Design of magnetic equilibrium for CFEDR

Abstract This study presents the design progress of the equilibrium configuration for the China Fusion Engineering Demo Reactor (CFEDR). A new equilibrium was developed using the TEQ code, incorporating both zero-dimensional physical parameters and the engineering specifications of the magnetic coils. Through iterative optimization of the divertor and blanket structures, the first viable single-null divertor (SND) plasma configuration was achieved. The METIS code was further used to efficiently calculate current and pressure profiles during the ramp-up and flattop phases, thereby validating the design of the poloidal field (PF) coils. Results indicate that the current PF coil system meets the requirements for the SND configuration but faces challenges in maintaining the quasi-snowflake plus shape.

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Publication Details

Journal
Plasma Science and Technology
Published
2025-09-02
DOI
https://doi.org/10.1088/2058-6272/ae0266
Citations
3
Primary Topic
Magnetic confinement fusion research
Type
article
Field-Weighted Citation Impact
5.61

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article

Design of magnetic equilibrium for CFEDR

Songlin 松林 LIU 刘, Guoqiang Li, T- Team, Rui 锐 DING 丁 et al.
3 citations
Plasma Science and Technology
Magnetic confinement fusion research
5.61
article

Design of magnetic equilibrium for CFEDR

Songlin 松林 LIU 刘, Guoqiang Li, T- Team, Rui 锐 DING 丁, Hang 航 LI 李, Miaohui 妙辉 LI 李, Yao 耀 HUANG 黄, Xiaoju 晓菊 LIU 刘, Yuehang 悦航 WANG 汪
article en
3 citations

Abstract

Abstract This study presents the design progress of the equilibrium configuration for the China Fusion Engineering Demo Reactor (CFEDR). A new equilibrium was developed using the TEQ code, incorporating both zero-dimensional physical parameters and the engineering specifications of the magnetic coils. Through iterative optimization of the divertor and blanket structures, the first viable single-null divertor (SND) plasma configuration was achieved. The METIS code was further used to efficiently calculate current and pressure profiles during the ramp-up and flattop phases, thereby validating the design of the poloidal field (PF) coils. Results indicate that the current PF coil system meets the requirements for the SND configuration but faces challenges in maintaining the quasi-snowflake plus shape.

Plasma Science and TechnologyVol. 27(10)
Chinese Academy of Sciences (CN), Institute of Plasma Physics (CN)
National Natural Science Foundation of China, National Magnetic Confinement Fusion Program of China
Openalex Percentile: Top 5%
Magnetic confinement fusion research
5.61
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