Results 131 to 140 of about 2,258 (214)

Progress of the CFETR design

Nuclear Fusion, 2019
The Chinese Fusion Engineering Testing Reactor (CFETR), complementing the ITER facility, is aiming to demonstrate fusion energy production up to 200 MW initially and to eventually reach DEMO relevant power level 1 GW, to manifest a high duty factor of 0.3–0.5, and to pursue tritium self-sufficiency with tritium breeding ratio (TBR) >1.
G. Zhuang, G.Q. Li, J. Li, Y.X. Wan, Y. Liu, X.L. Wang, Y.T. Song, V. Chan, Q.W. Yang, B.N. Wan, X.R. Duan, P. Fu, B.J. Xiao   +12 more
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Integrated modeling of CFETR hybrid scenario plasmas

Nuclear Fusion, 2021
Abstract Demonstration of DEMO relevant fusion power (P fus) level and tritium self-sufficiency are two important goals of the China fusion engineering testing reactor (CFETR). In this work the integrated modeling including self-consistent core–pedestal coupling are used to design the hybrid scenario plasmas at flat-top
Jiale Chen, Vincent S. Chan, Xiang Jian, Xinjun Zhang, Qilong Ren, Guoqiang Li, Chengxi Zhou, null CFETR Physics Team   +7 more
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Electromagnetic Parameters Analysis of CFETR Magnets

Journal of Fusion Energy, 2015
CFETR (China Fusion Engineering Test Reactor) is a test reactor which shall be constructed by National Integration Design Group for Magnetic Confinement Fusion Reactor of China. The reactor has the equivalent scale compared with ITER, but has the complementary function to ITER.
X. F. Liu, J. X. Zheng, Z. P. Luo, S. S. Du   +3 more
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Preliminary Design of CFETR TF Prototype Coil

Journal of Fusion Energy, 2021
China fusion engineering test reactor (CFETR), based on ITER technology and bridged between ITER and DEMO, has been supported by China government to start technologies R&D and engineering design. The field of CFETR at plasma core is 6.5 T, maximum field of TF coil is about 14.8 T. TF coil is wound by Nb3Sn and NbTi CIC conductors.
Yu Wu, Jiangang Li, Guang Shen, Jinxing Zheng, Xiaogang Liu, Feng Long, Chao Dai, Xufeng Liu, Yi Shi, Junjun Li, Qiangwang Hao, Yanlan Hu, Yezheng Xiao, Wei Wen, Xiaowu Yu, Chao Fang, Jing Wei, Lina Zhu, Houxiang Han   +18 more
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Integration design platform of the CFETR

Fusion Engineering and Design, 2017
Abstract An integration design platform is built for the CFETR design. By a project lifecycle management (PLM) system, the platform could provide the function to coordinate the progress among different task groups distributed in China. The PLM system manages many kinds of documents, like the project description and scientific target, the sub-system ...
Minyou Ye, Zhongwei Wang, Shifeng Mao, Yuntao Song, Xufeng Liu, Vincent Chan, Jiangang Li   +6 more
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Accident classification and initial events for CFETR

Fusion Engineering and Design, 2021
Abstract Accident analysis is an important part of the design of nuclear power reactor. It is a necessary step of nuclear safety review and a key requirement for the reactor operation permit. In the China Fusion Engineering Test Reactor (CFETR) preliminary design, the main contents of accident analysis include two aspects: verification of CFETR ...
Bing Zhou, Xiaoyu Wang, Yanling Wang, Bo Hu, Qixiang Cao, Long Zhang, Jun Wang, Xinghua Wu   +7 more
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Concept design of CFETR Tokamak machine

2013 IEEE 25th Symposium on Fusion Engineering (SOFE), 2013
CFETR (China Fusion Engineering Test Reactor) is a tokamak reactor, one option of which is superconducting machine and under designing by China national integration design group. The fusion power was designed as 50-200 MW and its duty cycle (or burning time) was envisioned as 30-50%. The plasma current will be 10MA and its major radius and minor radius
Y. T. Song, S. T. Wu, J. G. Li, B. N. Wan, Y. X. Wan, P. Fu, M. Y. Ye, S. M. Liu, X. Gao   +8 more
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Quench Detection Design for CFETR CSMC

Fusion Science and Technology, 2018
AbstractThe Central Solenoid Model Coils (CSMC) project (2014 to 2018), a part of the National Magnetic Confinement Fusion Science Program, is being developed by China independently under one of the largest research and development activities of the China Fusion Engineering Test Reactor (CFETR), demonstrating and validating the engineering design ...
Teng Wang, Yanlan Hu, Huajun Liu, Yu Wu, Yi Shi, Chao Pan, Longgui Zheng   +6 more
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Plasma ohmic discharge simulation of CFETR

2015 IEEE 26th Symposium on Fusion Engineering (SOFE), 2015
Tokamak Simulation Code (TSC) is a numerical model of an axisymmetric free boundary tokamak plasma and the associated control systems. The time dependence of ohmic discharges of China Fusion Engineering Test Reactor (CFETR) has been simulated using TSC in this work. The TSC numerical model, CFETR device and plasma parameters are presented. According to
null Rongfei Wang, null Jinhong Yang, null Weihua Wang, null Bo Shi, null Jiajia Han   +4 more
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Concept Design of CFETR Tokamak Machine

IEEE Transactions on Plasma Science, 2014
China Fusion Engineering Test Reactor (CFETR) is a tokamak reactor; one design option under the consideration of the China National Integration Design Group employs superconducting magnets. The fusion power is at the range of 50-200 MW and the duty cycle (or burning time) was envisioned as 30%-50%.
Yun Tao Song, Song Tao Wu, Jian Gang Li, Bao Nian Wan, Yuan Xi Wan, Peng Fu, Min You Ye, Jin Xing Zheng, Kun Lu, Xianggao Gao, Su Mei Liu, Xu Feng Liu, Ming Zhun Lei, Xue Bing Peng, Yong Chen   +14 more
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