Pioneering experimental platform for service performance of divertor components in future fusion reactors

Abstract

The invention discloses a service performance beforehand experiment platform of a future fusion reactor divertor part. The platform includes a drive assembly, a support assembly and an experiment part assembly. The drive assembly is externally connected to the bottom part of a lower window neck tube and provides vertical movement to the support assembly and the experiment part assembly and includes a support desk, a driver, a stepping motor, a coupler and a spiral elevator. The support assembly is in the lower window neck tube and includes a baffle, a corrugated pipe, a flange, a support main shaft and an auxiliary support. The experiment part assembly is in a vacuum chamber lower divertor area and includes the divertor part and a support body thereof, a support frame and a cooling pipe. During a service performance experiment is carried out, the platform accurately transports experiment parts to a standard divertor position and if the experiment parts are damaged, the experiments can be removed from the standard divertor position so as to be far away from a plasma and thus normal discharge operation of the plasma is not affected; and the system is adaptive to demands of carrying out of a service behavior beforehand experiment on divertor parts with different structures and technologies.

Description

Technical field [0001] The invention relates to the technical field of nuclear fusion device equipment, in particular to an advanced experimental platform for the service performance of future fusion reactor divertor components. Background technique [0002] The goal of nuclear fusion energy research is to provide mankind with inexhaustible clean and pollution-free energy. Tokamak magnetic confinement nuclear fusion is considered to be one of the most promising ways to commercialize fusion energy. In recent decades, great progress has been made in the research of Tokamak magnetically confined nuclear fusion energy at home and abroad, and the research is progressing towards the research of the all-superconducting tokamak experimental device or experimental reactor operating at steady state and high parameters. The significant improvement of each device's operating parameters, especially the improvement of plasma quality, is closely related to the development of divertor component...

AI Technical Summary

Problems solved by technology

The divertor is directly exposed to the bombardment of the high-flux particle flow and energy flow from the plasma, and at the same time, due to the breakup of the plasma, the occurrence of boundary localized modes (ELMs), the vertical displacement event (VDE), etc., the divertor will be greatly affected. The impact of instantaneous thermal load and electromagnetic load may cause surface ablation, melting, crack generation and structural damage to the divertor components, which will affect the performance of the divertor, and even affect the operation safety of the device in severe cases.

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