Design method for magnetic field configuration of quasi-ring symmetric star simulator

Abstract

The invention relates to the technical field of physical experiment equipment, in particular to a quasi-ring symmetric star imitator magnetic field configuration design method. The method comprises the following steps: scanning the radial position of a non-axisymmetric magnetic field component (B<m, n> is a magnetic field intensity spectrum) by utilizing STELLOPT codes, changing the shape of a plasma boundary by adopting an improved Levenberg-Marquardt algorithm, obtaining a plurality of groups of iterated quasi-ring symmetric star simulator magnetic field configuration parameters, and screening out the optimal quasi-ring symmetric star simulator magnetic field configuration from the multiple groups of iterated quasi-ring symmetric star simulator magnetic field configuration parameters. The quasi-ring symmetric star imitator magnetic field configuration designed by the invention can consider the advantages of Tokamak and a traditional star imitator, has the advantages of low new classical transportation, long-time steady-state operation, high beta (the ratio of plasma hot pressure to magnetic pressure) limit and the like, achieves the good plasma confinement performance, and can achieve the long-time steady-state operation. Meanwhile, the blank of domestic star simulator experimental physics research is filled up, and the method has important significance for promoting the construction and development of commercial fusion reactors with steady-state and high-constraint operation in the future.

Description

technical field [0001] 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. Background technique [0002] At present, the types of magnetic confinement fusion devices designed and built in the world include tokamak, anti-field pinch and stellarator. Among them, tokamak and stellarator are the two most mainstream magnetic confinement fusion devices in the world. Among stellarators, there are spiral stellarators with traditional magnetic field configurations, quasi-linear symmetric stellarators, and quasi-spiral symmetric stellarators. [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 circula...

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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.

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