Title :
Design of the HT-7U tokamak device
Author :
Wu, S.T. ; Wu, W.Y. ; Yao, D.M. ; Chen, Z.M. ; Bi, Y.F. ; Pan, Y.N. ; Li, B.Z. ; Liao, Z.Y. ; Yu, J. ; He, Y.X. ; Song, Y.T. ; Chen, W.G. ; Wu, X.B. ; Gao, D.J. ; Ji, A.H. ; Pan, W.J. ; Wu, D. ; Chao, Y.L.
Author_Institution :
Inst. of Plasma Phys., Acad. Sinica, Hefei, China
Abstract :
The HT-7U superconducting tokamak is an advanced steady-state plasma physics experimental device to be built at the Institute of Plasma Physics, the Chinese Academy of Sciences (ASIPP). HT-7U have a long pulse (60-1000 s) capability, a flexible PF system, and auxiliary heating and current drive systems, and will be able to accommodate divertor heat loads that make it an attractive test for the development of advanced tokamak operating modes. Now, the engineering design of the HT-7U device is in progress. The engineering design incorporates the superconducting toroidal field (TF) and poloidal field (PF) magnets, the vacuum vessel, the thermal shields, the cryostat and the current leads. This paper provides an overview of the HT-7U design emphasizing developments in the device design during the past year
Keywords :
Tokamak devices; fusion reactor design; superconducting coils; superconducting magnets; vacuum apparatus; HT-7U; PF system; auxiliary heating; cryostat; current drive; current leads; design; poloidal field system; superconducting poloidal field magnet; superconducting toroidal field magnet; thermal shields; tokamak; vacuum vessel; Design engineering; Heating; Nuclear and plasma sciences; Physics; Plasma devices; Steady-state; Superconducting devices; Superconducting magnets; System testing; Tokamak devices;
Conference_Titel :
Fusion Engineering, 1999. 18th Symposium on
Conference_Location :
Albuquerque, NM
Print_ISBN :
0-7803-5829-5
DOI :
10.1109/FUSION.1999.849899
