Development of equilibrium control technic for the spherical tokamak plasmas from initial phases to steady state phase

点击翻译按钮获取中文摘要

The purpose of this task is to develop the technic to identify and control plasma position and its shape on spherical tokamaks. In order to identify them, the magnetic signals are generally used. Since these signals are calculated with integration, errors called as drift errors are piled up in the long time plasma discharge. Thus, the idea is to acquire the images of plasma with visible lights, soft x-ray, and so on, and the plasma position is identified with the image in real-time. From this position, magnetic signals are estimated and errors are corrected. In this task, the operation test is done with a flashlight instead of plasma, and the good position detection and its drift error correction are confirmed. Furthermore, the real-time equilibrium calculation code is developed.