Spherical tokamak globus-m construction and operation

Abstract

Abstract Spherical tokamak Globus-M has been constructed for plasma experiments in the Ioffe Institute, St. Petersburg. This paper contains a brief overview of the tokamak characteristic features and main technical requirements and restrictions, which were used as the basis for Globus-M design. Currents in magnets are self-consistent with existing power supplies - thyristor rectifiers of 125 MVA total power. The poloidal field coils can sustain limiter and X-point plasma magnetic configurations with plasma current up to 0.5MA and plasma vertical elongation of 1.3–2.2. The central solenoid is designed for magnetic flux consumption of 0.3 V × s at a current swing of ± 70 kA. The parameters of the tokamak central column and the vacuum vessel are outlined. The plasma break-down phase achieved by means of the radio frequency preionization in the vicinity of electron cyclotron resonance is discussed.