First application of the island divertor configuration in the J-TEXT tokamak

Abstract For the first time, an island divertor configuration was successfully implemented in the J-TEXT tokamak to improve heat exhaust and impurity control. The magnetic island is generated by applying external resonant magnetic perturbation fields, and the intersection between the edge island and the divertor target is then controlled by adjusting the edge safety factor q a , thereby achieving the island divertor configuration. The overall confinement is maintained in spite of the loss of the edge volume. The island divertor configuration significantly reduces peak heat-load on the divertor target by approximately 50% and improves impurity screening. Additionally, it effectively modulates radiation around the magnetic island’s X-point, potentially enhancing the stability and control of radiative divertor operations. These findings highlight the island divertor configuration as a promising strategy for advancing heat exhaust and impurity control in tokamak operations.

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Publication Details

Journal
Nuclear Fusion
Published
2024-11-11
DOI
https://doi.org/10.1088/1741-4326/ad90f1
Citations
6
Primary Topic
Magnetic confinement fusion research
Type
article
Field-Weighted Citation Impact
3.30

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First application of the island divertor configuration in the J-TEXT tokamak

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Nuclear Fusion
Magnetic confinement fusion research
3.30
article

First application of the island divertor configuration in the J-TEXT tokamak

Jiankun Hua, Wei Yan, Nengchao Wang, S. Xu, Yonghua Ding, Zhoujun Yang, Zeran Hou, Zhongyong Chen, Song Zhou, Y.B. Li, X.Y. Zhang, Y. Liang, Qinghu Yang, Da Li, A. Knieps, Feiyue Mao, Zhonghe Jiang, Zhipeng Chen, Junjie Yang, Xuelin Zhang, Yun-Xia Yang
article en
6 citations

Abstract

Abstract For the first time, an island divertor configuration was successfully implemented in the J-TEXT tokamak to improve heat exhaust and impurity control. The magnetic island is generated by applying external resonant magnetic perturbation fields, and the intersection between the edge island and the divertor target is then controlled by adjusting the edge safety factor q a , thereby achieving the island divertor configuration. The overall confinement is maintained in spite of the loss of the edge volume. The island divertor configuration significantly reduces peak heat-load on the divertor target by approximately 50% and improves impurity screening. Additionally, it effectively modulates radiation around the magnetic island’s X-point, potentially enhancing the stability and control of radiative divertor operations. These findings highlight the island divertor configuration as a promising strategy for advancing heat exhaust and impurity control in tokamak operations.

Nuclear FusionVol. 65(1)
Forschungszentrum Jülich (DE), Chinese Academy of Sciences (CN), Institute of Plasma Physics (CN), Southwestern Institute of Physics (CN), Huazhong University of Science and Technology (CN)
National Natural Science Foundation of China
Openalex Percentile: Top 6%
Magnetic confinement fusion research
3.30
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