The oxidation-dissolution behavior of Cr-coated Zr alloy in high temperature water

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

Journal of Nuclear Materials Pub Date : 2024-11-08 DOI:10.1016/j.jnucmat.2024.155504

Tao Huang , Yuhao Zhou , Kai Chen , Tianguo Wei , Shixin Gao , Hua Pang , Huifang Yue , Kun Zhang , Zhao Shen , Lefu Zhang

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引用次数: 0

Abstract

The corrosion and dissolution behavior of Cr-coated Zr alloy were investigated in high temperature water under varying dissolved oxygen (DO) and temperatures. Results demonstrate that the oxidation and dissolution rates of Cr coatings increase significantly with higher DO levels and temperature, while the Zr substrate remains unaffected by DO concentration. At DO levels below 10 ppb, Cr coatings exhibit high stability, but at 300 ppb DO, rapid corrosion/dissolution and spallation occur. The electrochemical potential (ECP) shifts in response to temperature and DO, driving the dissolution mechanism through three distinct region: steady-state, field-assisted dissolution (FAD), and complete dissolution. During the FAD period, a porous nanocrystalline Cr₂O₃ layer with residual Cr forms, characterized by non-uniform dissolution due to preferential oxidation at grain boundaries and microstructural defects. The soluble

{HCrO}_{4}^{-}

ions form at the base of the porous layer, followed by partial recrystallization at the surface, leading to the development of a thin Cr₂O₃ crystalline layer.

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铬涂层锆合金在高温水中的氧化溶解行为

在不同溶解氧（DO）和温度条件下，研究了高温水中铬涂层锆合金的腐蚀和溶解行为。结果表明，随着溶解氧水平和温度的升高，铬涂层的氧化率和溶解率显著增加，而 Zr 基体则不受溶解氧浓度的影响。当溶解氧浓度低于 10 ppb 时，铬涂层表现出很高的稳定性，但当溶解氧浓度达到 300 ppb 时，就会出现快速腐蚀/溶解和剥落。电化学势（ECP）会随温度和溶解氧的变化而变化，从而推动溶解机制经历三个不同的阶段：稳态、场辅助溶解（FAD）和完全溶解。在 FAD 阶段，会形成带有残余铬的多孔纳米晶 Cr2O3 层，其特点是由于晶界优先氧化和微结构缺陷而导致溶解不均匀。可溶性 HCrO4- 离子在多孔层底部形成，随后在表面发生部分再结晶，形成薄的 Cr2O3 结晶层。

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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.