合金元素对Ni0.9M0.1合金（M=Cr, Mo， W） He离子辐照损伤行为的影响

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-09-02 DOI:10.1016/j.jnucmat.2025.156145

Ying Li , Yulin Wei , Min Liu , Yajuan Zhong , Ping Peng

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引用次数: 0

摘要

在700℃下对纯Ni和二元Ni基合金（Ni0.9Cr0.1、Ni0.9Mo0.1和Ni0.9W0.1）进行He离子辐照，系统研究了合金元素对He气泡和位错演化的影响。透射电镜（TEM）显示，He气泡平均尺寸依次为：纯Ni >； Ni0.9Cr0.1> Ni0.9Mo0.1 > Ni0.9W0.1，气泡数密度呈反比趋势。位错环的形成也存在明显差异，其中Ni0.9Cr0.1的位错环最大。所有辐照样品均表现出辐照诱导硬化，其特征为纳米压痕。利用密度泛函理论（DFT）分析了合金元素在He原子扩散和气泡成核中的作用。Mo和W通过提高晶格原子稳定性和增加He迁移势垒抑制气泡粗化。相反，Cr通过轨道杂化和电子云重叠与He形成吸引相互作用，作为额外的俘获中心促进He泡成核。在纯Ni中，He的快速迁移和晶格稳定性的降低导致局部He影响区域的缺陷富集，进一步形成小的位错环，并合并成位错线或网络。在合金中，降低的He迁移率和增强的间隙溶解度稳定了He缺陷，推动了缺陷的持续生长。具体而言，Cr-He相互作用使He稳定形成大尺寸的位错环，而Ni0.9W0.1合金由于晶格原子稳定性较高，其位错环较小。该研究为先进核系统中耐辐照镍基合金的设计和优化提供了有价值的见解。

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The influence of alloying elements on the He ion irradiation damage behavior of Ni0.9M0.1 alloys (M=Cr, Mo, W)

He ion irradiation was performed on pure Ni and binary Ni-based alloys (Ni_0.9Cr_0.1, Ni_0.9Mo_0.1 and Ni_0.9W_0.1) at 700 °C to systematically investigate the effects of alloying elements on He bubble and dislocation evolution. Transmission electron microscopy (TEM) revealed a gradual decrease in the average He bubble size in the sequence: pure Ni > Ni_0.9Cr_0.1> Ni_0.9Mo_0.1 > Ni_0.9W_0.1, accompanied by an inverse trend in bubble number density. Distinct differences in dislocation loop evolution were also observed, and Ni_0.9Cr_0.1 exhibited the largest loops among the alloys. All irradiated samples exhibited irradiation-induced hardening, as characterized by nanoindentation. Density functional theory (DFT) calculations were conducted to elucidate the role of alloying elements in He atom diffusion and bubble nucleation. Mo and W suppress bubble coarsening by enhancing lattice atom stability and increasing He migration barriers. In contrast, Cr forms attractive interactions with He via orbital hybridization and electron cloud overlap, acting as additional trapping centers to promote He bubble nucleation. In pure Ni, rapid He migration and diminished lattice stability induce defect enrichment in the local He-affected regions, further forming small dislocation loops that coalesce into dislocation lines or networks. In alloys, reduced He mobility and enhanced interstitial solubility stabilize He defects, driving continuous defect growth. Specifically, Cr-He interactions stabilize He to form large-sized dislocation loops, while Ni_0.9W_0.1 alloys exhibit smaller loops due to higher lattice atom stability. This study provides valuable insights for the design and optimization of irradiation-resistant Ni-based alloys for advanced nuclear systems.

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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.