核电用结构材料SCC裂纹扩展的研究现状
The Research Status of SCC Crack Propagation in Structural Materials of Nuclear Reactors
摘 要
详细介绍了核电用结构材料应力腐蚀开裂（SCC）裂纹扩展行为研究的最新进展，总结了应力因素、材料因素和水电化学因素等对SCC裂纹扩展的影响，在溶解滑移模型的基础上解释了不同影响因素对裂纹扩展的影响机理，并提出了未来研究的方向与趋势。
应力腐蚀
裂纹扩展
影响因素
structural material
stress corrosion
crack propagation
influencing factor
Abstract
The research advances in crack propagation behavior of stress corrosion cracking (SCC) in structural materials of nuclear reactors are introdnced. The effects of hydrochemical, mechanical and material factors on the crack propagation behavior of SCC are summarized. The influence mechanism of different influencing factors on crack propagation based on the slip-dissolution-oxidation model is explained, furthermore, the trend of further research of SCC crack propagation behavior is predicted.
中图分类号 TG174 DOI 10.11973/fsyfh-201903001
所属栏目 专论
基金项目
收稿日期 2017/9/12
修改稿日期
网络出版日期
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引用该论文: ZHANG Keqian,TANG Zhanmei,HU Shilin,ZHANG Pingzhu. The Research Status of SCC Crack Propagation in Structural Materials of Nuclear Reactors[J]. Corrosion & Protection, 2019, 40(3): 157
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参考文献
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【47】唐占梅,胡石林,张平柱. 氯和氧对304N在高温水中应力腐蚀开裂的影响[J]. 原子能科学技术,2012,46(11):1296.
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【55】ANDRESEN P L. Effects of transients in water chemistry,temperature,and loading on intergranular stress corrosion cracking of AISI 304 stainless steel[J]. Corrosion,1986,42(3):169-180.
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【2】VERMILYEA D A. A theory for the propagation of stress corrosion cracks in metals[J]. Journal of the Electrochemical Society,1972,119(4):405-407.
【3】TURNBULL A. Modelling of environment assisted cracking[J]. Corrosion Science,1993,34(6):921-960.
【4】FORD F P. Quantitative prediction of environmentally assisted cracking[J]. Corrosion,1996,52(5):375-395.
【5】MACDONALD D D,URQUIDI-MACDONALD M. A coupled environment model for stress corrosion cracking in sensitized type 304 stainless steel in LWR environments[J]. Corrosion Science,1991,32(1):51-81.
【6】ELIAZ N,SHACHAR A,TAL B,et al. Characteristics of hydrogen embrittlement,stress corrosion cracking and tempered martensite embrittlement in high-strength steels[J]. Engineering Failure Analysis,2002,9(2):167-184.
【7】FORD F P,TAYLOR D F,ANDRESEN P L,et al. Environmentally controlled cracking of stainless and low alloy steels in light water reactor environments[R]. NP-5064M,Final Report. [S.l.]:EPRI,1987.
【8】ANDRESEN P L,FORD F P. Life prediction by mechanistic modeling and system monitoring of environmental cracking of iron and nickel alloys in aqueous systems[J]. Materials Science and Engineering:A,1988,103(1):167-184.
【9】小若正伦. 金属的腐蚀破坏与防蚀技术[M]. 袁宝林等译. 北京:化学工业出版社,1988.
【10】BERGE P,DONATI J R,PRIEUX B,et al. Caustic stress corrosion of Fe-Cr-Ni austenitic alloys[J]. Corrosion,1977,33(12):425-435.
【11】OVERMAN R F. Using radioactive tracers to study chloride stress corrosion cracking of stainless steels[J]. Corrosion,1966,22(2):48-52.
【12】郑文龙,于青. 钢的环境敏感断裂[M]. 北京:化学工业出版社,1988:34-35.
【13】丁训慎. 核电站蒸汽发生器传热管的腐蚀与防护[J]. 腐蚀与防护,2000,21(1):15-37.
【14】丁训慎. 核电站蒸汽发生器传热管二次侧晶间腐蚀和晶间应力腐蚀及防护[J]. 腐蚀与防护,2002,23(10):441-444.
【15】徐雪莲,龚嶷,刘晓强,等. 压水堆核电厂结构材料腐蚀防护设计与老化管理[J]. 腐蚀与防护,2016,37(7):534-543.
【16】ARIOKA K,YAMADA T,MIYAMOTO T,et al. Intergranular stress corrosion cracking growth behavior of Ni-Cr-Fe alloys in pressurized water reactor primary water[J]. Corrosion,2014,70(7):695-707.
【17】ANDRESEN P L. Effects of temperature on crack growth rate in sensitized type 304 stainless steel and alloy 600[J]. Corrosion,1993,49(9):714-725.
【18】王荣山,徐超亮,黄平,等. 堆内构件用不锈钢辐照加速应力腐蚀开裂研究进展[J]. 科技导报,2014,32(20):79-83.
【19】RAO B R,RAO K P,IYER K J L. Effect of chemical composition and ferrite content on room temperature SCC behavior of austenitic weld metals[J]. Corrosion,1993,49(3):248-255.
【20】YOO S C,CHOI K J,KIM T,et al. Microstructural evolution and stress-corrosion-cracking behavior of thermally aged Ni-Cr-Fe alloy[J]. Corrosion Science,2016,111:39-51.
【21】LI S,WANG Y,WANG H,et al. Effects of long-term thermal aging on the stress corrosion cracking behavior of cast austenitic stainless steels in simulated PWR primary water[J]. Journal of Nuclear Materials,2016,469:262-268.
【22】LI N,SHI S Q,LUO J,et al. Lead-induced stress corrosion cracking behavior of mechanically surface-treated alloy 690[J]. Materials Research Letters,2016,4(3):180-184.
