DocumentCode
67755
Title
Concept Design of CFETR Tokamak Machine
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
Author_Institution
Inst. of Plasma Phys., Hefei, China
Volume
42
Issue
3
fYear
2014
fDate
Mar-14
Firstpage
503
Lastpage
509
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.
Keywords
Tokamak devices; fusion reactor design; fusion reactor divertors; plasma toroidal confinement; CFETR tokamak machine; China Fusion Engineering Test Reactor; China National Integration Design Group; central solenoid winding; concept engineering design; conductor stability; current 10 MA; divertor system design; duty cycle; electromagnetic analysis; fusion power; magnet system; mechanical design; plasma current; power 50 MW to 200 MW; superconducting magnets; toroidal magnetic field strength; vacuum vessel system; Coils; Maintenance engineering; Superconducting magnets; Tokamaks; Toroidal magnetic fields; Windings; China Fusion Engineering Test Reactor (CFETR) tokamak machine; concept design; magnet system; maintenance method; vacuum vessel (VV) system;
fLanguage
English
Journal_Title
Plasma Science, IEEE Transactions on
Publisher
ieee
ISSN
0093-3813
Type
jour
DOI
10.1109/TPS.2014.2299277
Filename
6716984
Link To Document