Effect of aging at 400°C on microstructure and corrosion properties of Fe-13Cr-3.5Al-2Mo-1.5Nb alloy

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

Journal of Nuclear Materials Pub Date : 2025-08-20 DOI:10.1016/j.jnucmat.2025.156117

Jingyi Tuo , Shuo Tian , Xuguang An , Huabei Peng , Yiyong Zhang , Yu Fu , Qingquan Kong , Donghai Du , Xuefei Huang , Hui Wang

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Abstract

The effects of aging time (0–2000 h) at 400 °C on the microstructure and electrochemical corrosion behavior of Fe-13Cr-3.5Al-2Mo-1.5Nb alloy in 1 wt.% NaCl solution were studied. The results showed that after aging at 400 °C, the grains of FeCrAl alloy hardly experienced significant growth, and the precipitates remained fine, uniformly distributed, and nanoscale in size, with more than 95% of the precipitates smaller than 200 nm. Additionally, the self-corrosion potential of the alloy in 1 wt.% NaCl solution shifted positively overall. After aging for 500 and 2000 h, the corrosion current density decreased by 42.9% and 41.9%, respectively, and the corrosion resistance improved. The alloy aged for 2000 h exhibited the higher uniform corrosion resistance and pitting resistance, characterized by a bilayer passivation film, with no niobium oxide phases (NbO, NbO₂, or Nb₂O₅) being detected in the outer oxide layer.

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400℃时效对Fe-13Cr-3.5Al-2Mo-1.5Nb合金组织和腐蚀性能的影响

研究了400℃时效时间（0 ~ 2000 h）对Fe-13Cr-3.5Al-2Mo-1.5Nb合金在1wt .% NaCl溶液中的组织和电化学腐蚀行为的影响。结果表明：在400℃时效后，FeCrAl合金晶粒几乎没有明显长大，析出相保持细小、分布均匀、纳米尺度，95%以上的析出相小于200 nm；此外，合金在1 wt.% NaCl溶液中的自腐蚀电位总体上正向移动。时效500 h和2000 h后，腐蚀电流密度分别下降42.9%和41.9%，耐蚀性提高。时效2000 h的合金表现出更高的均匀耐腐蚀性和抗点蚀性，其特征是双层钝化膜，在外层氧化层中没有检测到氧化铌相（NbO， NbO₂或Nb₂O₅）。

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 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.