Development of plasma control system for divertor configuration on QUEST
Development of plasma control system for divertor configuration on QUEST
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开发用于 QUEST 偏滤器配置的等离子控制系统
DOI：
10.1016/j.fusengdes.2013.03.035
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发表时间：
2013
影响因子：
1.7
通讯作者：
A. Higashijima
中科院分区：
文献类型：
--
作者：
M. Hasegawa;K. Nakamura;H. Zushi;K. Hanada;A. Fujisawa;K. Matsuoka;O. Mitarai;H. Idei;Y. Nagashima;K. Tokunaga;S. Kawasaki;H. Nakashima;A. Higashijima
在衢州大学稳态球形托卡马克实验上研制了一套等离子体控制系统。磁通量在100千赫使用FPGA（现场可编程门阵列）模块进行数值集成，并在4千赫传输到主计算环路。利用这些信号，在假设等离子体电流可以表示为一个灯丝电流的情况下，在2khz下实时识别等离子体形状。利用等离子体控制系统的多核处理器，在另一个计算循环中并行完成该计算。利用比例-积分-导数控制回路将等离子体内外边缘位置控制到目标位置。外边缘位置不能由外PF线圈电流控制，而内边缘位置可以由内PF线圈电流控制。
A plasma control system to sustain divertor configurations is developed on QUEST (Q-shu university experiment with steady-state spherical tokamak). Magnetic fluxes are numerically integrated at 100 kHz using FPGA (Field-Programmable Gate Array) modules and transferred to a main calculation loop at 4 kHz. With these signals, plasma shapes are identified in real time at 2 kHz under the assumption that the plasma current can be represented as one filament current. This calculation is done in another calculation loop in parallel by taking advantage of a multi-core processor of the plasma control system. The inside and outside plasma edge positions are controlled to their target positions using PID (proportional-integral-derivative) control loops. Whereas the outside edge position can not be controlled by the outer PF coil current, the inside edge position can be controlled by the inner PF coil current.