Crystal-orientation-dependence of irradiation damage in CoCrFeNiMn alloy under heavy ion irradiation at 500°C

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-03-04 DOI:10.1016/j.jnucmat.2025.155729

Fei Zhu, Feng Zhou, Qiang Zhang, Jinhong Chen, Jiaxin Wu, Ligang Song, Xianfeng Ma

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引用次数: 0

Abstract

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 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.