Tokamak inverse triangle divertor magnetic field configuration construction method

Abstract

The invention belongs to a magnetic confinement nuclear fusion technology, and particularly relates to a Tokamak inverse triangle divertor magnetic field configuration construction method, which comprises the following steps: determining the position of an inverse triangle divertor coil and the layout of a magnetic flux broadening coil, then carrying out preliminary estimation on the coil current, designing the configuration of the inverse triangle divertor, wherein the triangle variation rate is a negative number (the configuration triangle of the traditional divertor is changed into a positive number); the negative triangle variation rate enables the X point and the strike point to move towards the weak field, so that the large radius R of the strike point is obviously increased, the wetting area is naturally increased, and the thermal load of the target plate is effectively reduced.

Description

technical field [0001] The invention belongs to magnetic confinement nuclear fusion technology, and in particular relates to a method for constructing a magnetic field configuration of a tokamak inverse triangular divertor. Background technique [0002] In modern tokamaks, the progress of the divertor configuration has greatly improved the confinement performance of many devices, so that the divertor has become one of the core components of the tokamak device, which is responsible for key tasks such as heat removal and ash removal. At present, the world's largest fusion research cooperation program - ITER has entered the construction stage, and the divertor has become an indispensable part of it. However, the conventional divertor configuration of single zero is currently adopted by ITER, and the heat load on the inner and outer target plates is far beyond the allowable thermal load engineering limit of the existing target plate design, which is 10MW / m 2 , making the ITER d...

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 undergo strong convection and diffusion, and then flow to the target plate along the four legs, and finally achieve the effect of reducing the thermal load of the target plate; However, the target plate of the snowflake divertor is too close to the main 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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