Comparative studies of the long-term corrosion behavior of Zr-Sn-Fe-Cr-Ni alloys in pure water at 360 °C/18.6 MPa with high and low dissolved oxygen content

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

Journal of Nuclear Materials Pub Date : 2024-10-24 DOI:10.1016/j.jnucmat.2024.155481

Aijia Lei , Xun Dai , Yufeng Du , Jingjing Liao , Ruiju Deng , Jiangtao Xu , Xuefei Huang

引用次数: 0

Abstract

This study compared the uniform corrosion behavior of Zr-Sn-Fe-Cr-Ni alloys in deionized water at 360 °C/18.6 MPa with high and low concentration of dissolved oxygen (DO). It was found that high concentration of DO accelerated the corrosion rate of the Zr-Sn-Fe-Cr-Ni alloys and led to an earlier corrosion transition. Increased DO concentration resulted in a higher content of t-ZrO₂ near the metal-oxide interface, which induced greater in-plane compressive stress in the oxide film and a high-level phase transformation from t-ZrO₂ to m-ZrO₂. This, in turn, led to an earlier occurrence of corrosion transition.

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360 °C/18.6 MPa 溶解氧含量高低条件下纯水中 Zr-Sn-Fe-Cr-Ni 合金长期腐蚀行为的比较研究

本研究比较了去离子水中 360 °C/18.6 MPa 溶氧（DO）浓度高低下 Zr-Sn-Fe-Cr-Ni 合金的均匀腐蚀行为。研究发现，高浓度溶解氧加快了 Zr-Sn-Fe-Cr-Ni 合金的腐蚀速度，并导致腐蚀转变提前。溶解氧浓度的增加导致金属-氧化物界面附近的 t-ZrO2 含量增加，从而在氧化膜中产生更大的平面压应力，并导致 t-ZrO2 向 m-ZrO2 的高水平相变。这反过来又导致腐蚀转变提前发生。

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.