托卡马克
分流器
螺线管
核工程
聚变能
超导磁体
磁铁
占空比
计算机科学
电磁线圈
机械工程
电气工程
物理
等离子体
工程类
核物理学
电压
作者
Yongxian Song,Shan Wu,Jian Gang Li,Bao Nian Wan,Yuan Wan,Peng Fu,Min You Ye,Jinxing Zheng,Kun Lü,Xianggao Gao,Su Mei Liu,Xu Feng Liu,Lei Ming,X.B. Peng,Yong Chen
出处
期刊:IEEE Transactions on Plasma Science
[Institute of Electrical and Electronics Engineers]
日期:2014-03-01
卷期号:42 (3): 503-509
被引量:311
标识
DOI:10.1109/tps.2014.2299277
摘要
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%. The plasma current will be 10 MA and the major and minor radii are 5.7 and 1.6 m, respectively. The concept engineering design including the magnet system, vacuum vessel (VV) system, and maintenance method has been carried out in the past years. The toroidal magnetic field strength at $R_{0}$ is 5 T and the maximum flux swing provided by central solenoid winding will be 160 VS. The main design work, including the electromagnetic analysis of the magnet system, has already been carried out. This paper mainly probes into the VV design and optimization based on three types of maintenance ports. Furthermore, the maintenance method, counted as one of the most important design studies, is presented specifically in this paper. It includes the design of the maintenance ports and the remote handling system design, and so on. The next design stage will mainly include mechanical design, conductor stability, different types of divertor system design, and so on.
科研通智能强力驱动
Strongly Powered by AbleSci AI