Corrosion behavior and mechanism of 17–4PH martensitic stainless steel in saturated oxygen static lead-bismuth eutectic at 450 °C

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

Journal of Nuclear Materials Pub Date : 2025-09-07 DOI:10.1016/j.jnucmat.2025.156155

Guobao Ma , Gen Li , Zhengxin Tang , Xitao Wang , Jinshan He , Hansheng Bao , Xikou He

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引用次数: 0

Abstract

17–4PH martensitic stainless steel is used in pressurized water reactors (PWRs) nuclear systems and also shows potential for lead-cooled fast reactors (LFRs), while its resistance to lead-bismuth corrosion is critical. Therefpore, the corrosion behavior of 17–4PH steel in saturated oxygen static lead-bismuth eutectic (LBE) at 450 °C was investigated. It was found that during the initial 3000 h, an incomplete oxide film developed due to the cyclic formation and spalling of oxide layers. By 4500 h, a stable double-layered oxide film was formed, consisting of an outer Fe₃O₄ layer and an inner FeCr₂O₄ layer. During internal oxidation, Ni enrichment occurred beneath the internal oxidation layer (IOL)/matrix interface, transforming the body-centered cubic (BCC) martensitic matrix into a face-centered cubic (FCC) Ni-rich phase. The stress induced by the volume change during this phase transition constitutes the predominant driver for premature oxide film spalling. The Ni-rich phases exhibit resistance to oxidation and form isolated islands and flocculent structures within the IOL. Cu accumulates as Cu-rich phases within the IOL and tends to rapidly grow into irregular shapes by adhering to the Ni-rich phase. The flocculent distribution of Cu and Ni within the IOL produced nanoporous regions. These pores acted as diffusion pathways for metallic elements, accelerating oxide film growth after 4500 h. The corrosion mechanism of 17–4PH steel in liquid LBE is discussed based on these observations.

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17-4PH马氏体不锈钢在450℃饱和氧静态铅铋共晶中的腐蚀行为及机理

17-4PH马氏体不锈钢用于压水堆（pwr）核系统，也显示出铅冷快堆（LFRs）的潜力，同时其抗铅铋腐蚀的能力至关重要。因此，研究了17-4PH钢在450℃饱和氧静态铅铋共晶（LBE）中的腐蚀行为。结果表明，在最初的3000 h内，由于氧化层的循环形成和剥落，形成了一层不完整的氧化膜。经过4500 h，形成了稳定的双层氧化膜，由外层Fe3O4层和内层FeCr2O4层组成。在内部氧化过程中，镍在内部氧化层(IOL)/基体界面下方富集，使体心立方（BCC）马氏体基体转变为面心立方（FCC）富镍相。相变过程中体积变化引起的应力是氧化膜过早剥落的主要驱动因素。富镍相具有抗氧化性，在人工晶状体内形成孤岛和絮状结构。Cu在IOL内以富Cu相的形式积累，并通过附着富ni相迅速生长成不规则形状。Cu和Ni在IOL中的絮状分布产生了纳米孔区。这些孔隙作为金属元素的扩散途径，在4500 h后加速氧化膜的生长。根据这些观察结果，讨论了17-4PH钢在液态LBE中的腐蚀机理。

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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.