Tokamak tripod divertor magnetic field configuration construction method

Abstract

The invention belongs to the magnetic confinement fusion technical field and concretely relates to a Tokamak tripod divertor magnetic field configuration construction method. According to the method,distances between the geometric center position of a first poloidal field coil and a first X point, between the geometric center position of a second poloidal field coil and the first X point, betweenthe geometric center position of a third poloidal field coil and the first X point and between the geometric center position of a fourth poloidal field coil and the first X point are set to be 1-1.5a, 1.5-3a, 1.5-3a and 1.5-2.0a respectively, wherein a is the minor radius of a plasma. The method solves the technical problems that the target plate heating area of a common divertor of a conventional Tokamak magnetic confined plasma experiment apparatus is small and cooling of a target plate of the divertor faces huge technical challenges in a high heating condition. A constructed tripod divertor magnetic field configuration can alleviate heat load of a target plate and improve compatibility of running of a divertor and running of a core high heating plasma. The performance of dust removal and impurity shielding characteristics are better exhibited, and requirements of coil current strength and coil arrangement complexity are reduced for an advanced divertor configuration.

Description

technical field [0001] The invention belongs to the technical field of magnetic confinement fusion, and in particular relates to a method for constructing a magnetic field configuration of a tokamak tripod divertor. Background technique [0002] As an indispensable part of modern fusion tokamak devices, the divertor is responsible for the three major functions of ash discharge, heat removal and control of impurities entering the main plasma. With the improvement of the plasma operating parameters and the increase of auxiliary heating in the tokamak experimental device, more energy flows out of the separation surface in the divertor configuration, flows to the divertor along the magnetic field lines, and is deposited on the surface of the divertor target plate. The experimental results show that the radial energy attenuation length of the heat flow at the outer midplane is mainly related to the strength of the limiting magnetic field at the outer midplane. The energy attenuat...

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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

The snowflake divertor changes the first-order X point on the original standard divertor into a 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 wetted 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 have 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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