• 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

托卡马克聚变等离子体中全偏滤器脱靶与改善芯部约束的集成。

Integration of full divertor detachment with improved core confinement for tokamak fusion plasmas.

作者信息

Wang L, Wang H Q, Ding S, Garofalo A M, Gong X Z, Eldon D, Guo H Y, Leonard A W, Hyatt A W, Qian J P, Weisberg D B, McClenaghan J, Fenstermacher M E, Lasnier C J, Watkins J G, Shafer M W, Xu G S, Huang J, Ren Q L, Buttery R J, Humphreys D A, Thomas D M, Zhang B, Liu J B

机构信息

Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, China.

General Atomics, San Diego, CA, USA.

出版信息

Nat Commun. 2021 Mar 1;12(1):1365. doi: 10.1038/s41467-021-21645-y.

DOI:10.1038/s41467-021-21645-y
PMID:33649306
原文链接:https://pmc.ncbi.nlm.nih.gov/articles/PMC7921092/
Abstract

Divertor detachment offers a promising solution to the challenge of plasma-wall interactions for steady-state operation of fusion reactors. Here, we demonstrate the excellent compatibility of actively controlled full divertor detachment with a high-performance (β ~ 3, H ~ 1.5) core plasma, using high-β (poloidal beta, β > 2) scenario characterized by a sustained core internal transport barrier (ITB) and a modest edge transport barrier (ETB) in DIII-D tokamak. The high-β high-confinement scenario facilitates divertor detachment which, in turn, promotes the development of an even stronger ITB at large radius with a weaker ETB. This self-organized synergy between ITB and ETB, leads to a net gain in energy confinement, in contrast to the net confinement loss caused by divertor detachment in standard H-modes. These results show the potential of integrating excellent core plasma performance with an efficient divertor solution, an essential step towards steady-state operation of reactor-grade plasmas.

摘要

偏滤器脱靶为聚变反应堆稳态运行中面临的等离子体与壁相互作用挑战提供了一个有前景的解决方案。在此,我们利用DIII-D托卡马克中以持续的芯部内部输运垒(ITB)和适度的边缘输运垒(ETB)为特征的高β(极向β,β>2)工况,展示了主动控制的全偏滤器脱靶与高性能(β~3,H~1.5)芯部等离子体的优异兼容性。高β高约束工况促进了偏滤器脱靶,反过来又在大半径处促进了更强的ITB的发展,同时ETB减弱。ITB和ETB之间这种自组织协同作用导致能量约束净增益,这与标准H模中偏滤器脱靶导致的约束净损失形成对比。这些结果表明了将优异的芯部等离子体性能与高效的偏滤器解决方案相结合的潜力,这是朝着反应堆级等离子体稳态运行迈出的关键一步。

https://cdn.ncbi.nlm.nih.gov/pmc/blobs/30f7/7921092/2ca696244c8f/41467_2021_21645_Fig7_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/30f7/7921092/bfe74cb1a0b4/41467_2021_21645_Fig1_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/30f7/7921092/91d43800f58f/41467_2021_21645_Fig2_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/30f7/7921092/406cbe4b6746/41467_2021_21645_Fig3_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/30f7/7921092/d815b30f5f6f/41467_2021_21645_Fig4_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/30f7/7921092/3ef38bd9d7b9/41467_2021_21645_Fig5_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/30f7/7921092/fa00f9d878f5/41467_2021_21645_Fig6_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/30f7/7921092/2ca696244c8f/41467_2021_21645_Fig7_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/30f7/7921092/bfe74cb1a0b4/41467_2021_21645_Fig1_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/30f7/7921092/91d43800f58f/41467_2021_21645_Fig2_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/30f7/7921092/406cbe4b6746/41467_2021_21645_Fig3_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/30f7/7921092/d815b30f5f6f/41467_2021_21645_Fig4_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/30f7/7921092/3ef38bd9d7b9/41467_2021_21645_Fig5_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/30f7/7921092/fa00f9d878f5/41467_2021_21645_Fig6_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/30f7/7921092/2ca696244c8f/41467_2021_21645_Fig7_HTML.jpg

