Overview of Magnetic Confinement Controlled Nuclear Fusion Reactors and Superconducting Magnet Technologies

doi:10.12096/j.2096-4528.pgt.24119

Abstract

Abstract:

Objectives Magnetic confinement fusion is regarded as a critical solution to future global energy challenges. As the central component of magnetic confinement fusion devices, magnets play a crucial role in generating and sustaining plasma stability. A review of the magnetic system structures and specifications in representative magnetic confinement fusion devices worldwide was provided. Methods The technological evolution of fusion magnets was reviewed, from copper-based to low-temperature superconducting, and finally to high-temperature superconducting magnets. The structure and performance parameters of magnetic systems in various typical fusion devices were summarized systematically. Additionally, the technical challenges in magnet development were explored and an outlook on future development trend was offered. Conclusions Advances in magnet technology are vital for enhancing the performance of fusion devices and accelerating the commercialization of fusion energy. With the increasing application of high-temperature superconducting materials and continuous optimization of magnet designs, the practical realization of fusion energy is becoming increasingly feasible.

Key words: magnetic confinement controlled nuclear, high-temperature superconducting material, new energy, fusion energy resource, magnetic confinement fusion, Tokamak, fusion magnet, superconductor

CLC Number:

TK 01

Jialong ZHANG, Peng SONG, Timing QU. Overview of Magnetic Confinement Controlled Nuclear Fusion Reactors and Superconducting Magnet Technologies[J]. Power Generation Technology, 2024, 45(6): 995-1015.

Figures/Tables 26

Fig. 1 Diagram of the magnetic mirror effect

Fig. 2 Coil configuration in a stellarator

Fig. 3 Schematic diagram of a Tokamak device

Tab. 1 Some performance parameters of the magnet system of typical copper-based Tokamak devices

参数	系统名称
参数	TFTR	JET	JT-60	Alcator C-Mod	HL-3
首次运行年份	1982	1983	1985	1992	2020
主半径/m	2.48	2.96	3.32	0.68	1.78
TF线圈数量/个	20	32	18	20	20
TF线圈电流/kA	73.3	67	52.1	250	140(191)
中心磁场/T	5.2	3.45	4.5	8.0	2.2(3)
等离子体电流/MA	2.5	4.8	2.7	2	2.5(3)
国家或地区	美国	欧盟	日本	美国	中国

Fig. 4 Diagram of the internal structure of TFTR device

Fig. 5 Morphology diagram of JET device

Fig. 6 Morphology diagram of JT-60 device

Fig. 7 Cutaway view of Alcator C-Mod

Fig. 8 HL-3 device

Tab.2 Main performance parameters of typical low-temperature superconducting Tokamak devices

参数	系统名称
参数	EAST	KSTAR	CFETR	ITER
首次运行年份	2006	2008	2035(预计)	2033(预计)
主半径/m	1.85	1.8	7.2	6.2
TF线圈数量/个	16	16	16	18
TF线圈电流/kA	14.5	35.2	84.6	68
中心磁场/T	3.5	3.5	6.5	5.3
等离子体电流/MA	1.0	2.0	13.78	15
国家或地区	中国	韩国	中国	国际

Fig. 9 Components of ITER coil system

Fig. 10 Design diagram of CFETR device

Fig. 11 EAST device

Fig. 12 KSTAR magnet system

Tab. 3 Main information of some commercial high-temperature superconducting Tokamak devices

信息	公司名称
信息	Commonwealth Fusion Systems	Tokamak Energy	能量奇点	星环聚能
托卡马克名称	SPARC	Demo4	洪荒70	CTRFR-1
建成时间	2025年 (预计)	2024年 (预计)	2024年	2025年 (预计)
环向磁场/T	12.2	18	0.6	3~5
TF数量/个	18	14	12	16
国家	美国	英国	中国	中国

Fig. 13 Top view of TFMC

Fig. 14 Discharge demonstration of ST25(HTS)

Fig. 15 Assembly of HH 70

Fig. 16 SUNIST-2 fusion experimental device

Fig. 17 Schematic diagram of LHD

Fig. 18 W7-X stellarator device

Fig. 19 Simplified stellarator coil winding surface

Fig. 20 Concept diagram of EOS device (HTS planar coil array)

Fig. 21 Infinity One device concept diagram

Fig. 22 WHAM mirror device

Fig. 23 Trenta device

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