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
Effects of Sulfate and Electrode Potential on Stress Corrosion Cracking of A508/52M Dissimilar Metal Weld in High Temperature Water Environments
摘 要
采用慢应变速率拉伸(SSRT)、电位测控和水中掺杂的方法, 研究了SO42-和电极电位对异材焊接件A508/52M在模拟压水堆核电站主回路高温水环境中应力腐蚀破裂(SCC)行为的影响。结果表明: 在有和无SO42-掺杂的水环境中, 试样SSRT的力学行为和断口形貌随电极电位变化的规律相似, 即在低电位区均在远离界面的镍基合金焊缝处发生韧性断裂, 与氮气环境中的拉伸试验结果相似; 在高电位区, 试样在焊接件界面周围区域发生SCC脆断;但掺杂10 g·m-3的SO42-后, 试样发生SCC的临界电位明显降低, 说明SO42-的存在增加了该异材焊接件在主回路水中的SCC敏感性。最后探讨了相关试验现象的机理和该研究的工程意义。
主回路水
异材焊接件
应力腐蚀破裂
电极电位
硫酸根离子
pressurized water reactor
primary water
dissimilar metal weld
stress corrosion cracking
electrode potential
sulfate
Abstract
The effects of sulfate and electrode potential on stress corrosion cracking (SCC) behavior of A508/52M dissimilar metal weld in simulated primary water environments of pressurized water reactor (PWR) at 290 ℃ were investigated by means of slow strain rate tensile (SSRT) test and electrode potential control. The results show that the variations of SSRT behaviors with the electrode potential of the weld in the waters without and with sulfate doping were generally similar, that is, ductile failure in the bulk zone of Ni-based weld metal when tested at low potentials, but brittle failure by SCC in the area around the A508/52M interface when tested at high potentials. Doping 10 g·m-3 SO42- into the simulated primary water increased the SCC susceptibility by decreasing the critical potential for SCC. The cracking mechanism and the engineering practical significance were discussed at last.
中图分类号 TG172
所属栏目 试验与研究
基金项目 国家重点基础研究发展计划资助项目(2011CB610506); 核电重大专项资助项目(2010ZX06004-009-03)
收稿日期 2013/4/17
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备注王光辉(1987-),男,硕士研究生。
引用该论文: WANG Guang-hui,PENG Jun,YUAN Yi-fan,LI Guang-fu,YANG Wu. Effects of Sulfate and Electrode Potential on Stress Corrosion Cracking of A508/52M Dissimilar Metal Weld in High Temperature Water Environments[J]. Physical Testing and Chemical Analysis part A:Physical Testing, 2013, 49(6): 357～361
王光辉,彭君,袁义帆,李光福,杨武. 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): 357～361
被引情况:
【1】李光福,方可伟,许君,杨武, "异材焊接件A508III-52M-316L基本材料在高温水环境中的电化学特性",腐蚀与防护 35, 1177-1181(2014)
【2】沈朝,潘向烽,张乐福,李力,唐睿, "超级奥氏体不锈钢AL-6XN在超临界水环境中的应力腐蚀性能",腐蚀与防护 35, 340-343(2014)
【3】袁义帆,卢煦,杨星红,李光福, "16MND5/309L/308L/Z2CND18-12N异种金属焊接件的组织和性能",理化检验－物理分册 50, 404-408(2014)
【4】卢煦,袁义帆,李润,李光福, "电极电位和应变速率对16MND5/309L/308L异材焊接件高温水中应力腐蚀破裂行为的影响",腐蚀与防护 36, 923-928(2015)
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参考文献
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【2】LI G F,CONGLETON J. Stress corrosion cracking of a low alloy to stainless steel transition weld in PWR primary waters at 292 ℃[J]. Corrosion Science,2000,42:1005-1021.
【3】PENG Q J,SHOJI T,YAMAUCHI H,et al. Inter-granular environmentally assisted cracking of alloy 182 weld metal in simulated normal water chemistry of boiling water reactor[J]. Corrosion Science,2007,49:2767-2780.
【4】KIM J W,LEE K,KIM J S,et al. Local mechanical properties of alloy 82/182 dissimilar weld joint between SA508 Gr. 1a and F316 SS at RT and 320 ℃[J]. Journal of Nuclear Materials,2009,384:212-221.
【5】李光福, 李冠军, 方可伟,等. 异材焊接件A508-52M-316L在高温水环境中的应力腐蚀破裂[J]. 金属学报,2011,47(7):797-803.
【6】ANDREESEN P L,EMIGH P W,MORRA M M,et al. Effects of PWR primary water chemistry and deaerated water on SCC[C]//Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power System-Water Reactors,2005.
【7】SCOTT P M. A Review of environment-sensitive fracture in water reactor materials[J]. Corrosion Science,1985,25(8):583-606.
【8】HOU J. Microstructure and stress corrosion cracking of the fusion boundary region in alloy 182-A533B low alloy steel dissimilar weld joint[J]. Corrosion Science,2010,52:3949-3954.
【9】FORD F P. Quantitative prediction of environmentally assisted cracking[J]. Corrosion,1996,52(5):375-395.
【10】KRITZER P. Corrosion in high-temperature and supercritical water and aqueous solutions[J]. Journal of Supercritical Fluids,2004,29:1-29.
【11】CONGLETON J,BERRISFORD R A,YANG W. Stress corrosion cracking of sensitized type 304 SS in doped high temperature water[J]. Corrosion,1995,51(12):901-910.
【12】李光福, 黄春波, 李敬民, 等. 固溶态控氮不锈钢在高温水中的应力腐蚀破裂[J]. 核动力工程,2005,26(4):384-389.
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