作者: G. Li , Y. Tan , Y. Q. Liu
DOI: 10.1063/1.4927682
关键词: Physics 、 Magnetic field 、 Toroid 、 Magnetic confinement fusion 、 Reversed field pinch 、 Atomic physics 、 Plasma 、 Mechanics 、 Eddy current 、 Spherical tokamak 、 Tokamak
摘要: Eddy currents have an important effect on tokamak plasma equilibrium and control of magneto hydrodynamic activity. The vacuum vessel the Sino-UNIted Spherical Tokamak is separated into two hemispherical sections by a toroidal insulating barrier. Consequently, characteristics eddy are more complex than those found in standard tokamak. Thus, it necessary to measure analyze eddy-current distribution. In this study, we propose experimental method for measuring distribution vessel. By placing flexible printed circuit board with magnetic probes onto external surface field parallel then subtracting generated vertical-field coils, due current can be obtained, its determined. We successfully applied Tokamak, thus, obtained despite presence coils.