From microstructural changes to electrochemical behavior: decoding the corrosion mechanism in Zr-Sn-Nb-Fe-Cr-Mo-O-V alloys

被引：0

作者：

Wang, Xutong ^{[1
]}

Li, Jiuxiao ^{[1
]}

Yu, Yixiao ^{[2
]}

Shi, Huigang ^{[3
]}

Zhao, Zhiwei ^{[1
]}

Zeng, Qifeng ^{[3
]}

Liu, Qingdong ^{[2
]}

机构：

[1] Shanghai Univ Engn Sci, Sch Mat Sci & Engn, Shanghai, Peoples R China

[2] Shanghai Jiao Tong Univ, Sch Mat Sci & Engn, Shanghai 200240, Peoples R China

[3] Shanghai Jiao Tong Univ, Sch Nucl Sci & Engn, Shanghai 200240, Peoples R China

来源：

JOURNAL OF NUCLEAR MATERIALS | 2024年 / 598卷

关键词：

Dissolved oxygen; Zr-Sn-Nb Alloy; Electrochemical impedance spectroscopy; Precession electron diffraction; Corrosion behavior; Small modular reactor; ZIRCONIUM ALLOYS; DISSOLVED-OXYGEN; HIGH-TEMPERATURE; AQUEOUS OXIDATION; WATER; ZIRCALOY-4; RESISTANCE; INTERFACE; STEAM;

D O I：

10.1016/j.jnucmat.2024.155137

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

The oxide formed on a Zr-0.4Sn-0.7Nb-0.3Fe-0.1Cr-0.15Mo-0.12O-0.05V, wt% alloy, after exposure for 300 d in 360 degrees C/20 MPa (water with 0 ppb, 300 ppb, and 1000 ppb), was characterized by transmission electron microscope (TEM), precession electron diffraction (PED) and electrochemical impedance spectroscopy (EIS). Results showed that DO accelerated the corrosion of the alloy, and this effect was enhanced with the increase of the DO concentrations. A mechanism of the correlation between electrochemical behavior evolution and microstructural changes of oxide film was proposed, which provided theoretical guidance for the selection of fuel cladding materials for small nuclear reactors.

引用

页数：13

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