Real-time feedback system for divertor heat flux control at COMPASS tokamak

Khodunov I; Komm M.; Havranek A.; Adamek J.; Bohm P.; Cavalier J.; Seidl J.; Devitre A.; Dimitrova M.; Elmore S.; Faitsch M.; Hacek P.; Havlicek J.; Hron M.; Imrisek M.; Krbec J.; Peterka M.; Panek R.; Samoylov O.; Tomes M.; Tomova K.; Vondracek P.; Weinzettl V

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Real-time feedback system for divertor heat flux control at COMPASS tokamak

机译：罗盘托卡马克的转移器热通量控制的实时反馈系统

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摘要

The reduction of the incident heat flux onto the divertor will be a necessity for the future thermonuclear reactors. Impurity seeding is recognized as an efficient way to achieve the partial detachment regime, which allows to dissipate a large fraction of power flux by radiation. This paper presents a heat flux real-time feedback system (RTFS) based on impurity seeding controlled by a combined ball-pen and Langmuir probe divertor array in the COMPASS tokamak. A number of features of the system have been studied, such as the type of impurity, seeding location, constants used in the real-time controller and the diagnostic selections. A detailed description of the designed RTFS and the results of the implementation are presented. The findings confirm the applicability of the RTFS for reduction and control of the divertor heat fluxes. Another important implication of this research is the ability of installing such systems in next-step devices.

机译：减少偏滤器上的入射热流将是未来热核反应堆的必要条件。杂质注入被认为是实现部分分离区的有效方法，它允许通过辐射耗散大部分功率通量。本文介绍了一种基于圆珠笔和朗缪尔探针偏滤器组合控制的杂质注入热流实时反馈系统（RTFS）。研究了系统的一些特性，如杂质类型、种子位置、实时控制器中使用的常数和诊断选择。详细描述了设计的RTF和实现结果。研究结果证实了RTFS在减少和控制偏滤器热通量方面的适用性。这项研究的另一个重要意义是在下一步设备中安装此类系统的能力。

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来源
《Plasma physics and controlled fusion》 |2021年第6期|共8页
作者
Khodunov I; Komm M.; Havranek A.; Adamek J.; Bohm P.; Cavalier J.; Seidl J.; Devitre A.; Dimitrova M.; Elmore S.; Faitsch M.; Hacek P.; Havlicek J.; Hron M.; Imrisek M.; Krbec J.; Peterka M.; Panek R.; Samoylov O.; Tomes M.; Tomova K.; Vondracek P.; Weinzettl V;
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作者单位

CAS Inst Plasma Phys Slovankou 3 Prague 18200 8 Czech Republic;

CAS Inst Plasma Phys Slovankou 3 Prague 18200 8 Czech Republic;

CAS Inst Plasma Phys Slovankou 3 Prague 18200 8 Czech Republic;

CAS Inst Plasma Phys Slovankou 3 Prague 18200 8 Czech Republic;

CAS Inst Plasma Phys Slovankou 3 Prague 18200 8 Czech Republic;

CAS Inst Plasma Phys Slovankou 3 Prague 18200 8 Czech Republic;

CAS Inst Plasma Phys Slovankou 3 Prague 18200 8 Czech Republic;

Univ Ghent Dept Appl Phys Ghent Belgium;

CAS Inst Plasma Phys Slovankou 3 Prague 18200 8 Czech Republic;

CCFE Culham Sci Ctr Abingdon OX14 3DB Oxon England;

Max Planck Inst Plasma Phys D-85748 Garching Germany;

CAS Inst Plasma Phys Slovankou 3 Prague 18200 8 Czech Republic;

CAS Inst Plasma Phys Slovankou 3 Prague 18200 8 Czech Republic;

CAS Inst Plasma Phys Slovankou 3 Prague 18200 8 Czech Republic;

CAS Inst Plasma Phys Slovankou 3 Prague 18200 8 Czech Republic;

