A method for constructing the magnetic field configuration of a tokamak inverse triangular divertor

Abstract

The invention belongs to the magnetic confinement nuclear fusion technology, in particular to a method for constructing a magnetic field configuration of a tokamak inverse triangular divertor, determining the position of the inverse triangular divertor coil, the layout of the magnetic flux broadening coil, and then performing preliminary estimation and design of the coil current. The inverse triangular divertor configuration of , its triangle change rate is negative (the traditional divertor configuration triangle becomes positive); the negative triangle change rate makes the X point and the strike point move to the weak field measurement, making the strike point larger The radius R is significantly increased, which naturally increases the wetted area and effectively reduces the thermal load of the target plate.

Description

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

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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