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WANG Jiamei, SU Haozhan, CHEN Kai, GUO Xianglong, ZHANG Lefu, WANG Yuanhua, MA Wujiang. Effect of Grain Boundary Carbides and Cold Work on Stress Corrosion Cracking of Alloy 600[J]. Corrosion & Protection, 2022, 43(4): 1-6. DOI: 10.11973/fsyfh-202204001
Citation: WANG Jiamei, SU Haozhan, CHEN Kai, GUO Xianglong, ZHANG Lefu, WANG Yuanhua, MA Wujiang. Effect of Grain Boundary Carbides and Cold Work on Stress Corrosion Cracking of Alloy 600[J]. Corrosion & Protection, 2022, 43(4): 1-6. DOI: 10.11973/fsyfh-202204001

Effect of Grain Boundary Carbides and Cold Work on Stress Corrosion Cracking of Alloy 600

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  • Received Date: June 11, 2020
  • The stress corrosion cracking (SCC) behavior of alloy 600 in simulated pressurized water reactor (PWR) high-temperature water environment was investigated by direct current potential drop (DCPD) on-line monitoring. Analytical electron microscopy was utilized to characterize the cracking process to better understand the cold work and grain boundary (GB) carbides effect. Synergistic effect of GB carbides and cold work on SCC behavior was identified. A beneficial effect of carbides was identified in non-cold worked alloy 600, which was attributed to the physical impediment and reduced GB internal oxidation. In cold worked alloy 600, GB carbides had a detrimental effect due to the combination of the enhanced local strain at GBs and also enhanced GB internal oxidation.
  • [1]
    HWANG S S. Review of PWSCC and mitigation management strategies of Alloy 600 materials of PWRs[J]. Journal of Nuclear Materials,2013,443(1/3):321-330.
    [2]
    STAEHLE R W,GORMAN J A. Quantitative assessment of submodes of stress corrosion cracking on the secondary side of steam generator tubing in pressurized water reactors:Part 1[J]. Corrosion,2003,59(11):931-994.
    [3]
    ZHAO L,CHU F,LUO K,et al. Failure analysis of branch connection on the reactor primary pipeline,Eng. Fail. Anal.,2018(85):137-148.
    [4]
    FÉRON D,GUERRE C,HERMS E,et al. Chapter 9-Stress corrosion cracking of Alloy 600:overviews and experimental techniques,stress corrosion cracking of nickel based alloys in water-cooled nuclear reactors[M].[s.n.],Woodhead Publishing,2016:325-353.
    [5]
    ARIOKA K. 2014 WR Whitney award lecture:change in bonding strength at grain boundaries before long-term SCC initiation[J]. Corrosion,2014,71:403-419.
    [6]
    ECONOMY G,JACKO R J,PEMENT F W. IGSCC behavior of alloy 600 steam generator tubing in water or steam tests above 360℃[J]. Corrosion,1987,43:727-734.
    [7]
    BULISCHECK T S,ROOYEN D V. Stress corrosion cracking of alloy 600 using the constant strain rate test[J]. Corrosion,1981,37:597-607.
    [8]
    ARIOKA K,YAMADA T,MIYAMOTO T,et al. SCC initiation of CW alloy 690TT and alloy 600 in PWR water[C]//Proc. 17th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors Toronto,Canada:CNS,2015.
    [9]
    ARIOKA K. Change in bonding strength at grain boundaries before long-term SCC initiation[J]. Corrosion,2014,71(4):403-419.
    [10]
    SHEN Z,KARAMCHED P,ARIOKA K,et al. Observation and quantification of the diffusion-induced grain boundary migration ahead of SCC crack tips[J]. Corrosion Science,2019,147:163-168.
    [11]
    PERSAUD S Y,KORINEK A,HUANG J,et al. Internal oxidation of Alloy 600 exposed to hydrogenated steam and the beneficial effects of thermal treatment[J]. Corrosion Science,2014,86:108-122.
    [12]
    杜东海,陆辉,陈凯,等. 冷变形316不锈钢在高温水中的应力腐蚀开裂行为[J]. 原子能科学技术,2015,49(11):1977-1983.
    [13]
    CHEN K,WANG J,DU D,et al. dK/da effects on the SCC growth rates of nickel base alloys in high-temperature water[J]. Journal of Nuclear Materials,2018,503:13-21.
    [14]
    KIM Y J,ANDRESEN P L. Data quality,issues,and guidelines for electrochemical corrosion potential measurement in high-temperature water[J]. Corrosion,2003,59(7):584-596.
    [15]
    ANDRESEN P L,HICKLING J,AHLUWALIA A,et al. Effects of hydrogen on stress corrosion crack growth rate of nickel alloys in high-temperature water[J]. Corrosion,2008,64(9):707-720.
    [16]
    ANDRESEN P L,HICKLING J,AHLUWALIA A. Mitigation of PWSCC in nickel-base alloys by optimizing H2[J]. EPRI Final Report,2007,1015288.
    [17]
    ANDRESEN P,CHOU P. Crack initiation of alloy 600 in PWR water[C]//Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. Springer:Cham,2019:121-135.
    [18]
    ZHAI Z,TOLACZKO M,BRUEMMER S. Microstructural effects on SCC initiation in PWR primary water for cold-worked alloy 600[C]//Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. Springer:Cham,2019:217-229.
    [19]
    HOU J,WANG J Q,KE W,et al. Effect of mono-tension and biaxial tension on microstructure and stress corrosion cracking of alloy 690TT[J]. Materials Science and Engineering:A,2009,518(1/2):19-26.
    [20]
    张子龙,夏爽,曹伟,等. 晶界特征对316不锈钢沿晶应力腐蚀开裂裂纹萌生的影响[J]. 金属学报,2016,52(3):313-319.
    [21]
    CASSAGNE T,GELPI A. Crack growth rate measurements on alloy 600 steam generator tubing in primary and hydrogenated AVT water[C]//Proceedings of the Sixth Intl. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors.[S.l.]:[s.n.],1993:679-685.
    [22]
    REBAK R B,SZKLARSKA-SMIALOWSKA Z MCLLREE A R. Effects of pH and stress intensity on crack growth rate in Alloy 600 in lithiated + borated water at high temperatures[C]//Proceedings of the 5th Intl. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. La Grange Park:American Nuclear Society,1991:511-517.
    [23]
    KIM H P,CHOI M J,KIM S W,et al. Effects of grain boundary morphologies on stress corrosion cracking of alloy 600[J]. Archives of Metallurgy and Materials,2017,62(2):1415-1419.
    [24]
    SHEN Z,ARIOKA K,LOZANO-PEREZ S. A mechanistic study of SCC in Alloy 600 through high-resolution characterization[J]. Corrosion Science,2018,132:244-259.
    [25]
    SHEN Z,MEISNAR M,ARIOKA K,et al. Mechanistic understanding of the temperature dependence of crack growth rate in alloy 600 and 316 stainless steel through high-resolution characterization[J]. Acta Materialia,2019,165:73-86.
    [26]
    DONG L,PENG Q,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,2016,107:172-181.
    [27]
    BRUEMMER S M,THOMAS L E. Comparison of IGSCC crack-tip characteristics produced in BWR oxidizing water and BWR hydrogen water chemistry conditions[C]//Proceedings of 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors,[S.l.]:[s.n.],2007.
    [28]
    MORTON D S,MULLEN J V,PLESKO E,et al. Stress corrosion crack growth rate testing of novel composite arrest specimens[C]//Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. Springer:Cham,2011:131-147.

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