The Effect of Proton Irradiation on In-situ Corrosion Behavior of Zr-Sn-Nb Zirconium Alloy under Simulated PWR Water Condition

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

Journal of Nuclear Materials Pub Date : 2025-04-03 DOI:10.1016/j.jnucmat.2025.155802

Tianxu Chen, Jingjing Liao, Shaoyu Qiu

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引用次数: 0

Abstract

In this study, we conducted a 30-day in-situ electrochemical corrosion investigation on proton-irradiated N36 zirconium alloy samples. Both potentiodynamic polarization and electrochemical impedance spectroscopy (EIS) methods were utilized to examine changes in electrochemical properties. Additionally, a long-term corrosion study was performed. Through the incorporation of microscopic characterizations, including X-ray diffraction (XRD) and transmission electron microscopy (TEM), we explored the influence of irradiation on the corrosion behavior and microstructure of the N36 alloy. Our findings demonstrate that proton irradiation reduced the corrosion rate of the N36 alloy and led to the formation of a denser oxide layer. Notably, as the irradiation dose increased, the beneficial effects became more pronounced. This improvement is likely attributed to the increased stability of the tetragonal zirconia (t-ZrO₂) phase, facilitated by defect generation, Sn/Nb doping in the zirconia, and significant irradiation-induced hardening. These factors promote the formation of a dense phase during the initial stages of corrosion.

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质子辐照对模拟压水堆水条件下Zr-Sn-Nb锆合金原位腐蚀行为的影响

在这项研究中，我们对质子辐照的N36锆合金样品进行了为期30天的原位电化学腐蚀研究。利用动电位极化和电化学阻抗谱（EIS）方法研究了电化学性能的变化。此外，还进行了长期腐蚀研究。通过x射线衍射（XRD）和透射电子显微镜（TEM）等微观表征手段，探讨了辐照对N36合金腐蚀行为和微观组织的影响。我们的研究结果表明，质子辐照降低了N36合金的腐蚀速率，并导致形成更致密的氧化层。值得注意的是，随着照射剂量的增加，有益效果变得更加明显。这种改进可能归因于四方氧化锆（t-ZrO 2）相的稳定性增加，这是由于缺陷的产生、氧化锆中掺杂了Sn/Nb以及明显的辐照诱导硬化所促进的。这些因素促进了腐蚀初期致密相的形成。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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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.