温度对高温水中奥氏体不锈钢应力腐蚀开裂速率的影响
Effects of Temperature on Stress Corrosion Cracking of Austenitic Stainless Steels in High Temperature Water
摘 要
温度是影响核电站材料在高温水冷却剂中应力腐蚀开裂的关键参数之一。测试和分析了温度对不同外加应力水平下不同屈服强度奥氏体不锈钢在高温纯水中应力腐蚀开裂速率的影响。发现在110 ℃~288 ℃温度范围内,冷加工316L不锈钢的应力腐蚀开裂扩展速率为热激活过程。应力腐蚀开裂速率的表观活化能与温度区间、应力强度因子大小和屈服强度有关。分析了试验结果与文献报道的温度影响奥氏体不锈钢应力腐蚀开裂的几种类型和相关联的因素。
应力腐蚀开裂
核电站
高温水
热激活能
Austenitic stainless steel
stress corrosion cracking
nuclear power plant
high temperature water
thermal activation energy
Abstract
Temperature is one of the key factors for stress corrosion cracking (SCC) of nuclear power plant materials in high temperature water coolants. This paper analyzed the effects of temperature on SCC growth rates of austenitic stainless steels with different yield strengths at two stress intensity factors in high purity water. It was found that SCC growth rate was thermally activated from 110 to 288 ℃. The apparent thermal activation energy was affected by temperature range itself,stress intensity factor and yield strength. Experimental results and reported types of the temperature effect on SCC of austenitic stainless steels as well as correlated factors were analyzed.
中图分类号 172.8 DOI 10.11973/fsyfh-201509002
所属栏目 试验研究
基金项目 上海市浦江人才计划(12PJ1403600);教育部博士点基金博导类项目(20123108110021);上海市科委国际科技合作项目(13520721200)
收稿日期 2014/9/6
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联系人作者吕战鹏(zplu@shu.edu.cn)
备注吕战鹏(1967-),研究员,博士,从事金属腐蚀与防护研究。
引用该论文: L Zhan-peng,CHEN Jun-jie. Effects of Temperature on Stress Corrosion Cracking of Austenitic Stainless Steels in High Temperature Water[J]. Corrosion & Protection, 2015, 36(9): 803
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参考文献
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【6】RUTHER W E,SOPPET W K,KASSNER T F. Effect of temperature and ionic impurities at very low concentrations on stress corrosion cracking of aisi 304 stainless steel[J]. Corrosion,1988,44:791-799.
【7】WEEKS J R,VYAS B,ISAACS H S. Environmental factors influencing stress corrosion cracking in boiling water reactors[J]. Corrosion Science,1985,25:757-768.
【8】HALE D A. The effect of bwr startup environments on crack growth in structural alloys[J]. J Engineering Materials and Technology-Transactions ASME,1986,108:44-49.
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【19】L Z P,SHOJI T,TAKEDA Y,et al. The dependency of the crack growth rate on the loading pattern and temperature in stress corrosion cracking of strain-hardened 316L stainless steels in a simulated BWR environment[J]. Corrosion Science,2008,50:698-712.
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【21】SHOJI T,LI G F,KWON J H,et al. Quantification of yield strength effects on IGSCC of austenitic stainless steels in high temperature waters[C]//Proc.11th Int.Conf.Environmental Degradation Materials Nuclear Power Systems-Water Reactors.Houston:ANS,2003:834.
【22】ARIOKA K,YAMADA T,TERACHI T,et al. Temperature,potential and sensitization effects on intergranular crack growth and crack-tip appearance of cold worked 316[C]//Proc.13th Int.Conf.Environmental Degradation Materials Nuclear Power Systems-Water Reactors.whistler:CNS,2007:CD-ROM.
【23】ANDRESEN P L,ANGELIU T M,YOUNG L M. Effect of martensite and hydrogen on SCC of stainless steels and alloy 600[C]//Corrosion/2001,Houston:NACE,2001,:228.
【24】罗渝然,俞书勤,张祖德,等. 再谈什么是活化能-Arrhenius活化能的定义、解释、以及容易混淆的物理量[J]. 大学化学,2010,25(3):35-42.
