核级316H保护氧化层在长期超临界CO2腐蚀中的失效机理

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-04-02 DOI:10.1016/j.jnucmat.2025.155803

Zhihao Wang , Jichun Zou , Minghao Wang , Shen Li , Dequan Peng , Shuai Chen , Wanhuan Yang , Weihua Zhong , Wen Yang

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引用次数: 0

摘要

实验研究了核级316H奥氏体不锈钢在超临界CO2 （S-CO2）中500℃、25 MPa、6400 h的腐蚀行为。分析结果表明，在腐蚀初期，材料表面形成一层Cr2O3保护层，具有较强的耐蚀性。然而，3200 h后，重量急剧增加（增加13.4倍），同时形成双层氧化物结构（Fe3O4/FeCr2O4），表明Cr2O3层失效。该研究阐明了Cr2O3在长时间S-CO2暴露下的内在化学失效（InCF）机制，为先进核系统的材料选择提供了重要见解。

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The failure mechanism of nuclear-grade 316H protective oxide layer in long-term supercritical CO2 Corrosion

An experimental investigation was conducted to evaluate the corrosion behavior of nuclear-grade 316H austenitic stainless steel in supercritical CO₂ (S-CO₂) at 500 °C and 25 MPa over 6400 h. The analysis of the results indicated that, during the initial stage of corrosion, a protective Cr₂O₃ layer formed on the material's surface, exhibiting significant corrosion resistance. However, a sharp escalation in weight gain (13.4 × increase) was observed after 3200 h, accompanied by the formation of a dual-layered oxide structure (Fe₃O₄/FeCr₂O₄), indicating the failure of the Cr₂O₃ layer. This study elucidates the intrinsic chemical failure (InCF) mechanism of Cr₂O₃ under prolonged S-CO₂ exposure, providing critical insights for material selection in 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.