Magnetic diagnostics layout design for CFETR plasma equilibrium reconstruction

doi:10.1088/1674-1056/ad23d6

中国物理B ›› 2024, Vol. 33 ›› Issue (4): 45201-045201.doi: 10.1088/1674-1056/ad23d6

Magnetic diagnostics layout design for CFETR plasma equilibrium reconstruction

Qingze Yu(于庆泽)^1,2, Yao Huang(黄耀)^1,†, Zhengping Luo(罗正平)¹, Yuehang Wang(汪悦航)¹, Zijie Liu(刘自结)³, Wangyi Rui(芮望颐)^1,2, Kai Wu(吴凯)¹, Bingjia Xiao(肖炳甲)^1,2, and Jiangang Li(李建刚)^1,2

1 Institute of Plasma Physics, Hefei Institute of Physical Science, Chinese Academy of Sciences, Hefei 230031, China;
2 University of Science and Technology of China, Hefei 230026, China;
3 College of Physics and Optoelectronic Engineering, Shenzhen University, Shenzhen 518060, China

收稿日期:2023-11-23 修回日期:2024-01-18 接受日期:2024-01-30 出版日期:2024-03-19 发布日期:2024-03-22
通讯作者: Yao Huang E-mail:yaohuang@ipp.ac.cn
基金资助:
Project supported by the National MCF Energy Research and Development Program of China (Grant Nos. 2022YFE03010002, 2018YFE0302100, and 2018YFE0301105) and the National Natural Science Foundation of China (Grant Nos. 11875291, 11805236, 11905256, and 12075285).

Magnetic diagnostics layout design for CFETR plasma equilibrium reconstruction

1 Institute of Plasma Physics, Hefei Institute of Physical Science, Chinese Academy of Sciences, Hefei 230031, China;
2 University of Science and Technology of China, Hefei 230026, China;
3 College of Physics and Optoelectronic Engineering, Shenzhen University, Shenzhen 518060, China

Received:2023-11-23 Revised:2024-01-18 Accepted:2024-01-30 Online:2024-03-19 Published:2024-03-22
Contact: Yao Huang E-mail:yaohuang@ipp.ac.cn
Supported by:
Project supported by the National MCF Energy Research and Development Program of China (Grant Nos. 2022YFE03010002, 2018YFE0302100, and 2018YFE0301105) and the National Natural Science Foundation of China (Grant Nos. 11875291, 11805236, 11905256, and 12075285).

摘要/Abstract

摘要： Plasma equilibrium reconstruction provides essential information for tokamak operation and physical analysis. An extensive and reliable set of magnetic diagnostics is required to obtain accurate plasma equilibrium. This study designs and optimizes the magnetic diagnostics layout for the reconstruction of the equilibrium of the plasma according to the scientific objectives, engineering design parameters, and limitations of the Chinese Fusion Engineering Test Reactor (CFETR). Based on the CFETR discharge simulation, magnetic measurement data are employed to reconstruct consistent plasma equilibrium parameters, and magnetic diagnostics' number and position are optimized by truncated Singular value decomposition, verifying the redundancy reliability of the magnetic diagnostics layout design. This provides a design solution for the layout of the magnetic diagnostics system required to control the plasma equilibrium of CFETR, and the developed design and optimization method can provide effective support to design magnetic diagnostics systems for future magnetic confinement fusion devices.

关键词: plasma equilibrium reconstruction, EFIT code, flux loops and magnetic probes, optimization

Abstract: Plasma equilibrium reconstruction provides essential information for tokamak operation and physical analysis. An extensive and reliable set of magnetic diagnostics is required to obtain accurate plasma equilibrium. This study designs and optimizes the magnetic diagnostics layout for the reconstruction of the equilibrium of the plasma according to the scientific objectives, engineering design parameters, and limitations of the Chinese Fusion Engineering Test Reactor (CFETR). Based on the CFETR discharge simulation, magnetic measurement data are employed to reconstruct consistent plasma equilibrium parameters, and magnetic diagnostics' number and position are optimized by truncated Singular value decomposition, verifying the redundancy reliability of the magnetic diagnostics layout design. This provides a design solution for the layout of the magnetic diagnostics system required to control the plasma equilibrium of CFETR, and the developed design and optimization method can provide effective support to design magnetic diagnostics systems for future magnetic confinement fusion devices.

Key words: plasma equilibrium reconstruction, EFIT code, flux loops and magnetic probes, optimization

中图分类号: (Tokamaks, spherical tokamaks)

52.55.Fa

28.52.-s (Fusion reactors) 52.70.Ds (Electric and magnetic measurements) 52.55.-s (Magnetic confinement and equilibrium)

Qingze Yu(于庆泽), Yao Huang(黄耀), Zhengping Luo(罗正平), Yuehang Wang(汪悦航), Zijie Liu(刘自结), Wangyi Rui(芮望颐), Kai Wu(吴凯), Bingjia Xiao(肖炳甲), and Jiangang Li(李建刚). Magnetic diagnostics layout design for CFETR plasma equilibrium reconstruction[J]. 中国物理B, 2024, 33(4): 45201-045201.

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Magnetic diagnostics layout design for CFETR plasma equilibrium reconstruction

Magnetic diagnostics layout design for CFETR plasma equilibrium reconstruction

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