首页> 外文期刊>Nuclear fusion >Optimizing multi-modal, non-axisymmetric plasma response metrics with additional coil rows on DIII-D
【24h】

Optimizing multi-modal, non-axisymmetric plasma response metrics with additional coil rows on DIII-D

机译:优化多模态,非轴对称等离子体响应度量,DIII-D上的附加线圈行

获取原文
获取原文并翻译 | 示例
           

摘要

The expansion of the DIII-D tokamak operational space via the addition of new non-axisymmetric coil rows is investigated using the linear MHD plasma response code MARS-F. The plasma response to magnetic perturbations imposed by five distinct low-and high-field side coil geometries is modeled for toroidal mode numbers up to n = 6. A set of linear (similar to delta B: resonant, kink mode amplitude) and quadratic (similar to delta B-2: core and edge integrated NTV torque) plasma metrics are defined and compared directly for the various coil geometries. Coil size is also scanned as a secondary optimization variable. An in-vessel coil located at the low-field side midplane is identified as the most efficient plasma response actuator across all metrics and toroidal mode numbers. The multi-row combination of this new midplane (M) coil with the existing DIII-D non-axisymmetric coil set is considered in numerical optimization studies to quantify the impact of this new coil on modeled plasma response metrics. The addition of the M coil is shown to significantly increase the actuator efficiency in maximizing individual plasma response metrics as well as maximizing multi-modal ratios of response metrics, e.g. maximizing resonant modes or edge NTV torque while minimizing kink modes or core NTV torque. The ex-vessel midplane (C) coil is also observed to have an outsize effect on multi-modal optimization due to its uniquely narrow poloidal spectra, and the expansion of optimization space due to the combined use of the two existing in-vessel coil rows with both the M and C coils is notably larger than either coil's individual contribution even though both share similar poloidal locations. This four-row system is expected to greatly extend abilities to understand and optimize the control of transients and rotation on the DIII-D tokamak.
机译:通过添加新的非轴对称线圈行使用线性MHD等离子体响应码MARS-F来研究DIII-D Tokamak操作空间的扩展。对五个不同的低和高场侧线圈几何形状施加的磁扰动的等离子体响应是针对环形模式编号的模型,其直到n = 6.一组线性(类似于Delta B:谐振,扭结模式幅度)和二次(与Delta B-2:核心和边缘集成NTV扭矩)定义并直接比较各种线圈几何形状的等离子体度量。线圈尺寸也被扫描为辅助优化变量。位于低场侧中间平面处的容器内部线圈被识别为跨所有度量和环形模式编号的最有效的等离子体响应致动器。在数值优化研究中考虑了具有现有DIII-D非轴对称线圈组的这种新的中间板(M)线圈的多行组合,以量化该新线圈对模型等离子体响应度量的影响。显示M线圈的添加显着提高了最大化单个等离子体响应度量的致动器效率,以及最大化响应度量的多模态比。最大化谐振模式或边缘NTV扭矩,同时最小化扭结模式或核心NTV扭矩。还观察到ex-assel中平板(c)线圈由于其独特的窄面谱而对多模态优化具有超出效果,以及由于两个现有的血管线圈行的组合使用而导致的优化空间的扩展对于M和C线圈,即使两个共享类似的单位位置,M和C线圈也比线圈的个体贡献大。这一四排系统预计将大大扩展到理解和优化DIII-D Tokamak上的瞬态和旋转的能力。

著录项

  • 来源
    《Nuclear fusion》 |2019年第8期|086060.1-086060.16|共16页
  • 作者单位

    Gen Atom POB 85608 San Diego CA 92186 USA;

    Gen Atom POB 85608 San Diego CA 92186 USA;

    Gen Atom POB 85608 San Diego CA 92186 USA;

    Princeton Plasma Phys Lab Princeton NJ 08543 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

    coil design; plasma response; NTV torque; ELM control;

    机译:线圈设计;等离子体响应;NTV扭矩;ELM控制;

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