【25】L Z P,SHOJI T,XUE H,et al. Synergistic effects of local strain-hardening and dissolved oxygen on SCC of 316NG weld heat-affected zones in simulated BWR environments[J]. J Nuclear Materials,2012,423:28-39.
【26】NAUMOV G B,RYZHENKO B N,KHODAKOVSKY I L,et al. Handbook of Thermodynamic Data[M]. Menlo Park US Geological Survey,1974.
【27】VANKEERBERGHEN M,MACDONALD D D. Predicting crack growth rate vs.temperature behaviour of Type 304 stainless steel in dilute sulphuric acid solutions[J]. Corrosion Science,2002,44:1425-1441.
【28】SHREIR L L,JARMAN R A,BURSTEIN G T. Corrosion,Vol.1[M]. Boston: Butterworth-Heinemann,1994:2:19-20.
【29】ASM handbook volume 13A:Corrosion fundamentals,testing,and protection[C]//USA:ASM,2003.
【30】L Z P,TAKEDA Y,SHOJI T. Some fundamental aspects of thermally activated processes involved in stress corrosion cracking in high temperature aqueous environments[J]. J Nuclear Materials,2008,383:92-96.
【2】JIANG X C,STAEHLE R W. On the activation energy in the chemical-mechanical correlation model[J]. Corrosion,1997,53:869-879.
【3】FORD F P,POVICH M J. The effect of oxygen temperature combinations on the stress corrosion susceptibility of sensitized type 304 stainless steel in high purity water[J]. Corrosion,1979,35:569-574.
【4】ANDRESEN P L. Effects of temperature on crack growth rate in sensitized type 304 stainless steel and alloy 600[J]. Corrosion,1993,49:714-725.
【5】AGRAWAL A K,BEGLEY G A,STAEHLE R W. Stress corrosion of sensitized and quench annealed type 304 stainless steels in high purity water[C]//Corrosion/78,Houston:NACE,1978:187.
【6】RUTHER W E,SOPPET W K,KASSNER T F. Effect of temperature and ionic impurities at very low concentrations on stress corrosion cracking of aisi 304 stainless steel[J]. Corrosion,1988,44:791-799.
【7】WEEKS J R,VYAS B,ISAACS H S. Environmental factors influencing stress corrosion cracking in boiling water reactors[J]. Corrosion Science,1985,25:757-768.
【8】HALE D A. The effect of bwr startup environments on crack growth in structural alloys[J]. J Engineering Materials and Technology-Transactions ASME,1986,108:44-49.
【9】MAGDOWSKI R,SPEIDEL M O. Effect of temperature on stress corrosion crack growth in austenitic stainless steels exposed to water[C]//Corrosion/90,Houston:NACE,1990,291.
【10】ANDRESEN P L,SEEMAN R A. Effects of temperature and corrosion potential on SCC[C]//Proc.15th Int.Conf.Environmental Degradation Materials Nulcear Power Systems-Water Reactors,Colorado:[s.n.],2011:849.
【11】JENSSEN A,JANSSON C. Effects of temperature on crack growth rate in sensitized type 304 stainless steel in pure and sulfate bearing BWR Environments[C]//Proc.10th Int.Conf.Environmental Degradation Materials Nuclear Power Systems-Water Reactors.Colorado:[s.n.],NACE,2001.CDROM.
【12】STJRNSTER J,JENSSEN A,JANSSON C,et al. The effect of temperature on the crack growth rates of stainless steel and Ni-alloys in simulated BWR environments[C]//Proc.15th Int.Conf.Environmental Degradation Materials Nulcear Power Systems-Water Reactors,Colorado:TMS,2011:827.
【13】STJRNSTER J,JENSSEN A,BENGTSSON B,et al. The effect of temperature on the crack growth rate of sensitized stainless steel in BWR normal water chemistry with sulfate[C]//Proc.16th Int.Conf.Environmental Degradation Materials Nuclear Power Systems-Water Reactors,Asheville:NACE,2013,CD-ROM.
【14】L Z P,KAI A,ITO Y,et al. SCC growth behavior of cold worked 316l stainless steel in oxygenated pure water at different temperatures[C]//Proc.52nd Japan Conf.Materials and Environments.Sapporo:JSCE,2005:205.
