Effect of He/dpa ratio on bubble characteristics in Fe9Cr1.5W0.4Si F/M steel during irradiation and annealing

材料科学 气泡 退火(玻璃) 辐照 透射电子显微镜 复合材料 分析化学(期刊) 结晶学 纳米技术 化学 核物理学 机械 物理 色谱法
作者
Dewang Cui,Kefei Pei,Ziqi Cao,Yipeng Li,Yifan Ding,Yuanming Li,Shichao Liu,Guang Ran
出处
期刊:Journal of Materials Science & Technology [Elsevier BV]
卷期号:197: 17-24 被引量:2
标识
DOI:10.1016/j.jmst.2024.01.040
摘要

The He production rate (i.e., He/dpa) in nuclear reactors strongly affects the degradation of material properties. This is an important but not yet fully understood issue. Here, the effect of He/dpa on bubble characteristics in Fe9Cr1.5W0.4Si ferrite-martensitic (F/M) steel was in situ studied during 400 keV Fe+ and 30 keV He+ dual-beam irradiation at 723K with three ratios of 100, 500, and 2500 appm He/dpa and subsequent stepwise annealing using transmission electron microscopy (TEM). He/dpa strongly affected the bubble characteristics. During irradiation, the higher the He/dpa, the smaller the size of irradiated bubbles, but the higher their density. However, He/dpa didn't affect the final saturation size of irradiated bubbles for all three cases, which was ∼2.2 nm. During annealing, high He/dpa caused large, immobile, dense polyhedral bubbles with a wider bubble size distribution, while low He/dpa caused small, low-mobility, and relatively low-density spherical bubbles. It was found that the higher the He/dpa ratio, the greater the swelling during irradiation and annealing, and annealing further enhanced the swelling. Moreover, the tunnel structure was first found in body-centered cubic (BCC) F/M steel during in-situ irradiation. The current work provides valuable and potential insights for further understanding the He/dpa effects in materials serving in different nuclear reactors.

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