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Concept Design of CFETR Tokamak Machine.

Authors :
Song, Yun Tao
Wu, Song Tao
Li, Jian Gang
Wan, Bao Nian
Wan, Yuan Xi
Fu, Peng
Ye, Min You
Zheng, Jin Xing
Lu, Kun
Gao, Xianggao
Liu, Su Mei
Liu, Xu Feng
Lei, Ming Zhun
Peng, Xue Bing
Chen, Yong
Source :
IEEE Transactions on Plasma Science. Mar2014 Part 1, Vol. 42 Issue 3, p503-509. 7p.
Publication Year :
2014

Abstract

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 R0 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. [ABSTRACT FROM PUBLISHER]

Details

Language :
English
ISSN :
00933813
Volume :
42
Issue :
3
Database :
Academic Search Index
Journal :
IEEE Transactions on Plasma Science
Publication Type :
Academic Journal
Accession number :
94892160
Full Text :
https://doi.org/10.1109/TPS.2014.2299277