• 文献检索
  • 文档翻译
  • 深度研究
  • 学术资讯
  • Suppr Zotero 插件Zotero 插件
  • 邀请有礼
  • 套餐&价格
  • 历史记录
应用&插件
Suppr Zotero 插件Zotero 插件浏览器插件Mac 客户端Windows 客户端微信小程序
定价
高级版会员购买积分包购买API积分包
服务
文献检索文档翻译深度研究API 文档MCP 服务
关于我们
关于 Suppr公司介绍联系我们用户协议隐私条款
关注我们

Suppr 超能文献

核心技术专利:CN118964589B侵权必究
粤ICP备2023148730 号-1Suppr @ 2026

文献检索

告别复杂PubMed语法,用中文像聊天一样搜索,搜遍4000万医学文献。AI智能推荐,让科研检索更轻松。

立即免费搜索

文件翻译

保留排版,准确专业,支持PDF/Word/PPT等文件格式,支持 12+语言互译。

免费翻译文档

深度研究

AI帮你快速写综述,25分钟生成高质量综述,智能提取关键信息,辅助科研写作。

立即免费体验

Detachment in Fusion Plasmas with Symmetry Breaking Magnetic Perturbation Fields.

作者信息

Frerichs H, Schmitz O, Bonnin X, Loarte A, Feng Y, Li L, Liu Y Q, Reiter D

机构信息

Department of Engineering Physics, University of Wisconsin, Madison, Wisconsin 53706, USA.

ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St. Paul Lez Durance Cedex, France.

出版信息

Phys Rev Lett. 2020 Oct 9;125(15):155001. doi: 10.1103/PhysRevLett.125.155001.

DOI:10.1103/PhysRevLett.125.155001
PMID:33095602
Abstract

Power exhaust from the bulk plasma is significantly altered by symmetry breaking magnetic perturbation fields, because these create direct connections (perturbed field lines) from the confined high temperature plasma to solid surfaces. The same amount of power is distributed among those new exhaust channels as for a symmetric magnetic configuration, which reduces the local upstream heat flux flowing down the perturbed field lines, thereby making access to detachment easier (i.e., at lower upstream density) for the divertor plasma near the location corresponding to the symmetric magnetic separatrix. However, the divertor plasma regions with connection to the bulk plasma are extended nonaxisymmetrically further outside, where significant heat loads occur, unlike in the symmetric configuration. The temperature remains high at those locations, which reduces the divertor plasma dissipation capacity, making the mitigation of heat loads more difficult to achieve.

摘要

相似文献

1
Detachment in Fusion Plasmas with Symmetry Breaking Magnetic Perturbation Fields.
Phys Rev Lett. 2020 Oct 9;125(15):155001. doi: 10.1103/PhysRevLett.125.155001.
2
Real-time feedback control of the impurity emission front in tokamak divertor plasmas.托卡马克偏滤器等离子体中杂质发射前沿的实时反馈控制。
Nat Commun. 2021 Feb 17;12(1):1105. doi: 10.1038/s41467-021-21268-3.
3
First Evidence of Local E×B Drift in the Divertor Influencing the Structure and Stability of Confined Plasma near the Edge of Fusion Devices.在偏滤器中存在局部E×B漂移影响聚变装置边缘受限等离子体结构和稳定性的首个证据。
Phys Rev Lett. 2020 May 15;124(19):195002. doi: 10.1103/PhysRevLett.124.195002.
4
E×B Flux Driven Detachment Bifurcation in the DIII-D Tokamak.E×B 磁通驱动脱体分叉在 DIII-D 托卡马克装置中的研究。
Phys Rev Lett. 2018 Aug 17;121(7):075001. doi: 10.1103/PhysRevLett.121.075001.
5
Broadening of the Divertor Heat Flux Profile in High Confinement Tokamak Fusion Plasmas with Edge Pedestals Limited by Turbulence in DIII-D.在DIII-D中,具有受湍流限制的边缘台基的高约束托卡马克聚变等离子体中偏滤器热通量分布的展宽
Phys Rev Lett. 2024 Jun 7;132(23):235102. doi: 10.1103/PhysRevLett.132.235102.
6
Development of an 11-channel multi wavelength imaging diagnostic for divertor plasmas in MAST Upgrade.用于MAST升级装置偏滤器等离子体的11通道多波长成像诊断设备的研制。
Rev Sci Instrum. 2021 Jun 1;92(6):063510. doi: 10.1063/5.0043533.
7
Compact Radiative Divertor Experiments at ASDEX Upgrade and Their Consequences for a Reactor.紧凑辐射偏滤器实验在 ASDEX Upgrade 上的实现及其对反应堆的影响。
Phys Rev Lett. 2023 Apr 7;130(14):145102. doi: 10.1103/PhysRevLett.130.145102.
8
Diagnostic options for radiative divertor feedback control on NSTX-U.NSTX-U上辐射偏滤器反馈控制的诊断选项。
Rev Sci Instrum. 2012 Oct;83(10):10D716. doi: 10.1063/1.4732176.
9
Surface thermocouples for measurement of pulsed heat flux in the divertor of the Alcator C-Mod tokamak.用于测量阿尔卡特C-Mod托卡马克偏滤器中脉冲热通量的表面热电偶。
Rev Sci Instrum. 2012 Mar;83(3):033501. doi: 10.1063/1.3689770.
10
First Observation of a Stable Highly Dissipative Divertor Plasma Regime on the Wendelstein 7-X Stellarator.在文德尔施泰因7-X仿星器上首次观测到稳定的高耗散偏滤器等离子体状态。
Phys Rev Lett. 2019 Jul 12;123(2):025002. doi: 10.1103/PhysRevLett.123.025002.