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核聚变能是最有希望的一种新能源,我国自行设计与建造的核聚变装置——HL-1已于1985年投入运行。研究核聚变装置中等离子体与器壁、孔栏材料相互作用日益受到广泛重视,因为这种反应造成等离子体的污染及聚变装置材料灼损坏。同时,这一研究还将提供等离子体边界层的性能参数,为下一代装置的器壁材料选择和结构设计提供参考。本文研究了镍基合金和铝探针在HL-1装置的等离子体括削层内,经等离子体辐照后的表面形貌及表面组分的变化。
Nuclear fusion energy is the most promising new energy source. China’s own design and construction of nuclear fusion device - HL-1 has been put into operation in 1985. Research on the interactions between plasma and wall and cell material in nuclear fusion devices is gaining more and more attention due to the plasma pollution and the damage of fusion device materials. At the same time, this research will provide the performance parameters of the plasma boundary layer and provide reference for wall material selection and structure design of the next generation of devices. In this paper, the surface morphology and surface composition changes of Ni-based alloy and aluminum probe irradiated by plasma in the plasma cutting layer of HL-1 device were studied.