高温水中溶解氧对不锈钢堆焊层SCC性能的影响
Effects of Dissolved Oxygen on Stress Corrosion Cracking Behavior of Stainless Steel Cladding in High Temperature Water
摘 要
采用慢应变速率试验(SSRT),在模拟AP1000高温高压(350 ℃,18.5 MPa)水环境中,研究了溶解氧对E308L不锈钢堆焊层的应力腐蚀开裂(SCC)倾向的影响规律,并详细观察了试样断口形貌.结果表明,不锈钢堆焊层分别在含0 μg/kg、200 μg/kg和2 000 μg/kg的不同溶解氧量的高温水环境中都呈现出了不同程度的SCC倾向,且水中溶解氧含量的增加使得SCC倾向更为明显.
高温高压水
应力腐蚀开裂
SSRT
stainless steel cladding
high temperature and high pressure water
SCC
SSRT
Abstract
The effect of dissolved oxygen (DO) on the SCC behavior of E308L stainless steel cladding was studied by slow strain rate tests (SSRT) in high temperature (350 ℃) and high pressure (18.5 MPa) water of simulated AP1000 environments.And the fracture morphology of specimens after testing was observed carefully.The results showed that stainless steel cladding specimens had SCC susceptibility in high temperature water environments containing different concentrations of dissolved oxygen (DO) such as 0 μg/kg,200 μg/kg and 2 000 μg/kg DO.And SCC susceptibility became more remarkable with the increase of dissolved oxygen.
中图分类号 TG174.2 TL341 DOI 10.11973/fsyfh-201506005
所属栏目 试验研究
基金项目 压水堆核电材料环境相关性研究重大专项(2011ZX0600400908)
收稿日期 2014/6/10
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备注张乐福(1967-),副教授,博士,从事核材料相关研究.
引用该论文: LU Hui,DU Dong-hai,CHEN Kai,SHEN Zhao,ZHANG Le-fu,TANG Rui. Effects of Dissolved Oxygen on Stress Corrosion Cracking Behavior of Stainless Steel Cladding in High Temperature Water[J]. Corrosion & Protection, 2015, 36(6): 531
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参考文献
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【4】KANE R D.Slow strain rate testing for the evaluation of environmentally induced cracking[M].USA:ASTM International,1993.
【5】BERTINI L.New high concentration-high temperature hydrogenation method for slow strain rate tensile tests[J].Materials Letters,2007,61(11):2509-2513.
【6】MTHIS K.Acoustic emission monitoring of slow strain rate tensile tests of 304L stainless steel in supercritical water environment[J].Corrosion Science,2011,53(1):59-63.
【7】LONG B,DAI Y,BALUC N.Investigation of liquid LBE embrittlement effects on irradiated ferritic/martensitic steels by slow-strain-rate tensile tests[J].Journal of Nuclear Materials,2012,431(1):85-90.
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【12】ANDRESEN P L,MORRA M M.IGSCC of non-sensitized stainless steels in high temperature water[J].Journal of Nuclear Materials,2008,383:97-111.
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