Microstructural changes and irradiation hardening behavior of V-4Cr-4Ti alloys irradiated with He ions using flash-electropolishing

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2024-10-05 DOI:10.1016/j.jnucmat.2024.155438

Ken-ichi Fukumoto , Yichen Zou , Takuya Nagasaka , Ryoya Ishigami

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Abstract

The flash-electropolishing of focused ion beam samples for V-4Cr-4Ti alloys is established, and the microstructures of high-purity V-4Cr-4Ti alloys after He ion irradiation are examined by transmission electron microscopy from room temperature to 700 °C. The correlation between irradiation hardening behavior and microstructural changes is clarified. During room temperature irradiation, defect clusters are formed at shallow positions in the specimens and no He bubbles are observed at the damage peak position. In contrast, 500 and 700 °C, TiCON precipitates are predominantly formed and He bubbles and voids were formed at the damage peak position. The results of nanoindentation tests and a comparison of irradiation hardening by irradiation damage indicate that the obstacle barrier strength factorαof TiCON is 0.45 while that of the irradiation defect clusters irradiated at room temperature is 0.10. Irradiation damage in the He ion range extends toward the interior of the specimens with increasing irradiation temperature.

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使用闪速电抛光法辐照 He 离子的 V-4Cr-4Ti 合金的微观结构变化和辐照硬化行为

建立了 V-4Cr-4Ti 合金聚焦离子束样品的闪速电抛光方法，并通过透射电子显微镜观察了高纯度 V-4Cr-4Ti 合金在 He 离子辐照后从室温到 700 ℃ 的微观结构。阐明了辐照硬化行为与微观结构变化之间的相关性。在室温辐照期间，试样的浅层位置形成了缺陷簇，在损伤峰值位置没有观察到 He 气泡。相反，在 500 和 700 ℃ 时，主要形成了 TiCON 沉淀，并在损伤峰值位置形成了 He 气泡和空隙。纳米压痕测试结果和辐照损伤的辐照硬化比较表明，TiCON 的障碍强度因子α 为 0.45，而室温辐照缺陷簇的障碍强度因子α 为 0.10。随着辐照温度的升高，He 离子范围内的辐照损伤向试样内部扩展。

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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.