Results 121 to 130 of about 495 (172)

Physics of CFETR

2013 IEEE 25th Symposium on Fusion Engineering (SOFE), 2013
CFETR based on the tokamak approach with superconducting magnet technology is envisioned to provide 200 MW fusion power and operate with a goal of an annual duty factor of 0.3~0.5. This report based on a zero-dimensional system study using extrapolations of current physics by considering engineering constraints, is focused on qualitative determination ...
Baonian Wan, Siye Ding, Jinping Qian, Guoqiang Li, Bingjia Xiao, Guosheng Xu   +5 more
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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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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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The Reliability Design of CFETR Divertor

IEEE Transactions on Plasma Science, 2018
The steady state with duty cycle time 0.3–0.5 of Chinese fusion engineering testing reactor (CFETR) is a big challenge. To realize this goal, the divertor should be reliable. At the preconceptual phase of CFETR design, reliability engineering is engaged to determine how reliable of divertor is and how much level of reliability of divertor should be ...
Lei Cao, Zibo Zhou, Pengfei Zi, Damao Yao   +3 more
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Engineering conceptual design of CFETR divertor

Fusion Engineering and Design, 2015
Abstract The China Fusion Engineering Test Reactor (CFETR), which is in conceptual design phase, aims at producing fusion power of 50–200 MW with tritium breeding ratio of ∼1.2 and duty cycle time of 0.3–0.5. Its designed main parameters are major/minor radii of 5.7 m/1.6 m and plasma current of 10 MA.
Xuebing Peng, Minyou Ye, Yuntao Song, Xin Mao, Peiming Chen, Xinyuan Qian   +5 more
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Overview of the present progress and activities on the CFETR

Nuclear Fusion, 2017
The China Fusion Engineering Test Reactor (CFETR) is the next device in the roadmap for the realization of fusion energy in China, which aims to bridge the gaps between the fusion experimental reactor ITER and the demonstration reactor (DEMO). CFETR will be operated in two phases.
Yuanxi Wan, Jiangang Li, Yong Liu, Xiaolin Wang, Vincent Chan, Changan Chen, Xuru Duan, Peng Fu, Xiang Gao, Kaiming Feng, Songlin Liu, Yuntao Song, Peide Weng, Baonian Wan, Farong Wan, Heyi Wang, Songtao Wu, Minyou Ye, Qingwei Yang, Guoyao Zheng, Ge Zhuang, Qiang Li   +21 more
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Formation of snowflake diverted equilibria of CFETR

Fusion Engineering and Design, 2017
Abstract The Chinese Fusion Engineering Test Reactor (CFETR), a next-generation fully superconducting fusion reactor, is in the design stages. In this paper, we present three snowflake (SF) divertor configurations (SF+, exact SF, SF−), to demonstrate the possibility of attaining these SF configurations with two special additional poloidal-field (PF ...
H. Li, G.Q. Li, Z.P. Luo, D.M. Yao, Y. Guo, X. Gao   +5 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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Optimization design for plasma configuration at the CFETR

Fusion Engineering and Design, 2020
Abstract Equilibrium is essential in the design of the Chinese Fusion Engineering Test Reactor (CFETR). It is based on the principle underlying various physical and engineering issues, such as vertical instability, core plasma physics, divertor physics and design, etc.
H. Li, G.Q. Li, X.J. Liu, J.P. Qian, Y. Huang, Z.P. Luo, Y. Guo, X.F. Liu, L. Liu, J.X. Zheng, S.L. Liu, X. Gao   +11 more
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The effect of triangularity on predicted pedestals for the CFETR

Physics of Plasmas, 2023
In this work, the dominant unstable magnetohydrodynamic mode and its stable region in the pedestal of the China Fusion Engineering Test Reactor are studied by numerical modeling with the peeling-ballooning theory over a wide range of triangularities (δ) and collisionalities (υ*). A new accessible stable region is found at δ<−0.1 for large βN,ped
Cheng-Xi Zhou, Vincent Chan, Jia-Le Chen, Yi-Ren Zhu, Xiang Jian, Ge Zhuang   +5 more
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