相似文献

1
Integration of full divertor detachment with improved core confinement for tokamak fusion plasmas.托卡马克聚变等离子体中全偏滤器脱靶与改善芯部约束的集成。
Nat Commun. 2021 Mar 1;12(1):1365. doi: 10.1038/s41467-021-21645-y.
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
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.
4
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.
5
A high-density and high-confinement tokamak plasma regime for fusion energy.一种用于聚变能的高密度高约束托卡马克等离子体状态。
Nature. 2024 May;629(8012):555-560. doi: 10.1038/s41586-024-07313-3. Epub 2024 Apr 24.
6
Realization of thousand-second improved confinement plasma with Super I-mode in Tokamak EAST.托卡马克 EAST 中实现超 I 模千秒改进约束等离子体。
Sci Adv. 2023 Jan 6;9(1):eabq5273. doi: 10.1126/sciadv.abq5273.
7
Near-infrared spectroscopy for divertor plasma diagnosis and control in DIII-D tokamak.用于DIII-D托卡马克装置中偏滤器等离子体诊断与控制的近红外光谱技术。
Rev Sci Instrum. 2014 Nov;85(11):11E418. doi: 10.1063/1.4891600.
8
Tokamak operation with safety factor q95 < 2 via control of MHD stability.通过控制磁流体动力学稳定性实现安全因子q95 < 2的托卡马克运行。
Phys Rev Lett. 2014 Jul 25;113(4):045003. doi: 10.1103/PhysRevLett.113.045003. Epub 2014 Jul 24.
9
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.
10
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.

引用本文的文献

1
A high-density and high-confinement tokamak plasma regime for fusion energy.一种用于聚变能的高密度高约束托卡马克等离子体状态。
Nature. 2024 May;629(8012):555-560. doi: 10.1038/s41586-024-07313-3. Epub 2024 Apr 24.
2
Single-crystal ZrCo nanoparticle for advanced hydrogen and H-isotope storage.用于先进氢及氢同位素存储的单晶ZrCo纳米颗粒。
Nat Commun. 2023 Dec 2;14(1):7966. doi: 10.1038/s41467-023-43828-5.
3
Tungsten Material Behavior under H, D, and He Plasma Interaction Conditions in the Framework of Fusion-Relevant Studies.

本文引用的文献

1
The way ahead for fusion.核聚变的未来之路。
Nat Phys. 2020;16(9):889. doi: 10.1038/s41567-020-01043-9. Epub 2020 Aug 28.
2
Role of Microtearing Turbulence in DIII-D High Bootstrap Current Fraction Plasmas.微撕裂湍流在 DIII-D 高 bootstrap 电流分数等离子体中的作用。
Phys Rev Lett. 2019 Nov 29;123(22):225002. doi: 10.1103/PhysRevLett.123.225002.
3
Initial results of the high resolution edge Thomson scattering upgrade at DIII-D.DIII-D装置高分辨率边缘汤姆逊散射升级的初步结果。
在聚变相关研究框架下,氢、氘和氦等离子体相互作用条件下的钨材料行为。
Materials (Basel). 2023 Oct 25;16(21):6853. doi: 10.3390/ma16216853.
4
Steady-state burning plasma: a new stage in the development of magnetic confinement fusion energy.稳态燃烧等离子体:磁约束聚变能源发展的新阶段。
Natl Sci Rev. 2023 Aug 14;10(12):nwad217. doi: 10.1093/nsr/nwad217. eCollection 2023 Dec.
5
Recent progress in Chinese fusion research based on superconducting tokamak configuration.基于超导托卡马克构型的中国聚变研究的最新进展。
Innovation (Camb). 2022 Jun 11;3(4):100269. doi: 10.1016/j.xinn.2022.100269. eCollection 2022 Jul 12.
Rev Sci Instrum. 2012 Oct;83(10):10E343. doi: 10.1063/1.4738656.
4
Observation of continuous divertor detachment in H-mode discharges in ASDEX upgrade.在ASDEX升级装置的H模式放电中对连续偏滤器脱逸的观测。
Phys Rev Lett. 1995 May 22;74(21):4217-4220. doi: 10.1103/PhysRevLett.74.4217.
5
Internal transport barrier on q=3 surface and poloidal plasma spin up in JT-60U high- beta p discharges.JT - 60U高βp放电中q = 3表面的内部输运垒和极向等离子体自旋加速
Phys Rev Lett. 1994 Jun 6;72(23):3662-3665. doi: 10.1103/PhysRevLett.72.3662.