A Design Method of Magnetic Field Configuration for Quasi-Ring Symmetric Stellarator

Abstract

The invention relates to the technical field of physical experiment equipment, in particular to a method for designing the magnetic field configuration of a quasi-ring symmetric stellarator, which uses STELLOPT codes to scan non-axisymmetric magnetic field components (B m,n is the radial position of the magnetic field intensity spectrum), the improved Levenberg-Marquardt algorithm is used to change the shape of the plasma boundary, and multiple sets of iterative quasi-annular symmetric stellarator magnetic field configuration parameters are obtained, and the best quasi-annular symmetric Stellarator magnetic field configuration. The quasi-ring symmetric stellarator magnetic field configuration designed by the present invention can take into account the advantages of the tokamak and the traditional stellarator, has low neoclassical transport, long-term steady-state operation, high β (plasma thermal pressure and magnetic Pressure ratio) limit and other advantages, to achieve not only good plasma confinement performance, but also to achieve the technical effect of long-term steady-state operation. The construction and development of commercial fusion reactors with constrained operation is of great significance.

Description

Technical field [0001] The present invention relates to the technical field of physical experimental equipment, and more particularly to a design method of a quasi-ring symmetric mitigator magnetic field shape. Background technique [0002] The type of magnetic constrained fractal devices built in the world is currently designed with Togamark, anti-hunting and mitigator. Among them, Tomamack and the mitigator are the current world's most mainstream magnetic constraint fractal devices. In the mitigator, there is a conventional magnetic field-shaped helix, a regular line symmetric mitigation, quasi-spiral symmetrical mitigation starch. [0003] The core portion of the magnetic constrained fracture device is in which the magnetic field for constraining the high-temperature plasma, the constrained magnetic field of the Toma Mark is co-generated by the external coil current and the plasma current, and the magnetic field shape of Tomamack is a ring-symmetric Having a good plasma constr...

AI Technical Summary

Problems solved by technology

[0003] The core part of the magnetic confinement fusion device is the magnetic field used to confine the high-temperature plasma. The confinement magnetic field of the tokamak is jointly generated by the external coil current and the plasma current. The magnetic field configuration of the tokamak is circularly symmetrical It has good plasma confinement performance. However, when the plasma current of the tokamak is close to extreme conditions, it may cause a large rupture of the plasma due to the instability of the magnetic fluid, so the device cannot run stably for a long time.

The magnetic field of the stellarator is completely generated by the external coil, so there is almost no plasma current in the stellarator, so it will not cause a large rupture and can achieve long-term steady-state operation. It is much more complicated, and compared with the tokamak, the traditional stellarator has a high magnetic field ripple, which will cause a large neoclassical transport loss, resulting in a lower confinement performance than the tokamak

Quasi-linear symmetric stellarators and quasi-spiral symmetric stellarators are advanced stellarators proposed after the development of traditional stellarators. These advanced stellarators have improved the shortcomings of traditional stellarators to a certain extent. The ideal situation is not reached, such as: due to the relatively large number of circular cycles, under the same parameters, the neoclassical transport is relatively large; the relatively large ring diameter greatly limits the effective volume of the magnetically confined plasma, etc.

Images