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LI Run, JIN Yu-ting, HU Jun, LI Guang-fu. Electrochemical Behavior of Corrosion at Normal Temperature of Three Typical Metals in Coast Nuclear Power Plants[J]. Corrosion & Protection, 2016, 37(9): 730-734. DOI: 10.11973/fsyfh-201609009
Citation: LI Run, JIN Yu-ting, HU Jun, LI Guang-fu. Electrochemical Behavior of Corrosion at Normal Temperature of Three Typical Metals in Coast Nuclear Power Plants[J]. Corrosion & Protection, 2016, 37(9): 730-734. DOI: 10.11973/fsyfh-201609009

Electrochemical Behavior of Corrosion at Normal Temperature of Three Typical Metals in Coast Nuclear Power Plants

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  • Received Date: June 21, 2016
  • The corrosion behavior in three solutions at 30 ℃ of three typical important structural materials used in coastal pressurized water reactor (PWR) nuclear power plants were studied by electrochemical methods. The effects of solution and material factors were analyzed. The three materials were low alloy steel 16MND5, stainless steel weld metal 308L and stainless steel base metal Z2CND18-12N. And the three solution were simulated PWR primary water, simulated PWR pninary water with 10 mg/L Cl- and 3.5% NaCl solution. The results showed that, in simulated PWR primary water, three materials exhibited passivity and the minimum corrosion susceptibility as compared with in other solutions. When the primary water was added with 10 mg/L Cl-, corrosion behaviors of the two stainless steels had little change, while the corrosion rate of 16MND5 increased significantly and exhibited active dissolution controlled by polarization. Maximum corrosion susceptibilities of three materials were exhibited in 3.5% NaCl solution. 16MND5 showed the highest rate of general corrosion. The passivity zones of the two stainless steels were relatively narrow, indicating high susceptibility to pitting. The pitting resistance of weld metal 308L with different orientations was similar and lower significantly than that of Z2CND18-12N. Exposing the test solutions to air caused increase of corrosion susceptibility of the three materials, especially the low alloy steel, due to high content of dissolved oxygen in solutions.
  • [1]
    杨武. 核电工业的发展及其对腐蚀防护技术的需求[J]. 腐蚀与防护,1998,19(3):99-107.
    [2]
    DIERCKS D R,SHACK W J,MUSCARA J. Overview of steam generator tube degradation and integrity issues[J]. Nuclear Engineering and Design,1999,194:19-30.
    [3]
    李光福. 压水堆压力容器接管-主管安全端焊接件在高温水中失效案例和相关研究[J]. 核技术:2013,36(4):25-28.
    [4]
    FERON D,OLIVE J M. Corrosion issues in light water reactors-stress corrosion cracking[M]. Boca Raton,FL:CRC Press,2007.
    [5]
    彭君. 水化学若干因素对核电用异种金属焊接件SA508-52M-316L应力腐蚀破裂的影响[D]. 上海:上海材料研究所,2012:38,41-46.
    [6]
    王光辉,彭君,袁义帆,等. 硫酸根离子和电极电位对异材焊接件A508/52M在高温水中应力腐蚀破裂的影响[J]. 理化检验(物理分册),2013,49(6):357-360.
    [7]
    LI G F,CONGLETON J. Stress corrosion cracking of a low alloy steel to stainless steel transition weld in PWR primary waters at 292 ℃[J]. Corrosion Science,2000,42(6):1005-1021.
    [8]
    DONG L J,PENG Q J,HAN E H,et al. Stress corrosion cracking in the heat affected zone of a stainless steel 308L-316L weld joint in primary water[J]. Corrosion science,2006,107:172-181.
    [9]
    李光福,方可伟,许君,等. 异材焊接件A508III-52M-316L主要材料在高温水环境中的电化学特性[J]. 腐蚀与防护,2014,35(12):1177-1181.
    [10]
    SUN M C,WU X Q,ZHANG Z E,et al. Oxidation of 316 stainless steel in supercritical water[J]. Corrosion Science,2009,51:1069-1072.
    [11]
    袁义帆,卢煦,杨星红,等. 16MND5.309L/308L/Z2CND18-12N异材焊接件的组织和性能[J]. 理化检验:物理分册,2014,50(6):404-413.

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