FIELD: control and regulation.
SUBSTANCE: invention relates to a system for automatic magnetic control of position, shape and current of plasma in a tokamak with a divertor configuration. System consists of a unit of a linearized code for reconstructing a plasma shape in real time, connected by transmission channel of calculated geometrical parameters of plasma for development of vertical instabilities with control unit of power supply of winding of horizontal control field (WHCF) and a channel for transmitting the calculated geometric parameters of the plasma for calculating the setting of the control value with the control unit of the power supply sources of the inductor winding (IW) and control windings CW), discharge scenario data unit connected by reference current value transmission channels to the IW and CW power supply sources regulator, toroidal magnetic field winding power supply regulator unit and WHCF power supply regulator unit, electromagnetic diagnostics (EMD) sensor unit, which is connected by a channel for transmitting signals required for calculating geometric parameters of plasma to a unit of linearized code for reconstructing the shape of plasma in real time. To solve the problem of controlling the shape of the plasma, indirect methods of recovering shape parameters from measurements of electromagnetic diagnostics (EMD) sensors are used to determine current values of the controlled parameters in real time.
EFFECT: increasing duration and stability of plasma discharge in a tokamak with a divertor configuration in accordance with a given discharge scenario.
1 cl, 2 dwg
