Corrosion Behavior of Zr-1Sn-0.35Fe-0.15Cr-0.10Nb-0.03Ge Alloy in 400 °C Super-heated Steam with Different Oxygen Contents

被引:0
|
作者
Xu Shitong [1 ]
Yao Meiyi [1 ]
Bai Yong [1 ]
Huang Jiansong [1 ]
Lin Xiaodong [1 ]
Hu Lijuan [1 ]
Xie Yaoping [1 ]
Liang Xue [2 ]
Peng Jianchao [2 ]
Xu Jing [2 ]
Zhou Bangxin [1 ]
机构
[1] Shanghai Univ, Inst Mat, Shanghai 200072, Peoples R China
[2] Shanghai Univ, Lab Microstruct, Shanghai 200444, Peoples R China
关键词
zirconium alloy; corrosion; dissolved oxygen; microstructure; DISSOLVED-OXYGEN; LITHIATED WATER; RESISTANCE;
D O I
暂无
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
In order to explore the corrosion behavior of Zr-1Sn-0.35Fe- 0.15Cr-0.10Nb- 0.03Ge ( wt%) alloy in 400. super-heated steam with different oxygen contents, Zr-1Sn-0.35Fe-0.15Cr-0.10Nb-0.03Ge alloy specimens were put into static autoclave and dynamic autoclave for super- heated steam corrosion tests under deaeration, 300x10(-9) dissolved oxygen (DO) and 1000x10(-9) DO environment at 400 degrees C/10.3 MPa. The scanning electron microscope, transmission electron microscope, and X-ray photoelectron spectroscope were used to characterize the microstructure of alloys and oxide films, as well as the valence state of the alloying element. Results show that compared with the deaeration environment, the average corrosion rate of Zr-1Sn-0.35Fe-0.15Cr- 0.10Nb-0.03Ge alloy in 300x10(-9) DO and 1000x10(-9) DO environments is increased by 23.5% and 29.4%, respectively, indicating that DO can accelerate the corrosion of the alloys, and the higher the DO content, the more obvious the corrosion acceleration effect. DO not only promotes the oxidation of Fe, Cr, Sn and Ge in the oxide film, but also accelerates the reaction process of Zr -> ZrOx -> ZrO2 in the transition layer at the O/M interface. Based on the above two aspects, a mechanism of DO accelerating the corrosion of zirconium alloys at 400 degrees C/10.3 MPa is proposed. The increase in DO content in the corrosive environment leads to an increase in the concentration of O2- and OH- participating in the reaction in the oxide film. On the one hand, this promotes the oxidation of alloying elements, leading to the increase in defects and local stress in the oxide film; on the other hand, this also accelerates the evolution of Zr -> ZrOx -> ZrO2 at the O/M interface, resulting in higher stress in the oxide film and providing less time for stress release during oxidation. The roles of the two aspects both promote the generation of pores and cracks, and accelerate the diffusion of O2- and OH-, thus accelerating the corrosion of zirconium alloys.
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页码:1746 / 1758
页数:13
相关论文
共 23 条
  • [1] CORROSION BEHAVIOR OF Zr(Fex, Cr1-x)2 ALLOYS IN 400 °C SUPERHEATED STEAM
    Cao Xiaoxiao
    Yao Meiyi
    Peng Jianchao
    Zhou Bangxin
    [J]. ACTA METALLURGICA SINICA, 2011, 47 (07) : 882 - 886
  • [2] Garzarolli F, 1996, 11 INT S, P850
  • [3] ISOBE T, 1991, AM SOC TEST MATER, V1132, P346, DOI 10.1520/STP25517S
  • [4] Keller P, 2004, CORROS SCI, V46, P1939, DOI [10.1016/j.corsci.2004.01.007, 10.1016/j.corsci.2003.01.007]
  • [5] Effect of dissolved oxygen on oxidation and hydrogen pick up behaviour-Zircaloy vs Zr-Nb alloys
    Kumar, M. Kiran
    Aggarwal, Sachin
    Kain, Vivekanand
    Saario, Timo
    Bojinov, Martin
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (05) : 985 - 994
  • [6] Li M.S., 2011, High Temperature Corrosion of Metal
  • [7] Liu Jianzhang, 2007, Nuclear Structural Materials
  • [8] Pre-transition Corrosion Behavior of SZA-4 and ZIRLO Alloys in Dissolved Oxygen Aqueous Condition at 360℃
    Liu Q.
    Zhang H.
    Zeng Q.
    Lu J.
    Li C.
    Zhang L.
    [J]. Jixie Gongcheng Xuebao/Journal of Mechanical Engineering, 2019, 55 (08): : 88 - 96
  • [9] Shaoqiu Gou, 2015, Lithiated Aqueous Solution
  • [10] Mechanism of corrosion rate degradation due to tin
    Takeda, K
    Anada, H
    Barberis, P
    Maguire, M
    Motta, A
    Lemaignan, C
    Garde, A
    [J]. ZIRCONIUM IN THE NUCLEAR INDUSTRY: TWELFTH INTERNATIONAL SYMPOSIUM, 2000, 1354 : 592 - 608