_q~(target) is one of the most critical practical quantities in the development of magnetic fusion energy. It is essential to know how to scale this quantity to future devices. At present the controlling physics is not adequately understood, making reliable prediction difficult. It seems likely that two important processes effecting λ_q~(target) are (a) cross-field transport, e.g. D_⊥, x_(⊥e.i) and (b) volumetric power loss processes in the edge plasma, with the latter tending to occur mainly in the divertor for attached divertor conditions. It is hypothesized that a simple relation exists between the 'upstream' radial profiles of ne and T_e in the main scrape-off layer, λ_(n_u), λ_(T_(ue)), and the parallel power flux density at the divertor entrance, λ_(q||)~(div-ent). Such a simple relation is found here in 2D SOLPS edge code simulations of attached divertor conditions, which contain a wide range of more or less complex edge physics effects. It is found that λ_(q||)~(div-ent) ≈ {[(3/2)/λ_(T_(ue))] + (1/λ_(n_u))}~(-1) as can be expected on the basis of flux-limited parallel heat conduction, rather than Spitzer-Harm conduction for which λ_(q||)~(div-ent) ≈ 2/7λ_(T_(ue)) is expected. For the relatively open divertor configuration considered, and for attached divertor conditions, it is found that the flux-limited relationship also holds for the SOLPS power flux density deposited on the target λ_q~(target), even including the radiation load; this despite the fact that up to half the power into the SOL is dissipated radiatively. Comparing with experimentally measured target power widths for H-mode discharges, better agreement is found assuming flux limited rather than Spitzer-Harm transport although definitive conclusions will require analysis of specific discharges in specific tokamaks. This study is a necessary preliminary work to an equivalent treatment of the case where volumetric losses in the divertor are stronger, including the detached, strongly radiating divertor case with momentum loss.
机译:目标功率宽度λ_q〜(target)是磁聚变能发展中最关键的实际量之一。了解如何将这一数量扩展到未来的设备至关重要。目前,对控制物理学的认识还不够充分,因此很难进行可靠的预测。影响λ_q_(target)的两个重要过程似乎是(a)跨场传输,例如D_⊥,x_(⊥e.i)和(b)边缘等离子体中的体积功率损失过程,对于附接的偏滤器条件,后者往往主要发生在偏滤器中。假设在主刮除层ne和T_e的“上游”径向轮廓λ_(n_u),λ_(T_(ue))与分流器入口处的平行功率通量密度之间存在简单关系,λ_(q ||)〜(div-ent)。这样的简单关系可以在附加的偏滤器条件的2D SOLPS边缘代码模拟中找到,其中包含各种或多或少复杂的边缘物理效应。发现λ_(q ||)〜(div-ent)≈{[[(3/2)/λ_(T_(ue))] +(1 /λ_(n_u))}〜(-1)可以根据通量有限的平行热传导来预期,而不是期望λ_(q ||)〜(div-ent)≈2 /7λ_(T_(ue))的Spitzer-Harm传导。对于所考虑的相对开放的偏滤器配置以及附加的偏滤器条件,发现通量限制关系也适用于沉积在目标λ_q〜(target)上的SOLPS功率通量密度,甚至包括辐射负荷;尽管事实上,多达一半的SOL能量是通过辐射散发的。与实验测量的H型放电目标功率宽度相比,假设通量受限而不是Spitzer-Harm传输,则可以找到更好的一致性,尽管明确的结论需要分析特定托卡马克中的特定放电。此项研究是对等价处理偏滤器体积损失更大的情况(包括分离的强辐射偏滤器动量损失情况)进行必要的初步工作。

著录项

  • 来源
    《Nuclear fusion》 |2010年第12期|p.3.1-3.12|共12页
  • 作者单位

    University of Toronto Institute for Aerospace Studies, Toronto, M3H 5T6, Canada;

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

    MIT Plasma Science and Fusion Center, Cambridge, Massachusetts 02139, 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
  • 关键词

  • 入库时间 2022-08-18 00:44:49

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号