Real-time plasma configuration reconstructing system and real-time plasma configuration reconstructing method for Tokamak

Abstract

The invention discloses a real-time plasma configuration reconstructing system and a real-time plasma configuration reconstructing method for Tokamak. The real-time plasma configuration reconstructing system comprises a plasma diagnosis system, the plasma diagnosis system is connected with a real-time configuration acquiring industrial personal computer, and the real-time configuration acquiring industrial personal computer is provided with a data acquisition card and a corresponding reflection memory card. Plasma diagnosis signals of the plasma diagnosis system enters the data acquisition card of the real-time configuration acquiring industrial personal computer, a time sequence unifying system provides a unified time sequence signal which also enters the real-time configuration acquiring industrial personal computer, the real-time configuration acquiring industrial personal computer transmits numerical value information of the plasma diagnosis signals acquired by the data acquisition card to a reflection memory interchanger through the reflection memory card, the reflection memory interchanger synchronizes numerical values of the plasma diagnosis signals to a reflection memory card of a high-grade real-time configuration reconstructing work station, the high-grade real-time configuration reconstructing work station transmits calculated plasma configuration information to the reflection memory interchanger through the reflection memory card connected onto the high-grade real-time configuration reconstructing work station, and a configuration controls calculates according to the plasma configuration information.

Description

technical field [0001] The invention belongs to the field of real-time reconstruction systems, and in particular relates to a plasma configuration real-time reconstruction system and method applied to a tokamak. Background technique [0002] In the research of controlled nuclear fusion experiments, the magnetic confinement device used to confine the plasma is mainly a tokamak (or stellarator) device. Due to the drift of the plasma, it is impossible to achieve the confinement of charged particles solely relying on the longitudinal field; therefore, a poloidal magnetic field must be introduced to make the total field form a helical structure. In this way, the drift direction of the particles in the plasma will change with time, so that the total drift cancels each other out, so that the particles are better restrained by the magnetic field. [0003] Therefore, the tokamak, a specific fusion magnetic confinement device, puts forward relatively high requirements for the real-ti...

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Problems solved by technology

[0004] However, there is currently no diagnostic method to directly measure the plasma shape, that is, the shape of the plasma cannot be directly measured, and other diagnostic data must be used for configuration reconstruction.

In the offline situation, the reconstruction method can use the Grad-Shafranove equation to calculate the distribution of the magnetic flux profile of the plasma, so as to determine the outermost magnetic surface of the plasma. The outermost magnetic surface of the plasma is the shape of the plasma , the shape of the plasma is determined, and its position can be directly derived. The Grad-Shafranov equation is essentially a Poisson equation with only numerical solutions, so it takes a lot of iterations to get it, and it takes time to calculate a time slice each time. It is about hundreds of milliseconds to 1 second, while the control cycle of real-time plasma control is on the order of 1ms to several milliseconds, and each calculation can only calculate one time slice, and cannot be continuously calculated

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