与 316L 不锈钢相比,He 注入量对离子辐照 Cr0.8FeMnNi 中熵合金微观结构的影响

IF 2.3 2区 物理与天体物理 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Materials and Energy Pub Date : 2024-08-26 DOI:10.1016/j.nme.2024.101728
Mengke Niu , Naoyuki Hashimoto , Hiroshi Oka , Haotian Sun
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引用次数: 0

摘要

近年来,中熵和/或高熵合金(M/HEAs)因其优异的机械性能而备受关注,成为先进核反应堆结构材料的潜在候选材料。本研究探讨了 He 注入量对 Cr0.8FeMnNi MEA 和 316L 不锈钢微观结构演变的影响。首先注入氦原子,然后进行 Fe2+ 辐照。透射电子显微镜用于表征辐照诱发的缺陷。在所有氦注入量下观察到的主要辐照诱导缺陷都是黑点;在任何辐照条件下都没有发现空洞。在注入 He 的 Cr0.8FeMnNi 中,黑点的数量密度明显低于未注入 He 的 Cr0.8FeMnNi,而黑点的平均尺寸则随着 He 注入量的增加而增大。随着 He 注入量的增加,自间隙原子(SIA)与 He-V 复合物的结合能降低。这种降低促进了基质中大量 SIA 团簇的成核和生长,从而增加了黑点的数量密度。Cr0.8FeMnNi 中黑点数量密度的变化远远小于 316L 中观察到的变化。这可能是由于 Cr0.8FeMnNi 中点缺陷的多样性和较高的晶格畸变导致自愈过程增强。
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Influence of He injection amount on the microstructure of ion irradiated Cr0.8FeMnNi medium entropy alloy compared with 316L stainless steel

In recent years, medium and/or high-entropy alloys (M/HEAs) have attracted attention due to their excellent mechanical properties, positioning them as potential candidates for structural materials in advanced nuclear reactors. This study investigated the effect of He injection amount on the microstructural evolution in Cr0.8FeMnNi MEA and 316L stainless steel. Helium atoms were injected, followed by Fe2+ irradiation. Transmission electron microscopy was used to characterize the irradiation-induced defects. The primary irradiation-induced defects observed across all He injection amounts were black dots; no voids were seen under any irradiation conditions. In He-injected Cr0.8FeMnNi, the number density of black dots was significantly lower than in non-He-injected Cr0.8FeMnNi, while the average size of black dots increased with higher He injection rates. As the He injection amount increased, the binding energy of the self-interstitial atom (SIA) to the He-V complex decreased. This reduction facilitated the nucleation and growth of numerous SIA clusters within the matrix, consequently increasing the number density of black dots. The change in the number density of black dots in Cr0.8FeMnNi was much smaller than that observed in 316L. This could be ascribed to the enhanced self-healing process caused by the diversity of point defects and higher lattice distortion in Cr0.8FeMnNi.

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来源期刊
Nuclear Materials and Energy
Nuclear Materials and Energy Materials Science-Materials Science (miscellaneous)
CiteScore
3.70
自引率
15.40%
发文量
175
审稿时长
20 weeks
期刊介绍: The open-access journal Nuclear Materials and Energy is devoted to the growing field of research for material application in the production of nuclear energy. Nuclear Materials and Energy publishes original research articles of up to 6 pages in length.
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