| PHYSICS OF GASES, PLASMAS, AND ELECTRIC DISCHARGES |
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A divertor plasma configuration design method for tokamaks |
| Yong Guo(郭勇)1, Bing-Jia Xiao(肖炳甲)1,2, Lei Liu(刘磊)1, Fei Yang(杨飞)3, Yuehang Wang(汪悦航)4, Qinglai Qiu (仇庆来)1 |
1 Institute of Plasma Physics, Chinese Academy of Science, Hefei 230031, China;
2 School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230026, China;
3 Department of Computer Science, Anhui Medical University, Hefei 230026, China;
4 CAS Key Laboratory of Basic Plasma Physics and Department of Modern Physics, University of Science and Technology of China, Hefei 230026, China |
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Abstract The efficient and safe operation of large fusion devices strongly relies on the plasma configuration inside the vacuum chamber. It is important to construct the proper plasma equilibrium with a desired plasma configuration. In order to construct the target configuration, a shape constraint module has been developed in the tokamak simulation code (TSC), which controls the poloidal flux and the magnetic field at several defined control points. It is used to construct the double null, lower single null, and quasi-snowflake configurations for the required target shape and calculate the required PF coils current. The flexibility and practicability of this method have been verified by the simulated results.
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Received: 23 May 2016
Revised: 05 July 2016
Accepted manuscript online:
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PACS:
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52.55.Fa
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(Tokamaks, spherical tokamaks)
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52.65.-y
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(Plasma simulation)
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52.50.Nr
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(Plasma heating by DC fields; ohmic heating, arcs)
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| Fund: Project supported by the National Magnetic Confinement Fusion Research Program of China (Grant Nos. 2014GB103000 and 2014GB110003), the National Natural Science Foundation of China (Grant Nos. 11305216, 11305209, and 11375191), and External Cooperation Program of BIC, Chinese Academy of Sciences (Grant No. GJHZ201303). |
Corresponding Authors:
Lei Liu
E-mail: liulei@ipp.ac.cn
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Cite this article:
Yong Guo(郭勇), Bing-Jia Xiao(肖炳甲), Lei Liu(刘磊), Fei Yang(杨飞), Yuehang Wang(汪悦航), Qinglai Qiu (仇庆来) A divertor plasma configuration design method for tokamaks 2016 Chin. Phys. B 25 115201
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