Development of a plasma shape and position display system for damavand tokamak control room

Abstract

Determining the magnetic field profile is very important for studying flux surfaces, elongation, plasma boundaries, and real-time control in tokamaks. In this research, a system for calculating and displaying the shape, position, and boundary of plasma for Damavand Tokamak control room has been developed. This system determines the magnetic field profile and flux surfaces in the time interval between two consecutive shots. This software is implemented based on measurements with the probes' sensors and electromagnetic flux loops. It also solves mathematical equations based on the physics of the problem. In order to calculate the magnetic field profile and the plasma shape, after preparing and collecting the data from the data acquisition system, a developed code is used to pre-process the data, such as noise reduction, removing unnecessary data, etc. Then, using another code, the cross-section parameters such as shape, position, and plasma boundary are calculated and displayed in the tokamak control room. All the codes of this system are written in MATLAB software and as a graphical user interface procedure. This is so the tokamak operator has easy access to the results after every shot. This system is currently installed and operated in the Damavand tokamak control room.

Keywords

• damavand tokamak
• current filament method
• graphical user interface
• plasma shape and position
• plasma boundary