500℃重离子辐照下CoCrFeNiMn合金辐照损伤的晶体取向依赖性

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Fei Zhu, Feng Zhou, Qiang Zhang, Jinhong Chen, Jiaxin Wu, Ligang Song, Xianfeng Ma
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引用次数: 0

摘要

高熵合金作为一种极具发展前景的核结构材料,因其优异的抗辐照性能而受到广泛关注。在这项工作中,使用透射电子显微镜(TEM)研究了在500°C下,2.5 MeV Fe 2 +高达15 dpa的辐照下,等原子CoCrFeNiMn合金中辐照损伤的晶体取向依赖性。< 001 >取向的晶粒抗辐照性能最差,在所有受损取向中,1/2 < 110 >的完美位错密度最大,断裂环最大,空洞膨胀最大。< 011 >的晶粒溶胀程度最低。此外,< 111 >的晶粒呈现出更小、密度更高的断裂环。讨论了CoCrFeNiMn取向依赖性辐射损伤的可能原因。在< 011 >晶粒中观察到的最小损伤可归因于其最大程度的沟槽。对于< 001桶/立方米和< 111桶/立方米的谷物,考虑其他影响因素也是至关重要的。该研究强调了在评估具有大晶粒尺寸的多晶sp - csa的辐照损伤行为时考虑取向的重要性。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Crystal-orientation-dependence of irradiation damage in CoCrFeNiMn alloy under heavy ion irradiation at 500°C
As promising nuclear structural materials, high-entropy alloys have attracted extensive attentions due to their excellent anti-irradiation properties. In this work, the crystal-orientation-dependence of irradiation damage in equiatomic CoCrFeNiMn alloy, subjected to 2.5 MeV Fe²⁺ irradiation up to 15 dpa at 500 °C, was investigated using transmission electron microscopy (TEM). The 〈001〉-oriented grain exhibited the worst irradiation resistance, as evidenced by the densest 1/2〈110〉 perfect dislocations, the largest faulted loops and the greatest void swelling among all the damaged orientations. The 〈011〉 grain showed the lowest void swelling. Furthermore, the 〈111〉 grain exhibited faulted loops that were smaller in size and exhibited a higher density. Possible contributions to the orientation-dependent radiation damage of CoCrFeNiMn were discussed. The minimal damage observed in 〈011〉 grain can be attributed to its highest degree of channeling. It is also crucial to consider other contributing factors as well for 〈001〉 and 〈111〉 grains. This study underscores the importance of accounting for orientation when assessing the irradiation damage behavior of polycrystalline SP-CSAs with substantial grain sizes.
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来源期刊
Journal of Nuclear Materials
Journal of Nuclear Materials 工程技术-材料科学:综合
CiteScore
5.70
自引率
25.80%
发文量
601
审稿时长
63 days
期刊介绍: The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.
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