镍中自离子辐照诱导的晶粒形成

IF 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-02-01 Epub Date: 2024-12-25 DOI:10.1016/j.jnucmat.2024.155588
S.E. Donnelly , G. Greaves , F. Granberg , J. Sharp , A.H. Milston , J.A. Hinks , K. Nordlund
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引用次数: 0

摘要

在一系列实验中,用300 keV的Ni离子在25°至475°C的温度下照射含有大镍多晶(从透射电子显微镜的角度来看是单晶)的薄箔。其目的是研究在没有外来物质注入和没有分离、沉淀或形成新相的可能性的“简单”系统中扩大缺陷积累的基本方面。实验使用MIAMI-2设备进行,在该设备中观察(并记录)辐射损伤的发展,同时在透射电子显微镜下进行离子照射。令人惊讶的是,电化学薄化镍箔的所有辐照都导致位错积累,形成低角度晶界,使单晶材料转化为一系列晶粒,每个晶粒的宽度通常小于200 nm,但长度通常大于1 μ m,长轴近似平行于箔的边缘。用分子动力学模拟方法模拟了这一过程的早期阶段,并从辐射损伤引起的辐照、温度和应力耦合效应的角度讨论了这一辐射诱导晶界形成过程的解释。应力的产生是由于射流抛光试样(具有楔形径向截面)的薄辐照区域的膨胀,该区域受到较深的未辐照材料的约束。晶界形成的位置是由玻璃质位错与辐射损伤层和邻近边界引起的应力的相互作用决定的。
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Self-ion-irradiation-induced grain formation in nickel
A series of experiments has been conducted in which thin foils containing large polycrystals of Ni (single crystals from the perspective of transmission electron microscopy) have been irradiated with 300 keV Ni ions at temperatures from 25° to 475°C. The aim was to examine the fundamental aspects of the build-up of extended defects in a “simple” system with no implantation of foreign species and without the likelihood of segregation, precipitation or formation of new phases. Experiments were carried out using the MIAMI-2 facility in which the development of radiation damage is observed (and recorded) whilst ion-irradiating in-situ in a transmission electron microscope. Surprisingly, all irradiations of the electrochemically-thinned foils of Ni resulted in the accumulation of dislocations to form low-angle grain boundaries such that single crystal material was converted into a series of grains, each typically less than 200 nm in width but generally more than 1 µm in length with the long axis approximately parallel to the edge of the foil. The early stages of this process have been modelled using Molecular Dynamics simulations and an interpretation of this process of radiation-induced grain-boundary formation is discussed in terms of the coupled effects of irradiation, temperature and stress induced by the radiation damage. The stress arises due to swelling in the thin irradiated region of the jet-polished specimens (with a wedge-shaped radial cross section) which is constrained by deeper-lying unirradiated material. The position in which a grain boundary forms is determined by the interaction of glisssile dislocations with the stress induced by the radiation-damaged layer and that from a neighbouring boundary.
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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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