压水堆条件下中子辐照在 Zr-1Nb 中形成的 β-Nb 的氧化行为

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

Journal of Nuclear Materials Pub Date : 2024-10-29 DOI:10.1016/j.jnucmat.2024.155478

Xue Han, Huacai Wang, Huanlin Cheng, Jinze Sun, Lina Guo, Wulin Song, Huize Fan

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引用次数: 0

摘要

本研究以中子辐照 Zr-1Nb 合金为研究对象，使用高分辨率透射电子显微镜 (HRTEM) 研究氧化膜内β-Nb 在距离氧化物/金属（O/M）界面不同距离处的氧化行为。结果表明，β-Nb 最初在 O/M 界面 0 纳米处氧化成 T-NbO2，然后在 600 纳米内氧化成 T-NbO2、M-Nb2O5 和 O-Nb2O5 的复杂形态。最后，在 800 纳米内完全氧化为 M-Nb2O5。在本研究中，β-Nb 在观察到的距离内没有出现无定形形态。此外，还采用了反快速傅里叶变换（IFFT）和弱束暗场（WBDF）技术来表征氧化膜中的位错密度和分布，结果表明氧化膜中由中子辐照产生的位错分布相对均匀，中子辐照不是影响β-Nb氧化行为的主要原因。

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Oxidation behavior of β-Nb formed in Zr-1Nb under neutron irradiation in PWR conditions

This work focuses on neutron irradiated Zr-1Nb alloy, using High Resolution Transmission Electron Microscopy (HRTEM) to investigate the oxidation behavior of β-Nb at different distances from the Oxide /Metal (O/M) interface within the oxide film. Results show that β-Nb was initially oxidized to T-NbO₂ at 0 nm at O/M interface, then into a complex morphology of T-NbO₂, M-Nb₂O₅, and O-Nb₂O₅ within 600 nm. Finally, it was completely oxidized to M-Nb₂O₅ within 800 nm. β-Nb in this study did not exhibit amorphous morphology within observed distances. In addition, Inverse Fast Fourier Transformation (IFFT) and Weak Beam Dark Field (WBDF) techniques are employed to characterize the dislocation density and distribution in the oxide film, results indicate that the distribution of dislocations generated by neutron irradiation in the oxide film is relatively uniform and neutron irradiation is not the primary reason affecting the oxidation behavior of β-Nb.

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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.