通过实验和 DFT 计算对铬涂层 Zr-4 合金的高温空气氧化和蒸汽氧化进行比较研究

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2024-09-06 DOI:10.1016/j.jnucmat.2024.155382
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引用次数: 0

摘要

通过密度泛函理论(DFT)计算,比较研究了在空气和蒸汽气氛中镀铬 Zr-4 合金的高温氧化性能,并揭示了蒸汽促进氧化的机理。实验结果表明,在两种气氛中氧化后,表面和横截面的微观结构存在显著差异。高温空气氧化后会形成致密的不规则多面体氧化物,并伴有随机出现的微裂纹。而在高温蒸汽氧化后,则会形成具有须状结构的鲭鱼鳞状或蠕虫状颗粒,并伴有气孔和微裂纹等缺陷。在高温蒸汽气氛中,更剧烈的原子扩散导致更厚的 Cr-Zr 扩散层和更高的 O 含量,因此在 1100 °C 下暴露 3 小时和 4 小时后,邻近 Cr-Zr 扩散层的 Zr-4 合金被氧化成 ZrO2。所有实验结果都表明,在高温蒸汽气氛中,Cr 涂层 Zr-4 合金经历了更严重的氧化。DFT 计算结果表明,蒸汽促进氧化的主要原因是间隙 H 质子促进了 Cr2O3 氧化尺度中 Cr 和 O 空位及空位对的形成。
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Comparative study on high-temperature air and steam oxidation of Cr-coated Zr-4 alloy through experimental and DFT calculation

The high-temperature oxidation performance of Cr-coated Zr-4 alloy in air and steam atmosphere is comparatively studied and the mechanism of steam promoted oxidation is revealed by density functional theory (DFT) calculation. The experimental results show that there are significant differences in surface and cross-sectional microstructures after oxidation in the two atmospheres. Dense irregular polyhedral oxides accompanied by randomly occurring micro-cracks are developed after high-temperature air oxidation. While mackerel scale-like or worm-like particles with whisker-like structures accompanied by defects such as pores and micro-cracks are developed after high-temperature steam oxidation. In the high-temperature steam atmosphere, the more vigorous atomic diffusion leads to a thicker Cr-Zr diffusion layer and higher O content, so that after exposure at 1100 °C for 3 and 4 h, the Zr-4 alloy adjacent to the Cr-Zr diffusion layer is oxidized to ZrO2. All the experimental results demonstrate that Cr-coated Zr-4 alloy experiences more severe oxidation in high-temperature steam atmosphere. The DFT calculation results reveal the main reason of steam promoted oxidation is that the interstitial H protons boost the formation of Cr and O vacancies and vacancy pairs in the Cr2O3 oxide scale.

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来源期刊
Journal of Nuclear Materials
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.
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