Effects of Zinc Concentration on Oxide Films of Alloy 690 in PWR Primary Water
摘 要
在模拟压水堆一回路水环境中, 对镍基690合金进行了在加锌量分别为10, 60, 120 μg/L的三组320 ℃高温溶液中600 h的腐蚀试验, 并对腐蚀后的试样表面进行了X射线光电子能谱(XPS)分析。结果表明, 随着锌浓度的增加, 试样的腐蚀增重速率降低, 氧化膜厚度减薄, 降低腐蚀速率的有效加锌量范围为10~60 μg/L; 试样表面形成主要成分为ZnCr2O4和Cr2O3的氧化膜。
Abstract
The effects of zinc concentration on the oxide films of alloy 690 were investigated in simulated pressurized water reactor(PWR) primary water. After exposed in 320 ℃ solutions with the zinc concentration of 10, 60, 120 μg/L, respectively, for 600 h , oxide films developed on the surface of specimens were analyzed by X-ray photoelectron spectroscopy (XPS). The results show that with the increase of zinc concentration, the weight gain rate decreased, and the oxide film became thinner. The range of effective zinc concentration to reduce corrosion rate was advised between 10 to 60 μg/L. The main compontents of the oxide film after exposure in zinc addition solutions were ZnCr2O4 and Cr2O3.
中图分类号 TG174
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 2013/6/5
修改稿日期
网络出版日期
作者单位点击查看
备注张乐福, 副教授, 博士, 从事核电材料腐蚀性能研究,
引用该论文: DUAN Zhen-gang,PAN Xiang-feng,ZHANG Le-fu,WANG Li,XU Xue-lian,SHI Xiu-qiang. Effects of Zinc Concentration on Oxide Films of Alloy 690 in PWR Primary Water[J]. Corrosion & Protection, 2014, 35(4): 348
共有人对该论文发表了看法,其中:
人认为该论文很差
人认为该论文较差
人认为该论文一般
人认为该论文较好
人认为该论文很好
参考文献
【1】GOLD R E, KORMUTH J W, BERGMANN C A, et al. Evaluation of zinc addition to primary coolant of Farley-2 PWRs:fuel cladding corrosion[R]. Palo Alto:EPRI, 1996.
【2】ROUMIGULRE F. Field experience on Zn injection on PWR plants with a view to dose rate reduction[C]//International Conference of Nuclear Energy for New Europe 2005 Bled, Slovenia:[s.n.], 2005.
【3】MACHET A, GALTAYRIES A, MARXCUS P, et al. XPS study of oxides formed on nickel-base alloys in high-temperature and high-pressure water[J]. Surface and Interface Analysis, 2002, 34(1):197-200.
【4】ROBERTSON J. The mechanism of high temperature aqueous corrosion of stainless steels[J]. Corrosion Science, 1991, 32(4):443-465.
【5】KAWAMURA H, HIRANO H, SHIRAI S, et al. Inhibitory effect of zinc addition to high-temperature hydrogenated water on mill-annealed and prefilmed alloy 600[J]. Corrosion, 2000, 56(6):623-637.
【6】HUANG J, LIU X, HAN E H, et al. Influence of Zn on oxide films on alloy 690 in borated and lithiated high temperature water[J]. Corrosion Science, 2011, 53(10):3254-3261.
【7】乔培鹏, 张乐福, 刘瑞芹, 等. 压水堆条件下锌对奥氏体不锈钢腐蚀性能的影响[J]. 原子能科学技术, 2010, 44(6):690-693.
【2】ROUMIGULRE F. Field experience on Zn injection on PWR plants with a view to dose rate reduction[C]//International Conference of Nuclear Energy for New Europe 2005 Bled, Slovenia:[s.n.], 2005.
【3】MACHET A, GALTAYRIES A, MARXCUS P, et al. XPS study of oxides formed on nickel-base alloys in high-temperature and high-pressure water[J]. Surface and Interface Analysis, 2002, 34(1):197-200.
【4】ROBERTSON J. The mechanism of high temperature aqueous corrosion of stainless steels[J]. Corrosion Science, 1991, 32(4):443-465.
【5】KAWAMURA H, HIRANO H, SHIRAI S, et al. Inhibitory effect of zinc addition to high-temperature hydrogenated water on mill-annealed and prefilmed alloy 600[J]. Corrosion, 2000, 56(6):623-637.
【6】HUANG J, LIU X, HAN E H, et al. Influence of Zn on oxide films on alloy 690 in borated and lithiated high temperature water[J]. Corrosion Science, 2011, 53(10):3254-3261.
【7】乔培鹏, 张乐福, 刘瑞芹, 等. 压水堆条件下锌对奥氏体不锈钢腐蚀性能的影响[J]. 原子能科学技术, 2010, 44(6):690-693.
相关信息