4.5 Article Proceedings Paper

EAST plasma control system

Journal

FUSION ENGINEERING AND DESIGN
Volume 83, Issue 2-3, Pages 181-187

Publisher

ELSEVIER SCIENCE SA
DOI: 10.1016/j.fusengdes.2007.12.028

Keywords

plamsa control; tokamak; diverted plasma; EAST

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Experimental advanced superconducting tokamak (EAST), the first tokomak with ITER-like fully superconductive poloidal and toroidal coils, successfully completed its engineering commission in March 2006; had its first plasma in September 2006 [B.N. Wan, et al., The first plasma of EAST, in: 21st IAEA Fusion Energy Conference, Chengdu, China, 16-21 October, 2007. [1]] and further generated diverted plasma in January 2007. The plasma control system was adapted from DIII-D plasma control system architecture and jointly developed by the DIII-D and EAST plasma control team. After briefly outlining the hardware and software architecture of the EAST plasma control system, this paper summarizes the plasma control results in the first plasma and first diverted plasma campaigns. (c) 2008 Elsevier B.V. All rights reserved.

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