Abstract
The NanChang Spherical Tokamak (NCST), a new compact (plasma major radius R = 0.40 m, minor radius a = 0.24 m, and aspect ratio A = 1.67) spherical tokamak, is suitable for teaching and scientific research activities at the university. The principal goal of the device is to initiate plasma currents by utilizing merging compression. At present, the NCST has a total of five complete coil systems, including the coils and their dedicated power supplies, to generate and control the plasma as per the experimental objectives. This paper presents the NCST device and its coils, the design of the power supplies, and the simulation results of plasma configurations as well as the comparison of experimental and simulation results of the above-mentioned power supply system.
Highlights
A spherical tokamak is a magnetic confinement fusion device with an outstanding low aspect ratio (A = major radius/minor radius
We have monitored the induced current in the Poloidal Field (PF) coils when the Central Solenoid (CS) power supply system is tested separately
It can be found that the induced current clearly disappears on the PF coils, which creates better conditions for plasma discharge experiments
Summary
A spherical tokamak is a magnetic confinement fusion device with an outstanding low aspect ratio (A = major radius/minor radius
Sign-in/Register to view highlights & summary Sign-in/Register to access full text options 
Free) 
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a call
