Title :
Concept design of CFETR Tokamak machine
Author :
Song, Yuntao ; Wu, S.T. ; Li, J.G. ; Wan, Baonian ; Wan, Yuanxi ; Fu, P. ; Ye, M.Y. ; Liu, S.M. ; Gao, X.
Author_Institution :
Inst. of Plasma Phys., Hefei, China
Abstract :
CFETR (China Fusion Engineering Test Reactor) is a tokamak reactor, one option of which is superconducting machine and under designing by China national integration design group. The fusion power was designed as 50-200 MW and its duty cycle (or burning time) was envisioned as 30-50%. The plasma current will be 10MA and its major radius and minor radius is 5.7m and 1.6 m, respectively. The concept engineering design including the magnet system, vacuum vessel system and maintenance method has been done in the past year. The center magnetic field strength on the TF magnet is 5.0 T, the maximum capacity of the volt seconds provided by center solenoid winding will be 160 VS. The main design work was carried out including the electromagnetic analysis and parameters for magnet system. In addition, the vacuum vessel system´s design and optimization based on three types of maintenance ports was discussed in this paper. What´s more, the maintenance method which is one of the most important design works was presented as detailed as possible in this paper. It includes the design of the maintenance ports and the the remote handling system design and so on. The next optimized design mainly includes the mechanical design, conductor stability and different types of divertor system design and so on.
Keywords :
Tokamak devices; fusion reactor design; fusion reactor divertors; optimisation; plasma toroidal confinement; remote handling; solenoids; superconducting machines; CFETR tokamak reactor; China Fusion Engineering Test Reactor; China national integration design group; burning time; center magnetic field strength; center solenoid winding; concept design; concept engineering design; conductor stability; current 10 MA; divertor system design; duty cycle; electromagnetic analysis; fusion power; magnet system; maintenance method; maintenance ports; mechanical design; optimization; optimized design; plasma current; power 50 MW to 200 MW; remote handling system design; size 1.6 m; size 5.7 m; superconducting machine; vacuum vessel system design; Coils; Maintenance engineering; Superconducting magnets; Tokamaks; Toroidal magnetic fields; Vacuum systems; CFETR tokamak machine; Concept design; Magnet system; Maintenance method; Vacuum vessel system;
Conference_Titel :
Fusion Engineering (SOFE), 2013 IEEE 25th Symposium on
Conference_Location :
San Francisco, CA
Print_ISBN :
978-1-4799-0169-2
DOI :
10.1109/SOFE.2013.6635362