辐照
氙气
氪
离子
材料科学
碳化硅
通量
原子物理学
硅
抗辐射性
晶格常数
陶瓷
放射化学
化学
核物理学
衍射
物理
光学
复合材料
冶金
有机化学
作者
В.В. Углов,P. S. Grinchuk,M. V. Kiyashko,V. М. Kholad,S.V. Zlotski,В.А. Скуратов,A. T. Issatov
出处
期刊:High Temperature Material Processes
日期:2022-09-02
卷期号:27 (1): 53-58
被引量:1
标识
DOI:10.1615/hightempmatproc.2022043720
摘要
Due to its superior high-temperature strength, high thermal conductivity, chemical inertness, and
\nsmall neutron capture cross section, silicon carbide (SiC) is suitable for use as structural components
\nin nuclear fusion reactors, or as an encapsulating material for nuclear fuel in light water
\nreactors and gas-cooled fission reactors, and also in radioactive nuclear waste disposals. Thus,
\nthe study of the radiation resistance of the structural-phase state and the nature of the evolution
\nof defects in silicon carbide after simulated ion irradiation of fission fragments is a relevant task
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