Method and device for measuring corona current in Tokamak device

Abstract

This invention discloses a method for measuring corona current in tokmak device and its device, characterized in: equipping interconnect screw coil with high frequency response in tokmak device vacuum case inwall, via inducted current of screw coil, attaining changes of vacuum inner magnetic field, based on these, via high temperature plasmas, round vertical field magnet, pole field magnet and vacuum case body in the tokmak device, testing the screw coils to attain corona current, and the non-uniformation of current distribution along ring direction.

Description

technical field [0001] The invention relates to the field of fusion plasma and electronics, in particular to a method and device for measuring corona current in a tokamak device. Background technique [0002] With the continuous deepening and development of fusion plasma physics research, people began to pursue the quality parameters and confinement performance of the tokamak device more, and actively explored some related to the future steady-state advanced tokamak fusion reactor. In recent years, the main direction of the development of tokamak nuclear fusion devices is to study the engineering technology and physical problems of the conventional circular cross-section plasma configuration to superconducting non-circular cross-section elongated plasma configuration. The tokamak device with plasma elongated cross-section is beneficial to improve the plasma parameters, especially the specific pressure value β, and the value of β is directly related to the economic quality of...

AI Technical Summary

Problems solved by technology

At present, some experimental measurement methods are being carried out on devices such as JET. The most basic method for studying the impact of HALO current on tokamak devices in the world still relies on the inductive statistics of the experimental operation data of devices with similar configurations, assuming that the plasma is symmetrically distributed. Then use TSC, EFIT and other tokamak discharge simulation programs to carry out two-dimensional numerical simulation. The biggest defect of this method is that it is difficult to simulate the asymmetry of the distribution of HALO current along the direction of the large ring, so that the three-dimensional space field of HALO current cannot be obtained. distribution, and for the tokamak device, the uneven electromagnetic load caused by the asymmetrical circular distribution current is one of the most dangerous working conditions that must be considered in the design, and it is extremely destructive to the device structure

Images