Testing of Tungsten Plasma-Facing Components of a Divertor in PLM Plasma Device

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发表日期：

2024年12月1日

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V. P. Budaev,
S. D. Fedorovich,
A. V. Dedov,
D. I. Kavyrshin,
A. V. Karpov,
M. V. Lukashevsky,
A. V. Zakharenkov,
M. V. Gubkin,
Q. V. Tran,
K. A. Rogozin,
A. A. Konkov,
A. I. Gubanova

摘要

Abstract

The created plasma device PLM-M is used to test the heat-shielding lining of the in-vessel components of a thermonuclear reactor with steady-state plasma having parameters similar to the near-wall and divertor plasma of a tokamak. The PLM-M is a linear magnetic trap with a multi-cusp magnetic field. A special feature of the device is the many hours of steady-state operation with magnetized plasma of high parameters. Tungsten modules manufactured using ITER divertor technology have been tested with high-heat loads from ~1 to ~5 MW/m². There were no significant macroscopic surface changes, large-scale cracks or splits on the surface, or significant erosion of the tungsten layout during plasma tests. For additional load on the tungsten during plasma tests, a laser with a power simulating the level of ELMs was used. Traces of arcs were detected on the plasma-facing tungsten surface of the model during plasma tests. Additional tests of cooled tungsten modules of in-vessel components are planned in order to estimate their erosion in the ITER and develop recommendations for in-vessel component design for the FNS.