Research on intergranular corrosion of welded joint of nuclear-grade austenitic stainless steel

被引：0
|
作者：
机构：
[1] School of Material Science and Engineering, Jiangsu University, Zhenjiang
[2] JiangsuYinhuan Precision Steel Tube Co Ltd, Yixing
[3] China FSW Center, Beijing FSW Technology Co., Ltd., Beijing
来源：
Cheng, Xiao-Nong | 1600年 / Journal of Functional Materials卷 / 45期
关键词：
Austenitic stainless steel; Intergranular corrosion; Nuclear; Welding;
D O I：
10.3969/j.issn.1001-9731.2014.23.007
中图分类号：
学科分类号：
摘要：
The tendency to intergranular corrosion of the welded joints of 800H and Cr18Ni30Mo2Al3Nb alloy was investigated. Sensitizing treatment of 650℃ ×100 h and no treatment was used. The microstructure, morphology and the intergranular corrosion resistance of samples were studied by optical microscope, SEM and Method of copper sulfate-sulfuric acid test for stainless steels. The results show that the dissimilar welded joints are all the single austenite (γ) organizations. TiN inclusions lead to pitting corrosion in alloy 800H. However, no excessive pitting corrosion in Cr18Ni30Mo2Al3Nb alloy. As can be seen from the weightlessness, corrosion depth test results, clearly shown that Cr18Ni30Mo2Al3Nb welded joint has better intergranular corrosion resistance than 800H. ©, 2014, Journal of Functional Materials. All right reserved.
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页码：23033 / 23037
页数：4
相关论文
共 11 条
  • [1] Dutta R.S., Corrosion aspects of Ni-Cr-Fe based and Ni-Cu based steam generator tube materials, Journal of Nuclear Materials, 393, 2, pp. 343-349, (2009)
  • [2] Tan L., Rakotojaona L., Allen T.R., Et al., Microstructure optimization of austenitic alloy 800H (Fe-21Cr-32Ni), Materials Science and Engineering A, 528, 6, pp. 2755-2761, (2011)
  • [3] Cheng X., Jiang Y., Li D., Et al., High temperature oxidation behavior of new Cr<sub>19</sub>Ni<sub>28</sub>Ti alloy in atmospheres, Journal of Functional Materials, 44, 12, pp. 1792-1794, (2013)
  • [4] Dutta R.S., Purandare R., Lobo A., Et al., Microstructural aspects of the corrosion of alloy 800, Corrosion Science, 46, 12, pp. 2937-2953, (2004)
  • [5] Ding X., IGA/IGSCC and protection on secondary side of steam generator tubes in nuclear power plants, Corrosion & Protection, 23, 10, pp. 441-444, (2002)
  • [6] Han E., Wang J., Wu X., Et al., Corrosion mechanisms of stainless steel and nickel base alloys in high temperature high pressure water, Acta Metallurgica Sinica, 46, 11, pp. 1379-1390, (2010)
  • [7] Wu X., Xu S., Han E., Et al., Corrosion fatigue of nuclear-grade stainless steel in high temperature water and its environmental fatigue design model, Acta Metallurgica Sinica, 47, 7, pp. 790-796, (2011)
  • [8] Meng W., Yang R., Shu J., Et al., Intergranular corrosion susceptibility of welded joint of stainless steels, Corrosion & Protection, 30, 10, pp. 684-687, (2009)
  • [9] Li X., Wang J., Han E., Et al., Corrosion behavior of nuclear grade alloys 690 and 800 in simulated high temperature and high pressure primary water of pressurized and water reactor, Acta Metallurgica Sinica, 48, 8, pp. 941-950, (2012)
  • [10] Li X., Huang F., Wang J., Et al., Influences of TiN inclusion on corrosion and stress corrosion behaviors of alloy 690 tube in high temperature and high pressure water, Acta Metallurgica Sinica, 47, 7, pp. 847-852, (2011)
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