CAS Inst Plasma Phys Slovankou 3 Prague 18200 8 Czech Republic;

CAS Inst Plasma Phys Slovankou 3 Prague 18200 8 Czech Republic;

CAS Inst Plasma Phys Slovankou 3 Prague 18200 8 Czech Republic;

Aix Marseille Univ Marseille France;

CAS Inst Plasma Phys Slovankou 3 Prague 18200 8 Czech Republic;

Univ Lorraine Nancy France;

CAS Inst Plasma Phys Slovankou 3 Prague 18200 8 Czech Republic;

CAS Inst Plasma Phys Slovankou 3 Prague 18200 8 Czech Republic;

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原文格式 PDF
正文语种 eng
中图分类等离子体物理学;
关键词
plasma; tokamak; detachment; nitrogen; divertor; heat flux;

机译：等离子体;Tokamak;脱离;氮气;偏转器;热通量;

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1. Calculation of the heat flux in the lower divertor target plate using an infrared camera diagnostic system on the experimental advanced superconducting tokamak [J] . Zhi-Xue Cui, Xin Li, Shuang-Bao Shu, 核技术（英文版） . 2019,第006期
2. Analysis of Divertor Heat Flux with Infrared Thermography During Gas Fuelling in the HL-2A Tokamak [J] . GAO Jinming, LI Wei, XIA Zhiwei, 等离子体科学和技术（英文版） . 2013,第011期
3. Observation of deuterium molecule emission spectra under an active feedback control of H-mod plasma divertor detachment experiment on the EAST tokamak [J] . Wei Gao, the EAST Team, Juan Huang, 中国物理：英文版 . 2019,第012期
4. The Construction of Plasma Density Feedback Control System on J-TEXT Tokamak [J] . KE Xin, CHEN Zhipeng, BA Weigang, 等离子体科学和技术（英文版） . 2016,第002期
5. Real-time estimation and control of divertor surface heat flux on the DⅢ-D tokamak [J] . Anand H., Eldon D., Humphreys D., Fusion Engineering and Design . 2021,第Octa期

机译：DⅢ-D Tokamak上的转子表面热通量的实时估计与控制
6. Scaling of L-mode heat flux for ITER and COMPASS-U divertors, based on five tokamaks [J] . J. Horacek, J. Adamek, M. Komm, Nuclear fusion . 2020,第6期

机译：基于五个Tokamaks的ITER和COMPART-U VERERTORS的L模式热通量的缩放
7. Upgrade of the COMPASS tokamak real-time control system [J] . F. Janky, J.Havlicek, A.J.N. Batista, Fusion Engineering and Design . 2014,第3期

机译：升级COMPASS tokamak实时控制系统
8. PPPS-2013: Modeling snowflake divertors for reduced surface heat-flux in tokamaks [C] . Rognlien T.D., Cohen R.H., Ryutov D.D., 2013 Abstracts IEEE International Conference on Plasma Science . 2013

机译：PPPS-2013：为减少托卡马克表面热通量而设计的雪花偏滤器
9. Design of real-time combustion feedback system and experimental study of an RCCI engine for control [D] . Arora, Jayant Kumar. 2016

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10. Development of a Real-Time Human-Robot Collaborative System Based on 1 kHz Visual Feedback Control and Its Application to a Peg-in-Hole Task [O] . Yuji Yamakawa, Yutaro Matsui, Masatoshi Ishikawa 2021

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11. Feedback system for divertor impurity seeding based on real-time measurements of surface heat flux in the Alcator C-Mod tokamak [O] . Brunner D., Burke W., Kuang A. Q., 2016

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12. Enhanced Particle Flux Control in a Tokamak with a Resonant Helical Divertor [R] . Evans, T. E. , deGrassie, J. S. , Jackson, G. L. , 1987

机译：用共振螺旋转向器在托卡马克中增强粒子通量控制

Real-time feedback system for divertor heat flux control at COMPASS tokamak

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