Recent advance progress of HL-3 experiments

Abstract Since the first plasma realized in 2020, a series of key systems on HL-3 (known as HL-2M before) tokamak have been equipped/upgraded, including in-vessel components (the first wall, lower divertor, and toroidal cryogenic/water-cooling/baking/glow discharge systems, etc.), auxiliary heating system of 11 MW, and 28 diagnostic systems (to measure the plasma density, electron temperature, radiation, magnetic field, etc.). Magnet field systems were commissioned firstly for divertor plasma discharges. During the 2nd experimental campaign of HL-3 tokamak, several great progresses have been achieved. Firstly, the successful operation with plasma current larger than 1 MA was achieved under a divertor configuration. Secondly, the advanced divertor concept with two distinct snowflake configurations was realized. It is found that the distribution of ion saturation current and heat flux on bottom plate becomes wide due to magnetic surface expansion, demonstrating the advantage of such configuration in the heat flux mitigation. In addition, using the combination of NBI, ECRH and LHCD, the standard sawtoothing high confinement mode of megampere plasma was firstly accessed on the HL-3. The successful commissioning of HL-3 is beneficial for the initial operation of ITER.

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Publication Details

Journal
Nuclear Fusion
Published
2024-08-13
DOI
https://doi.org/10.1088/1741-4326/ad6e9e
Citations
25
Primary Topic
Magnetic confinement fusion research
Type
article
Field-Weighted Citation Impact
16.49

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article

Recent advance progress of HL-3 experiments

Xianglei Liu, Y. P. Zhang, Jinming Gao, X.R. Duan et al.
25 citations
Nuclear Fusion
Magnetic confinement fusion research
16.49
article

Recent advance progress of HL-3 experiments

Xianglei Liu, Y. P. Zhang, Jinming Gao, X.R. Duan, D. Q. Liu, M. Jiang, Z.B. Shi, Zhe Yang, Y. Q. Wang, W.L. Zhong, Guoliang Xiao, Ruihai Tong, D.L. Yu, Z. Cao, Yongjie Zhang, B. Li, Peng Shi, Hui-Ling Wei, A.S. Liang, Y. H. Chen, Wei Chen, Yong Liu, Jiquan Li, T.F. Sun, Rui Ke, X. L. Zhang, Xiao Ji, Linfeng Lu, G.Q. Dong, Haoyu Li, Y Liu, Shuo Wang, Xue Bai, M. Xu, Guangzhou Hao, Yongge Li, L.W. Yan, Ting Long, Liming Yu, Xiaobing Zheng, Long Zhang, Feng Zhang, Jingchao Li, Haotian Chen, Xiaomei Chen, Qing Li, Hongbing Xu, Zheng Guo, Lijun Cai, Junkun Peng, Lei Xue, L. Nie, X. P. Xiao, Shaofei Geng, Weibing Li, Qiang Yang, Hong Du, He Hongming, L. C. Li, Dongmei FAN, Bo Lü, M. Huang, A.P. Sun
article en
25 citations

Abstract

Abstract Since the first plasma realized in 2020, a series of key systems on HL-3 (known as HL-2M before) tokamak have been equipped/upgraded, including in-vessel components (the first wall, lower divertor, and toroidal cryogenic/water-cooling/baking/glow discharge systems, etc.), auxiliary heating system of 11 MW, and 28 diagnostic systems (to measure the plasma density, electron temperature, radiation, magnetic field, etc.). Magnet field systems were commissioned firstly for divertor plasma discharges. During the 2nd experimental campaign of HL-3 tokamak, several great progresses have been achieved. Firstly, the successful operation with plasma current larger than 1 MA was achieved under a divertor configuration. Secondly, the advanced divertor concept with two distinct snowflake configurations was realized. It is found that the distribution of ion saturation current and heat flux on bottom plate becomes wide due to magnetic surface expansion, demonstrating the advantage of such configuration in the heat flux mitigation. In addition, using the combination of NBI, ECRH and LHCD, the standard sawtoothing high confinement mode of megampere plasma was firstly accessed on the HL-3. The successful commissioning of HL-3 is beneficial for the initial operation of ITER.

Nuclear FusionVol. 64(11)
Southwestern Institute of Physics (CN)
University of Wisconsin-Madison, Durham University, Dalian University of Technology, Huazhong University of Science and Technology, Harbin Institute of Technology, Tsinghua University, Zhejiang University, Peking University, University of South China, University of California, San Diego, Princeton Plasma Physics Laboratory
Openalex Percentile: Top 0%
Magnetic confinement fusion research
16.49
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