【作者】 邢哲； 肖炳甲； 钱金平； 陈树亮；

【Author】 Xing Zhe,Xiao Bingjia,Qian Jinping,Chen Shuliang Institute of Plasma Physics,Chinese Academy of Sciences,Hefei 230031,China

【机构】 中国科学院等离子体物理研究所；

【摘要】 在托卡马克装置的运行实验中,我们需要测定等离子体电流重心位移量米反馈控制垂直场线圈的电流。本文基于HT-7装置等离子体外部磁场测量结果估算出等离子体电流重心位置,并与之前HT-7实验中使用的垂直场线圈电流的控制变量进行比较,得到比后者更准确合理的结果。更多还原

【Abstract】 During the tokamak discharge experiments,we need to determine the coordinate values of plasma current center which are the control variable for the feedback control of vertical field coil current.In this paper,we multiply the external magnetic measurement with the constant coefficient matrix(E-matrix) to estimate the plasma current center on HT-7.After comparison,we acquire the more accurate and reasonable results than the previous quantity which is used as the control variable for vertical field coil current control.更多还原