Results 121 to 130 of about 541 (171)

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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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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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 impacts of blanket on CFETR ohmic breakdown

Fusion Engineering and Design, 2019
Abstract China Fusion Engineering Test Reactor (CFETR) design is under way, it is necessary to develop an optimized scenario for plasma breakdown and current ramp-up, and to evaluate the consequent design constraints. A good initial magnetization (IM) and volt-seconds optimization are carried out for the ohmic breakdown based on the 2D TokSys model ...
D. Chen, M.Y. Ye, Z.P. Luo, S.F. Mao, V.S. Chan, L. Liu, L. Liu   +6 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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Optimizaton of the snowflake diverted equilibria in CFETR

2013 IEEE 25th Symposium on Fusion Engineering (SOFE), 2013
The China Fusion Engineering Test Reactor (CFETR) is under conceptual design, which will be a good complementary with ITER. One of the critical issues for the long pulse or steady-state operation is how to reduce heat loads below a limitation on plasma facing components, especially on divertor plates.
Z. P. Luo, B. J. Xiao, Y. Guo, M. Y. Ye
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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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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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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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