Structure characterization and steam oxidation performance of U3Si2 with Zr alloying additions

Journal of Nuclear Materials(2022)

引用 2|浏览4
暂无评分
摘要
•An annealed, 7 vol% Zr: U3Si2 sample displayed an onset of oxidation in steam at T > 500°C- a higher temperature than any arc-melt fabricated silicides tested to date.•A unique microstructure is observed in a 2 vol% Zr addition to U3Si2, hypothesized here to be caused by strain induced from the incorporation of Zr into the U3Si2 lattice.•Direct comparison was made between the simulated XRD patterns of the computational model system and the measured of the 14 vol%Zr sample, suggesting Zr-inclusion into uranium silicide to occur substitutionally.
更多
查看译文
关键词
Uranium Silicide,Nuclear Fuel,Nuclear Materials,Accident Tolerant Fuel,Steam Oxidation,DFT
AI 理解论文
溯源树
样例
生成溯源树,研究论文发展脉络
Chat Paper
正在生成论文摘要