Results 151 to 160 of about 2,258 (214)

EAST contributions to closing CFETR physics gaps

2015 IEEE 26th Symposium on Fusion Engineering (SOFE), 2015
Gaps remain in physics and engineering for CFETR design. This report will focus on the high performance long pulse/steady-state operation and the power exhausting issues. The possible operation windows for designed CFETR plasma to achieve its goal and related challenge are presented.
Siye Ding, Baonian Wan, Liang Wang, null Youwen Sun   +3 more
openaire   +1 more source

The Structural Design of a CFETR Divertor IT with RH Compatibility

Fusion science and technology
A single divertor module is generally composed of an inner target (IT), a dome, an outer target (OT), and a cassette for a tokamak fusion reactor. As the plasma-facing components (PFCs), the IT, dome and OT are highly likely to be destroyed, while the ...
Xin Mao, Xuebing Peng, Peng Liu, Siqing Feng, Wei Song, Xinyuan Qian, Tiejun Xu   +6 more
semanticscholar   +1 more source

Reverse Engineering of CFETR Vacuum Vessel Mockup

IEEE Transactions on Plasma Science, 2018
The 1/32 subsector of China Fusion Engineering Test Reactor vacuum vessel mockup is fully penetration welded together with four poloidal segments (PSs) which are made by forming and welding, so that each PS needs to machine the welding grooves. However, the measurement results show that there are dimensional errors between the design model and each PS ...
Haibiao Ji, Yongqi Gu, Jiefeng Wu, Zhihong Liu, Xiaosong Fan, Jianguo Ma, Xiaowei Xia   +6 more
openaire   +1 more source

Preliminary analysis of typical accidents of CFETR helium-cooled solid breeder blanket system based on COSINE

Kerntechnik
Blankets are an important component of fusion reactors and the key object of thermal design and safety analysis. The helium-cooled solid breeder (HCSB) blanket is one of the three candidate tritium breeding blanket concepts for the Chinese Fusion ...
Zhenze Zhang, Tianze Bai, Changhong Peng, Yifei Wang, Bin Luo   +4 more
semanticscholar   +1 more source

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
openaire   +1 more source

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
openaire   +1 more source

Quasi-optical layout design of the ECRH equatorial launcher prototype towards the CFETR

International Conference on Precision Instruments and Optical Engineering
The China Fusion Engineering Test Reactor (CFETR) is the proposed next-generation fusion facility in China. Currently, the crucial technology validation work for CFETR is in process.
Chao Zhang, Dingzhen Li, Yunying Tang, Xiaojie Wang   +3 more
semanticscholar   +1 more source

An Accident Diagnosis Method of CFETR Water-Cooled Blanket Based on Deep Neural Network

IEEE Transactions on Plasma Science
The accident diagnosis of fusion blanket is one of the important issues of fusion reactor safety. In this study, the water-cooled blanket system of China Fusion Engineering Test Reactor (CFETR) is modeled using the RELAP5 code.
Tianze Bai, Changhong Peng
semanticscholar   +1 more source

Physical design of electron dumps for the beamline of CFETR advance neutral beam equipment (CANBE)

Plasma Science and Technology
Negative-ion-based neutral beam injection (NNBI) at high energy is still a potential heating and current drive method for future large-scale fusion reactors.
Yuwen Yang, Bin Li, Jianglong Wei, Lizheng Liang, Yahong Xie, Chundong Hu   +5 more
semanticscholar   +1 more source

Evaluation of the fusion power via beam-target reaction on EAST and CFETR

Plasma Science and Technology
This study quantifies deuterium-tritium (D-T) fusion power contributions from beam-target reactions in the EAST and CFETR tokamaks, providing support for the planned trace tritium experiments on EAST.
Jiarong Wu, Guosheng Xu, Dehong Chen, Fujia Wang, Baonian Wan   +4 more
semanticscholar   +1 more source