Zobrazeno 1 - 10
of 60
pro vyhledávání: '"Kun Lu"'
Publikováno v:
Fusion Science and Technology. 78:676-682
Publikováno v:
Annals of Nuclear Energy. 188:109802
Autor:
Yilin Chang, Xiangwei Zhu, Yanan Shi, Yanan Liu, Ke Meng, Yanxun Li, Jingwei Xue, Lingyun Zhu, Jianqi Zhang, Huiqiong Zhou, Wei Ma, Zhixiang Wei, Kun Lu
Publikováno v:
Energy & Environmental Science. 15:2937-2947
Siloxane with low surface tension can regulate the intermolecular interactions, and optimize the phase separation morphology and molecule stacking, finally contributing to an excellent PCE of 16.4% with small energy loss for ASM-OSCs.
Autor:
Mingzhun Lei, Weibin Xi, Yuntao Song, Songtao Wu, Jing Pan, Xufeng Liu, Kun Lu, Weiwei Xu, Jing Wei
Publikováno v:
Fusion Science and Technology. 77:477-488
The evaluation of electromagnetic (EM) loads acting on conductive structures is one of the critical problems for tokamaks. This paper focuses on the main conductive components of the Chinese Fusion...
Autor:
Shanshuang Shi, Dongyi Li, Wenlong Zhao, Kun Lu, Zhang Yu, Junwei Li, Yang Songzhu, Yong Cheng
Publikováno v:
Nuclear Engineering and Technology. 52:2630-2637
The structure design of divertor Multi-Functional Maintenance Platform (MFMP) actuated by hydraulic system for China Fusion Engineering Test Reactor (CFETR) was introduced in this paper. The model of MFMP was established according to maintenance requ
Autor:
Yue Xu, Kun Lu, Guang Shen, Bing Hu, Feng Cheng, Chao Mo, Mengyuan Zhang, Yanyu Xie, Chenglian Liu
Publikováno v:
Annals of Nuclear Energy. 178:109336
Autor:
Xinpeng Guo, Kun Lu, Yong Cheng, Wenlong Zhao, Huapeng Wu, Dongyi Li, Junwei Li, Songzhu Yang, Yu Zhang
Publikováno v:
Fusion Engineering and Design. 185:113321
Autor:
Kaizhong Ding, Chenglian Liu, Chao Wang, Zheng Gong, N. Clayton, Erwu Niu, R. Piccin, Jun Wang, Liu Chen, Tingzhi Zhou, Xiongyi Huang, Kun Lu, P. Bauer, Chen-yu Gung, Yuntao Song, Linlin Fang, Guoliang Li, Zhiheng Dai
Publikováno v:
Fusion Engineering and Design. 146:955-958
The ITER high temperature superconducting current lead is a critical component for the magnet system, which has the benefit of reduction in the heat load of the cryogenic system compare with the conventional lead. The current lead is located in the c
Publikováno v:
Fusion Engineering and Design. 146:1192-1197
China Fusion Engineering Test Reactor (CFETR), the next fusion device in China, is proposed to bridge the gaps between ITER and the demonstration reactor (DEMO). The Water Cooled Ceramic Breeder (WCCB) blanket, one candidate option of breeding blanke
Autor:
Yong Cheng, Yuntao Song, Huibin Sun, Jiangang Li, Huapeng Wu, Xiaodong Lin, Xiang Gao, Kun Lu, Jianjun Huang, Gong Zheng, Wenlong Zhao
Publikováno v:
Fusion Engineering and Design. 146:2777-2780
China Fusion Engineering Testing Reactor (CFETR) will be built to test and verify the feasibility of engineering and technology in practice for the future fusion reactor. Long pulse and steady-state operation will be demonstrated with duty cycle time