Tokamak hybrid divertor magnetic field configuration construction method

Abstract

The invention belongs to the magnetic confinement fusion design technical field and concretely relates to a Tokamak hybrid divertor magnetic field configuration construction method. According to the method, a first poloidal field coil, a second poloidal field coil and a third poloidal field coil are arranged on a strong field side, and distances between the geometric center position of the first poloidal field coil and a first X point, between the geometric center position of the second poloidal field coil and the first X point and between the geometric center position of the third poloidal field coil and the first X point are set to be 1-1.5a, 1.5-3a and 1.5-3a respectively, wherein a is the minor radius of a plasma. The method solves the technical problems that a divertor magnetic fieldconfiguration constructed by a conventional divertor magnetic field configuration construction method makes the target plate heating area small and target plate hot fluid faces huge challenges in a high heating condition. A hybrid divertor magnetic field configuration has capabilities of reducing inner and outer heat load of a divertor target plate and improving target plate particle control at the same time, and improves compatibility of running of a divertor and running of a core high heating plasma.

Description

technical field [0001] The invention belongs to the technical field of magnetic confinement fusion design, and in particular relates to a method for constructing a magnetic field configuration of a tokamak hybrid divertor. Background technique [0002] As one of the most important key components of the magnetic confinement tokamak device, the divertor is used to remove the heat from the core plasma entering the edge region and flowing to the divertor, and at the same time discharge the alpha particle cooling produced by the fusion reaction in the core region The "helium ash" particles that come down ensure the cleanliness of the core plasma and maintain the continuation of the fusion reaction. In addition, the divertor also controls the entry of impurity particles generated in the edge region or actively injected into the main plasma region. [0003] With the improvement of the plasma operating parameters and the increase of auxiliary heating in the tokamak experimental dev...

AI Technical Summary

Problems solved by technology

The realization of the super X divertor configuration puts forward extremely high requirements for engineering design, especially the coil design under the superconducting tokamak device, followed by the design of the super X divertor configuration for the inner and outer divertors, and the space is limited , if only one of the inner and outer divertors adopts the super X divertor configuration, the other side will have a higher thermal load than the conventional divertor, and if it is improved by implementing a double zero divertor, it will face the upper and lower coil currents Unable to be consistent from time to time, forming a quasi-double-zero discharge, the thermal load of the inner target plate is still high

[0007] The snowflake divertor changes the first-order X point on the original standard divertor to the second-order X point, and the second-order X point changes the 4 branches of the standard X point into 6 branches, and the configuration is near its second-order X point There is a very large extremely low poloidal field area, which effectively realizes the expansion of the magnetic surface, increases the wetting area of ​​the plasma and increases the connection length from the outermost midplane to the divertor target plate, and the weak field area will also cause X The particle loss in the area near the point is enhanced. Through the high poloidal specific pressure area where the poloidal magnetic field is close to zero, the plasma will appear strong convection and diffusion, and then flow to the target plate along the four legs, but the target plate of the snowflake divertor is too close to the main body. In the plasma area, although the heat load can be reduced, the temperature of the particles reaching the target plate is very high and the particles are scattered, so it is impossible to effectively control the particles, especially the control of the density of impurity particles

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