NDLI: Concept Design of CFETR Tokamak Machine

Content Provider	IEEE Xplore Digital Library
Author	Yun Tao Song Song Tao Wu Jian Gang Li Bao Nian Wan Yuan Xi Wan Peng Fu Min You Ye Jin Xing Zheng Kun Lu Xianggao Gao Su Mei Liu Xu Feng Liu Ming Zhun Lei Xue Bing Peng Yong Chen
Copyright Year	1973
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.
Sponsorship	IEEE Nuclear and Plasma Sciences Society
Starting Page	503
Ending Page	509
Page Count	7
File Size	5022223
File Format	PDF
ISSN	00933813
Volume Number	42
Issue Number	3
Language	English
Publisher	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Publisher Date	2014-01-01
Publisher Place	U.S.A.
Access Restriction	One Nation One Subscription (ONOS)
Rights Holder	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Subject Keyword	Coils Superconducting magnets Toroidal magnetic fields Maintenance engineering Windings Tokamaks vacuum vessel (VV) system China Fusion Engineering Test Reactor (CFETR) tokamak machine concept design magnet system maintenance method
Content Type	Text
Resource Type	Article
Subject	Nuclear and High Energy Physics Condensed Matter Physics

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