首页> 外文期刊>Nuclear fusion >Sensitivity of detachment extent to magnetic configuration and external parameters
【24h】

Sensitivity of detachment extent to magnetic configuration and external parameters

机译:脱离程度对磁性结构和外部参数的敏感性

获取原文
获取原文并翻译 | 示例
       

摘要

Divertor detachment may be essential to reduce heat loads to magnetic fusion tokamak reactor divertor surfaces. Yet in experiments it is difficult to control the extent of the detached, low pressure, plasma region. At maximum extent the front edge of the detached region reaches the X-point and can lead to degradation of core plasma properties. We define the 'detachment window' in a given position control variable C (for example, the upstream plasma density) as the range in C within which the front location can be stably held at any position from the target to the X-point; increased detachment window corresponds to better control. We extend a 1D analytic model to determine the detachment window for the following control variables: the upstream plasma density, the impurity concentration and the power entering the scrape-off layer (SOL). We find that variations in magnetic configuration can have strong effects; increasing the ratio of the total magnetic field at the X-point to that at the target, B_×/B_t, (total flux expansion, as in the super-x divertor configuration) strongly increases the detachment window for all control variables studied, thus strongly improving detachment front control and the capability of the divertor plasma to passively accommodate transients while still staying detached. Increasing flux tube length and thus volume in the divertor, through poloidal flux expansion (as in the snowftake or x-divertor configurations) or length of the divertor, also increases the detachment window, but less than the total flux expansion does. The sensitivity of the detachment front location, z_h, to each control variable, C, defined as ∂_(Z_h)/∂C, depends on the magnetic configuration. The size of the radiating volume and the total divertor radiation increase ∝ (B_×/B_t)~2 and ∝ B_×/B_t, respectively, but not by increasing divertor poloidal flux expansion or field line length. We believe this model is applicable more generally to any thermal fronts in flux tubes with varying magnetic field, and similar sources and sinks, such as detachment fronts in stellarator divertors and solar prominences in coronal loops.
机译:分流器分离对于减少磁聚变托卡马克反应堆分流器表面的热负荷可能至关重要。然而,在实验中,难以控制分离的低压等离子体区域的程度。分离区域的前边缘在最大程度上达到X点,并可能导致核心等离子体性能下降。我们将给定位置控制变量C(例如上游血浆密度)中的“分离窗口”定义为C中的范围,在该范围内,前端位置可以稳定地保持在从目标到X点的任何位置;增加的分离窗口对应于更好的控制。我们扩展一维分析模型来确定以下控制变量的分离窗口:上游等离子体密度,杂质浓度和进入刮除层(SOL)的功率。我们发现磁性结构的变化会产生强烈的影响。增加X点处的总磁场与目标处的总磁场之比B_x / B_t(总通量膨胀,如在super-x偏滤器配置中一样)会大大增加所有研究的控制变量的分离窗口,因此极大地改善了分离前部的控制,并改善了偏滤器等离子体在保持分离状态的同时被动适应瞬变的能力。通过极向通量膨胀(如在积雪或x型分流器配置中)或分流器的长度来增加通量管的长度,从而增加分流器中的体积,也会增加分离窗口,但小于总通量膨胀。分离前位置z_h对定义为C_(Z_h)/∂C的每个控制变量C的敏感度取决于磁性配置。辐射体积的大小和总偏滤器辐射的大小分别增加∝(B_×/ B_t)〜2和∝ B_×/ B_t,但不会通过增加偏滤器的倍数通量膨胀或场线长度来增加。我们认为,该模型更普遍适用于具有变化磁场的通量管中的任何热锋,以及类似的源和汇,例如恒星散射器中的分离锋和日冕中的太阳突出。

著录项

  • 来源
    《Nuclear fusion》 |2016年第5期|056007.1-056007.14|共14页
  • 作者单位

    York Plasma Institute, University of York, Heslington, York, YO10 5DQ, UK;

    Rudolf Peierls Centre for Theoretical Physics, University of Oxford, Oxford, OX1 3NP, UK,Culham Centre for Fusion Energy, Abingdon, OX14 3DB, UK;

    Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, MA 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

    divertor physics; detachment; feedback control; tokamak; flux expansion; plasma; solar prominence;

    机译:偏滤器物理;分离;反馈控制;托卡马克通量膨胀等离子体;太阳突出;
  • 入库时间 2022-08-18 00:41:58

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