材料科学
通量
钨
辐照
位错
Burgers向量
箔法
分子物理学
复合材料
冶金
核物理学
化学
物理
作者
Yipeng Li,Li Wang,Guang Ran,Yue Yuan,Lu Wu,Xinyi Liu,Xi Qiu,Zhirong Sun,Yifan Ding,Qing Han,Xiaoyong Wu,Hui Deng,Xiuyin Huang
出处
期刊:Acta Materialia
[Elsevier BV]
日期:2021-03-01
卷期号:206: 116618-116618
被引量:43
标识
DOI:10.1016/j.actamat.2020.116618
摘要
In-situ irradiations with 30 keV He+ were performed on tungsten in an investigation of the influences of irradiation temperature and fluence, pre-existing dislocation and sample thickness on dislocation loop evolution including interaction, density and size. Dislocation loops with b = 1/2<111> and b =<100> were found to form in tungsten during irradiation. The ratio of 〈100〉 loops was obviously affected by irradiation temperature, fluence, sample thickness and pre-existing dislocation lines. The interaction between high density helium clusters could stimulate the formation of 〈100〉 loops in irradiated W, which was verified by Molecular Dynamic (MD) simulations. In addition, the driving force for the 〈100〉 loop formation should also be attributed to the reaction of two 1/2<111> loop variants driven by long-time and elevated temperature irradiation. The pre-existing dislocation lines were found to have a profound effect on the size, density and Burgers vector of dislocation loops. Additionally, irradiation-induced defects were likely to be absorbed by the surface sinks of thin foil during ion irradiation, resulting in the formation of a denuded zone near the surface. The in-situ observation of irradiation defect evolution will lead to an improved fundamental understanding of irradiation damage process of tungsten serviced in fusion reactor.
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