Dispersed barrier hardening modeling on depth-distributed helium bubbles in iron-based alloys

IF 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-02-01 Epub Date: 2025-01-06 DOI:10.1016/j.jnucmat.2025.155608
Xinrun Chen , Tatsuya Suzuki , Phongsakorn Prak Tom , Bo Li , Zongda Yang , Sho Kano , Takuya Yamamoto , Kenta Murakami
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Abstract

The present study investigates the irradiation hardening in pure Fe and Fe-0.3 wt.% Si alloys after He+ ion implantation tests in order to obtain a representative value for the barrier strength (α-value) of helium bubbles in model ferritic alloys. 160 keV He+ ion implantation was performed at 400 ± 2 °C with a fluence up to 3.6 × 1016 cm-2 at a flux of 4.0 × 1013 cm-2∙s-1. Hardness was measured using the nanoindentation technique at different indentation depths, and the depth-distributed helium bubbles were observed by transmission electron microscopy (TEM). The results of the hardness measurement demonstrated a significant damage gradient effect in both He+ implanted specimens. This could be attributed to the presence of depth-distributed helium bubbles. Additionally, a significant dose dependence on swelling was observed in both alloys, suggesting that the primary parameter governing the evolution of helium bubbles is the dose. While the traditional dispersed barrier hardening (DBH) model could be employed to evaluate the α-value based on helium bubble-induced hardening, the distribution of dispersed barriers should be uniform. Consequently, we proposed a more efficacious application of the dispersed barrier hardening model to describe the depth-distributed helium bubble-induced hardening in iron-based materials by integrating the nanoindentation technique with TEM. The α-value for helium bubbles of approximately 2∼3 nm in diameter in model ferritic alloys is estimated to be approximately 0.15 to 0.16 based on the revised DBH model, which is consistent with the value observed in annealed F82H of neutron irradiation. Furthermore, this study suggested that the much greater hardness increase and swelling rate of implanted Fe-0.3Si than that of pure iron is due to the additive silicon, which has a strong ability to inhibit vacancy diffusion in the evolution of helium bubbles.

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铁基合金中深度分布氦泡的分散势垒硬化模型
本文研究了纯Fe和Fe-0.3 wt.% Si合金在He离子注入试验后的辐照硬化,以获得模型铁素体合金中氦气泡阻挡强度(α-值)的代表值。160 keV He+离子注入在400±2°C下进行,通量为4.0 × 1013 cm-2∙s-1,通量高达3.6 × 1016 cm-2。采用纳米压痕技术测量了不同压痕深度下的硬度,并通过透射电镜(TEM)观察了深度分布的氦气泡。硬度测量结果表明,两种He+注入试样均存在明显的损伤梯度效应。这可能归因于深度分布的氦气泡的存在。此外,在两种合金中观察到明显的剂量依赖于膨胀,这表明控制氦气泡演化的主要参数是剂量。传统的分散势垒硬化(DBH)模型可用于评价基于氦气气泡诱导硬化的α-值,但分散势垒的分布应是均匀的。因此,我们将纳米压痕技术与透射电镜相结合,提出了一种更有效的应用分散势垒硬化模型来描述铁基材料中深度分布的氦泡诱导硬化。根据修正的DBH模型,模型铁素体合金中直径约为2 ~ 3 nm的氦气泡α-值约为0.15 ~ 0.16,与中子辐照退火F82H观测值一致。此外,本研究表明,注入Fe-0.3Si后,其硬度的提高和膨胀率远高于纯铁,这是由于添加了硅,硅在氦泡演化过程中具有很强的抑制空位扩散的能力。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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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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