Effect of oxidation temperature on microstructure and liquid lead-bismuth eutectic corrosion resistance of pre-oxidized film on high-silicon ferritic/martensitic steel
IF 3.2 2区 工程技术Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Yangpeng Zhang , Xia Pan , Xinyu Cao , Haichang Jiang , Desheng Yan , Lijian Rong
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引用次数: 0
Abstract
This study systematically investigates the influence of oxidation temperature on the microstructural of pre-oxidized films and their corrosion resistance in liquid lead-bismuth eutectic (LBE) for ferritic/martensitic steel. Key findings demonstrate that pre-oxidation temperature significantly affect oxide film composition: (Cr,Fe)₂O₃ oxides initiate formation above 650 °C, while MnCr₂O₄ spinel phases emerge at temperatures exceeding 720 °C. In addition, a progressive increase in pre-oxidation temperature from 650 °C to 780 °C results in oxide film thickening from ∼50 nm to ∼250 nm. Corrosion tests in static oxygen-saturated LBE at 550 °C reveal that higher pre-oxidation temperatures enhance the LBE corrosion resistance of the pre-oxidized films due to increased thickness and improved oxide composition. The best protective effect is achieved after pre-oxidation at 780 °C. However, microstructural defects such as oxide interfaces and gaps between the oxide film and the substrate can serve as pathways for inward oxygen diffusion and outward iron diffusion. Over time, ions preferentially penetrate the pre-oxidized film along defect-rich regions, leading to the formation of localized corrosion zones. This research elucidates the influence mechanism of oxidation temperature on the microstructure and LBE corrosion resistance of pre-oxidized films, providing guidance for optimizing pre-oxidation processes and enhancing corrosion resistance.
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.