材料科学
退火(玻璃)
钨
大气温度范围
辐照
透射电子显微镜
Burgers向量
离子
活化能
分析化学(期刊)
等温过程
结晶学
热力学
复合材料
冶金
纳米技术
物理化学
化学
核物理学
有机化学
物理
色谱法
作者
Francesco Ferroni,Xiaoou Yi,Kazuto Arakawa,S. Fitzgerald,Philip D. Edmondson,Steve Roberts
标识
DOI:10.1016/j.actamat.2015.01.067
摘要
Transmission electron microscopy of high temperature annealing of pure tungsten irradiated by self-ions was conducted to elucidate microstructural and defect evolution in temperature ranges relevant to fusion reactor applications (500–1200 °C). Bulk isochronal and isothermal annealing of ion irradiated pure tungsten (2 MeV W+ ions, 500 °C, 1014 W+/cm2) with temperatures of 800, 950, 1100 and 1400 °C, from 0.5 to 8 h, was followed by ex situ characterisation of defect size, number density, Burgers vector and nature. Loops with diameters larger than 2–3 nm were considered for detailed analysis, among which all loops had b=12〈111〉 and were predominantly of interstitial nature. In situ annealing experiments from 300 up to 1200 °C were also carried out, including dynamic temperature ramp-ups. These confirmed an acceleration of loop loss above 900 °C. At different temperatures within this range, dislocations exhibited behaviour such as initial isolated loop hopping followed by large-scale rearrangements into loop chains, coalescence and finally line–loop interactions and widespread absorption by free-surfaces at increasing temperatures. An activation energy for the annealing of dislocation length was derived, finding Ea=1.34±0.2 eV for the 700–1100 °C range.
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