DocumentCode
3130784
Title
The R&D progress of the EAST (HT-7U) superconducting tokamak
Author
Wu, S.T. ; Wu, W.Y. ; Pan, Y.N. ; Yao, D.M. ; Liao, Z.Y. ; Yu, J. ; Li, B.Z. ; Chen, Z.M. ; Pan, W.J. ; Song, Y.T. ; Chen, W.G. ; Wei, J. ; Weng, P.D. ; Gao, D.M. ; Wan, Y.X. ; Li, J.G.
Author_Institution
Inst. of Plasma Phys., Chinese Acad. of Sci., Beijing, China
fYear
2003
fDate
14-17 Oct. 2003
Firstpage
646
Lastpage
651
Abstract
The superconducting tokamak project HT-7U, aiming at steady-state advanced operation mode, will make a contribution to future steady-state tokamak reactors. The scientific and the engineering missions of the project are to study physics issues of the steady-state tokamak operation and to establish technology basis of full superconducting tokamaks. It features: superconducting toroidal field system and poloidal field system, non-inductive current drive and plasma heating systems, flexibility and reliability of plasma shaping control, J(r) and P(r) control, replaceability of plasma facing components and divertors for power and particle handling study in steady-state operation and advanced diagnostic measurements. The physics design and the engineering design have been completed essentially. The key R&D programs of the tokamak device have been successful. The assembly of the device has begun. It is planned to obtain the first plasma in 2005.
Keywords
Tokamak devices; fusion reactor design; fusion reactor divertors; fusion reactor operation; physical instrumentation control; plasma diagnostics; plasma heating; plasma instability; plasma toroidal confinement; plasma transport processes; superconducting magnets; EAST superconducting tokamak; HT-7U superconducting tokamak project; R&D progress; advanced diagnostic measurements; divertors; engineering design; flexibility; noninductive current drive; physics design; plasma facing components; plasma heating systems; plasma shaping control; reliability; steady-state advanced operation mode; steady-state tokamak reactors; superconducting poloidal field system; superconducting toroidal field system; tokamak device; Physics; Plasma devices; Plasma diagnostics; Plasma measurements; Power system reliability; Reliability engineering; Research and development; Shape control; Steady-state; Tokamaks;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on
Print_ISBN
0-7803-7908-X
Type
conf
DOI
10.1109/FUSION.2003.1426729
Filename
1426729
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