Results 131 to 140 of about 495 (172)

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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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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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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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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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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Conceptual design and analysis of CFETR magnets

2013 IEEE 25th Symposium on Fusion Engineering (SOFE), 2013
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.
Xufeng Liu, Jinxing Zheng, Zhengping Luo, Shuangsong Du, Sumei Liu, Yuntao Song, Yuanxi Wan, Minyou Ye   +7 more
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Optimization of the gravity support in CFETR vacuum vessel

Fusion Engineering and Design, 2021
Abstract The China Fusion Engineering Test Reactor (CFETR) is developed as the next tokamak device in China. The gravity support of CFETR VV is designed with a flexible plate structure to allow radial thermal expansion of the vacuum vessel (VV) system and to withstand various design loads.
Xiaojun Ni, Songbo Han, Jian Ge, Jinxin Sun   +3 more
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Development of system code of CFETR design

2015 IEEE 26th Symposium on Fusion Engineering (SOFE), 2015
China Fusion Engineering Test Reactor (CFETR) is now in the conceptual design phase. The main objective of CFETR is demonstration of fusion energy with 50 ∼ 200 MW fusion power, fuel cycle of T self-sustained and steady-state operation with duty cycle of 0.3 ∼ 0.5.
M.Y. Ye, S. J. Wang, Z. W. Wang, G.L. Xu, X.F. Liu, J.W. Zhang, S. F. Mao, V.S. Chan   +7 more
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A ride-through power structure for CFETR

IEEE Transactions on Dielectrics and Electrical Insulation, 2015
The China fusion engineering test reactor (CFETR) is an ITER-like tokamak system for fusion energy development. It could output 50-200 MW fusion power in phase I for demonstrating power generation with complete structure of fusion power plant, and 1 GW output power can be expected in phase II.
Hua Li, Ge Li, Lu Qu, Peng Fu, Ying Wang, Qiangjian Chen   +5 more
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Concept design of the CFETR central solenoid

Fusion Engineering and Design, 2015
Abstract China Fusion Engineering Test Reactor (CFETR) superconducting tokamak is a national scientific research project of China with major and minor radius is 5.7 m and 1.6 m respectively. The magnetic field at the center of plasma with radius as R = 5.7 m is set to be 5.0 T.
Jinxing Zheng, Yuntao Song, Xufeng Liu, Jiangang Li, Yuanxi Wan, Baonian Wan, Minyou Ye, Huan Wu   +7 more
openaire   +1 more source