Jinchao Li
Chinese Academy of Sciences
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Publication
Featured researches published by Jinchao Li.
IEEE Transactions on Plasma Science | 2016
Zhiquan Song; Peng Fu; Jinchao Li; Peng Wang; Xiuqing Zhang; Chuan Li; Yong Yang; Ling Dong
This paper presents the design and testing of the full scale prototype of the international thermonuclear experimental reactor (ITER) poloidial field converter unit (PFCU), which is mainly composed of converter transformer, converter module, external bypass, and dc reactors with a rated capacity of 82 MVA and a rated dc current of 55 kA. Considering the space limitation, the high safety and reliability requirements, the nonsame-phase antiparallel connection structure, and the fault suppression capability criterion are applied in the prototype design. After the completion of the preliminary design of the PFCU in summer 2012, the detailed prototype structure design and the manufacturing of the PFCU were launched and completed at the end of 2013, then the following main type tests, including short circuit current test and temperature rise test on the main components of the PFCU, have been done on the ITER power supply test platform at ASIPP site. In addition, the PFCU integration test has also been done to verify the system operation performance. The prototype test results are well in compliance with the design requirements of the ITER PF converter system. It indicates that the full scale prototype research and development of PFCU has been accomplished successfully.
ieee symposium on fusion engineering | 2015
Zhiquan Song; Peng Fu; George F. Gao; Liuwei Xu; Jinchao Li; Peng Wang; Xiuqing Zhang; Chuan Li; Yong Yang; L. Dong; M. Wang; T. Z. Fang
This paper presents the design, manufacturing and testing of the full scale prototype of the ITER Polodial Field Converter Unit (PFCU) for the coil power supply system of the ITER superconducting Tokamak. The PFCU is mainly composed of converter transformer, converter module, external bypass and dc reactors with a rated capacity of 82 MVA and a rated dc current of 55 kA, which is also required for the Fault Suppression Capability (FSC) criterion. After the completion of the preliminary design of the PF converter package in summer 2012, the detailed prototype structure design, manufacture of the PFCU were launched and completed at the end of 2013. Then the following main type tests, including short circuit current test and temperature rise test on the main components of the PFCU, have been done on the ITER power supply test platform at ASIPP site and are described in this paper. And the PFCU integration test has also been done to verify the system operation performance. The prototype test results are well in compliance with the design. It indicates that the full scale prototype of PFCU can fully meet the design requirements of ITER PF converter system.
Plasma Science & Technology | 2014
Jinchao Li; Liuwei Xu; Zhiquan Song; Peng Fu; Bin Guo; Sen Li; Lin Dong; Min Wang
The design of high current balance reactors used in the ITER DC testing platform is presented, which is verified by simulations with finite element method software, and the reactors are fabricated and tested according to the design output. These reactors are chosen as multilayer multi-turn structure and cooled by water. The multilayer multi-turn structure is usually selected by some high voltage reactors, but is seldom used in high current situations. The analysis and testing results indicate that the multilayer multi-turn structure is also feasible for high current reactors with many advantages, and is of considerable significance to similar applications.
Plasma Science & Technology | 2004
K. Toi; S. Ohdachi; Satoshi Yamamoto; S. Sakakibara; K Y Watanabe; N Nakajima; X Ding; Jinchao Li; S. Morita; K. Narihara; K. Tanaka; T. Tokuzawa; H. Yamada; Q Yang
MHD stability of the Large Helical Device (LHD) plasmas produced with intense neutral beam injection is experimentally studied. When the steep pressure gradient near the edge is produced through L-H transition or linear density ramp experiment, interchange-like MHD modes whose rational surface is located very close to the last closed flux surface are strongly excited in a certain discharge condition and affect the plasma transport appreciably. In NBI-heated plasmas produced at low toroidal field, various Alfven eigenmodes are often excited. Bursting toroidal Alfven egenmodes excited by the presence of energetic ions induce appreciable amount of energetic ion loss, but also trigger the formation of internal and edge transport barriers.
Journal of Fusion Energy | 2015
Yuanxu Liao; Zhiquan Song; Ge Gao; Jinchao Li; Peng Fu; Chuan Li; Jie Zhang
Journal of Fusion Energy | 2015
Peng Wang; Peng Fu; Zhiquan Song; Jinchao Li; Lin Dong; Min Wang; Tongzhen Fan
Journal of Fusion Energy | 2015
Zhiquan Song; Jinchao Li; Peng Fu; Sen Li; Lin Dong; Min Wang; Tongzhen Fang
Journal of Fusion Energy | 2015
Peng Wang; Zhiquan Song; Peng Fu; Jinchao Li; Chuan Li; Lin Dong; Min Wang; Tongzhen Fan
Archive | 2012
Jinchao Li; Peng Fu; Zhiquan Song; Zhiyun Zheng; Haitao Cao
Journal of Fusion Energy | 2016
Fan Kuang; Zhiquan Song; Meng Mao; Jinchao Li; Peng Fu; Chuan Li; Yong Yang