Results 141 to 150 of about 541 (171)

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
openaire   +1 more source

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

Progress in the Electromagnetic Optimization of the Cfetr Cs Coil

Fusion Engineering and Design, 2023
Lijuan Yu, Xiaogang Liu, Xiang Gao, Fan Wu, Jiandong Zhu, Dongquan Wang, Shenghua Hong, Long Zeng, Jiangang Li   +8 more
openaire   +1 more source

Neutronics analyses of COOL blanket for CFETR

Fusion Engineering and Design, 2022
Qiuran Wu, Peng Lu, Xiaokang Zhang, Lei Chen, Songlin Liu   +4 more
openaire   +1 more source

Seismic Analysis of the Vacuum Vessel for CFETR

Fusion Science and Technology, 2022
Xiaojun Ni, Songbo Han, Jian Ge, Jinxin Sun   +3 more
openaire   +1 more source

A Possible Shielding Blanket Module for CFETR Reactor

Journal of Fusion Energy, 2015
The basic function of shielding blanket (SB) is to provide the main thermal and nuclear shielding to the vessel and external machine components. CFETR SB modules will be operated in steady mode with continuous neutron radiation and heat source. The SB module is currently operated in pulse mode, which indicates the SB module for CFETR should be designed
Hao Yang, Jie Zhang, Lei Li, Yang Qiu, Changle Liu, Damao Yao   +5 more
openaire   +1 more source

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

Qualification activities of the spliced joint for CFETR

Annals of Nuclear Energy, 2022
Yue Xu, Kun Lu, Guang Shen, Bing Hu, Feng Cheng, Chao Mo, Mengyuan Zhang, Yanyu Xie, Chenglian Liu   +8 more
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Design status of the ECRH system for CFETR

Fusion Engineering and Design, 2022
Yunying Tang, Xiaojie Wang, Liyuan Zhang, Chao Zhang, Hanlin Wang, Wei Wei, Dajun Wu, Huaichuan Hu, Fukun Liu   +8 more
openaire   +1 more source

Activation analysis and radwaste assessment of CFETR

Fusion Engineering and Design, 2022
Xiaokang Zhang, Qiuran Wu, Hua Du, Yu Zheng, Peng Lu, Songlin Liu   +5 more
openaire   +1 more source