EAST plasma control system
EAST plasma control system
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DOI：
10.1016/j.fusengdes.2007.12.028
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发表时间：
2008-04
影响因子：
1.7
通讯作者：
B. Xiao;D. Humphreys;M. Walker;A. Hyatt;J. Leuer;D. Mueller;B. Penaflor;D. A. Pigrowski;
中科院分区：
文献类型：
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作者：
B. Xiao;D. Humphreys;M. Walker;A. Hyatt;J. Leuer;D. Mueller;B. Penaflor;D. A. Pigrowski;
实验性先进超导托卡马克（EAST）是第一个具有类似 ITER 的全超导极向和环形线圈的托卡马克，于 2006 年 3 月成功完成了工程调试； 2006 年 9 月获得了第一批血浆 [B.N. Wan等人，EAST的第一个等离子体，于：第21届国际原子能机构聚变能源会议，中国成都，2007年10月16-21日。[1]]并于2007年1月进一步产生转向等离子体。等离子体控制系统改编自DIII-D等离子体控制系统架构，由DIII-D和EAST等离子体控制团队联合开发。本文简要概述了EAST等离子体控制系统的硬件和软件架构，总结了首次等离子体和首次转移等离子体活动中的等离子体控制结果。
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.