【15】L Z P,SHOJI T,TAKEDA Y,et al. Memory effects and steady state growth kinetics for stress corrosion cracking of cold worked 316l stainless steel in high temperature pure water[C]//Proc.13th Int.Conf.Environmental Degradation Materials Nuclear Power Systems-Water Reactors,Whistler:CNS,2007.CD-ROM.
【16】L Z P,SHOJI T,TAKEDA Y,et al. Effects of loading mode and temperature on stress corrosion cracking growth behavior of strain-hardened 316l stainless steels in oxygenated pure water[C]//Proc.13th Int.Conf.Environmental Degradation Materials Nuclear Power Systems-Water Reactors.Whistler:CNS，2007.CD-ROM.
【17】L Z P,SHOJI T,TAKEDA Y,et al. Effects of loading mode and temperature on stress corrosion cracking growth rates of a cold-worked type 316L stainless steel in oxygenated pure water[J]. Corrosion,2007,63:1021.
【18】L Z P,HOJI T S,TAKEDA Y,et al. Transient and steady state crack growth kinetics for stress corrosion cracking of a cold worked 316L stainless steel in oxygenated pure water at different temperatures[J]. Corrosion Science,2008,50:561-575.
【19】L Z P,SHOJI T,TAKEDA Y,et al. The dependency of the crack growth rate on the loading pattern and temperature in stress corrosion cracking of strain-hardened 316L stainless steels in a simulated BWR environment[J]. Corrosion Science,2008,50:698-712.
【20】L Z P,SHOJI T,YAMAZAKI S. Effects of loading mode and water chemistry on stress corrosion cracking of 316L stainless steel in simulated PWR environments[C]//14th Int.Conf.Environ.Degradation of Materials Nuclear Power Systems-Water Reactors. Virginia Beach:ANS,2009:217.
【21】SHOJI T,LI G F,KWON J H,et al. Quantification of yield strength effects on IGSCC of austenitic stainless steels in high temperature waters[C]//Proc.11th Int.Conf.Environmental Degradation Materials Nuclear Power Systems-Water Reactors.Houston:ANS,2003:834.
【22】ARIOKA K,YAMADA T,TERACHI T,et al. Temperature,potential and sensitization effects on intergranular crack growth and crack-tip appearance of cold worked 316[C]//Proc.13th Int.Conf.Environmental Degradation Materials Nuclear Power Systems-Water Reactors.whistler:CNS,2007:CD-ROM.
【23】ANDRESEN P L,ANGELIU T M,YOUNG L M. Effect of martensite and hydrogen on SCC of stainless steels and alloy 600[C]//Corrosion/2001,Houston:NACE,2001,:228.
【24】罗渝然,俞书勤,张祖德,等. 再谈什么是活化能-Arrhenius活化能的定义、解释、以及容易混淆的物理量[J]. 大学化学,2010,25(3):35-42.
【25】L Z P,SHOJI T,XUE H,et al. Synergistic effects of local strain-hardening and dissolved oxygen on SCC of 316NG weld heat-affected zones in simulated BWR environments[J]. J Nuclear Materials,2012,423:28-39.
【26】NAUMOV G B,RYZHENKO B N,KHODAKOVSKY I L,et al. Handbook of Thermodynamic Data[M]. Menlo Park US Geological Survey,1974.
【27】VANKEERBERGHEN M,MACDONALD D D. Predicting crack growth rate vs.temperature behaviour of Type 304 stainless steel in dilute sulphuric acid solutions[J]. Corrosion Science,2002,44:1425-1441.
【28】SHREIR L L,JARMAN R A,BURSTEIN G T. Corrosion,Vol.1[M]. Boston: Butterworth-Heinemann,1994:2:19-20.
【29】ASM handbook volume 13A:Corrosion fundamentals,testing,and protection[C]//USA:ASM,2003.
【30】L Z P,TAKEDA Y,SHOJI T. Some fundamental aspects of thermally activated processes involved in stress corrosion cracking in high temperature aqueous environments[J]. J Nuclear Materials,2008,383:92-96.
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