奥氏体不锈钢在含锌PWR一回路水中的均匀腐蚀行为
General Corrosion Behaviors of Austenitic Stainless Steels in Zinc Containing PWR Primary Water
摘 要
通过模拟压水堆一回路水环境, 对304和316L两种不锈钢进行了在含锌10 μg/kg,320 ℃高温溶液中浸泡1 000 h的腐蚀试验, 并对试验后的试样氧化膜进行SEM和XPS分析。结果表明, 304不锈钢的腐蚀增重率高于316L, 且其氧化膜较316L疏松; 两种试样均形成了富铁、锌内富铬的氧化膜; 外层氧化膜以(Zn,Fe,Ni)(Fe,Cr)2O4为主, 内层以ZnCr2O4为主, 氧化膜与基体过渡层以Cr2O3为主。
304不锈钢
316L不锈钢
含锌溶液
XPS分析
PWR
304 stainless steel
316L stainless steel
zinc solution
XPS analysis
Abstract
General corrosion of 304 and 316L stainless steels was studied in simulated pressurized water reactor (PWR) primary water environment containing 10 μg/kg zinc. After exposion for 1 000 h, the oxide films formed on the surface of specimens were analyzed by scanning electron microscopy (SEM) and X-ray photoelectron spectroscopy (XPS). The results showed that the corrosion weight gain of 304 stainless steel was higher than that of 316L, and the oxide film on 304 was looser than that on 316L. The oxide film was a double layer structure, in which the outer layer was thin and rich in Fe and Zn, while the inner layer was rich in Cr. The chemical composition analysis showed that the outer layer was mainly made up of (Zn,Fe,Ni)(Fe,Cr)2O4, the inner layer was ZnCr2O4, and the transition layer between oxide film and matrix metal was mainly Cr2O3.
中图分类号 TG172
所属栏目 试验研究
基金项目 大型先进压水堆核电站重大专项(2011ZX06004010)
收稿日期 2013/9/1
修改稿日期
网络出版日期
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备注张乐福(1967-),副教授,博士,从事核电材料的腐蚀与防护研究,
引用该论文: DUAN Zhen-gang,SHEN Zhao,ZHANG Le-fu,WANG Li,XU Xue-lian,SHI Xiu-qiang. General Corrosion Behaviors of Austenitic Stainless Steels in Zinc Containing PWR Primary Water[J]. Corrosion & Protection, 2014, 35(7): 637
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