【23】CHEN J,LU Z,XIAO Q,et al. The effects of cold rolling orientation and water chemistry on stress corrosion cracking behavior of 316L stainless steel in simulated PWR water environments[J]. Journal of Nuclear Materials,2016,472:1-12.
【24】候娟,彭群家,庄子哲熊,等. 镍基合金焊接过渡区微观结构及应力腐蚀行为研究[J]. 金属学报,2016,46(10):1258-1266.
【25】LU Z,SHOJI T,MENG F,et al. Characterization of microstructure and local deformation in 316NG weld heat-affected zone and stress corrosion cracking in high temperature water[J]. Corrosion Science,2011,53(5):1916-1932.
【26】ZHU R,WANG J,ZHANG L,et al. Stress corrosion cracking of 316L HAZ for 316L stainless steel/Inconel 52M dissimilar metal weld joint in simulated primary water[J]. Corrosion Science,2016,112:373-384.
【27】ZHU R,WANG J,ZHANG Z,et al. Stress corrosion cracking of fusion boundary for 316L/52M dissimilar metal weld joints in borated and lithiated high temperature water[J]. Corrosion Science,2017,120:219-230.
【28】GARCÍA C,MARTÍN F,DE TIEDRA P,et al. Effects of prior cold work and sensitization heat treatment on chloride stress corrosion cracking in type 304 stainless steels[J]. Corrosion Science,2001,43(8):1519-1539.
【29】TSUBOTA M,KANAZAWA Y,INOUE H. The effect of cold worked on the SCC susceptibility of austenitic stainless steels[C]//NACE International. Houston TX (United States):[s.n.],1995:519-527.
【30】KUNIYA J,FUKAI M,MASAOKA I. Hydrogen induced cracking in cold worked,creviced type 304 austenitic stainless steel[C]//Environmental Degradation of Materials in Nuclear Power Systems——Water Reactors.[S.l.]:[s.n.],1987:383-388.
【31】ANDRESEN P L. Similarity of cold work and radiation hardening in enhancing yield strength and SCC growth of stainless steel in hot water[C]//Corrosion 2002,NACE International.[S.l.]:[s.n.],2002.
【32】MENG F,LU Z,SHOJI T,et al. Stress corrosion cracking of unidirectionally cold worked 316NG stainless steel in simulated PWR primary water with various dissolved hydrogen concentrations[J]. Corrosion Science,2011,53(8):2558-2565.
【33】YAGUCHI S,YONEZAWA T. Intergranular stress corrosion cracking growth perpendicular to fatigue pre-cracks in T-L oriented compact tension specimens in simulated pressurized water reactor primary water[J]. Corrosion Science,2014,86:326-336.
【34】GUERRE C,LAGHOUTARIS P,CHẼNE J,et al. Stress corrosion cracking of alloy 600 in PWR primary water:influence of chromium,hydrogen and oxygen diffusion[C]//Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. Springer:[s.n.],2011:1477-1490.
【35】TSENG C M,TSAI W T. Environmentally assisted cracking behavior of single and dual phase stainless steels in hot chloride solutions[J]. Materials Chemistry and Physics,2004,84(1):162-170.
【36】MACDONALD K A,AIGNER H. Some case studies of failed austenitic drill collars[J]. Engineering Failure Analysis,1996,3(4):281-297.
【37】NISHIMURA R,MUSALAM I,MAEDA Y. The effect of sensitizing temperature on stress corrosion cracking of type 316 austenitic stainless steel in hydrochloric acid solution[J]. Corrosion Science,2002,44(6):1343-1360.
【38】TURNBULL A,RYAN M,WILLETTS A,et al. Corrosion and electrochemical behaviour of 316L stainless steel in acetic acid solutions[J]. Corrosion Science,2003,45(5):1051-1072.
【39】CONGLETON J,YANG W. The effect of applied potential on the stress corrosion cracking of sensitized type 316 stainless steel in high temperature water[J]. Corrosion Science,1995,37(3):429-444.
【40】HERMS E,OLIVE J M,PUIGGALI M. Hydrogen embrittlement of 316L type stainless steel[J]. Materials Science and Engineering:A,1999,272(2):279-283.
【41】ZHANG L,WANG J. Effect of dissolved oxygen content on stress corrosion cracking of a cold worked 316L stainless steel in simulated pressurized water reactor primary water environment[J]. Journal of Nuclear Materials,2014,446(1):15-26.
【42】DU D,CHEN K,LU H,et al. Effects of chloride and oxygen on stress corrosion cracking of cold worked 316/316L austenitic stainless steel in high temperature water[J]. Corrosion Science,2016,110:134-142.
【43】ZHANG L,WANG J. Effect of dissolved oxygen content on stress corrosion cracking of a cold worked 316L stainless steel in simulated pressurized water reactor primary water environment[J]. Journal of Nuclear Materials,2014,446(1):15-26.
【44】LOU X,ANDRESEN P L,LIAN T,et al. Effect of ppb levels of chloride on the stress corrosion cracking of pressure vessel steel[C]//CORROSION 2016. [S.l.]:NACE International,2016.
【45】唐占梅,胡石林,张平柱. 316 LN在模拟压水堆一回路异常水化学条件下的应力腐蚀敏感性研究[J]. 原子能科学技术,2014,48(11):1960-1964.
【46】唐占梅,胡石林,张平柱. 316Ti在含氯离子300 ℃高温水中的应力腐蚀开裂[J]. 中国腐蚀与防护学报,2012,32(4):291-295.
【47】唐占梅,胡石林,张平柱. 氯和氧对304N在高温水中应力腐蚀开裂的影响[J]. 原子能科学技术,2012,46(11):1296.
【48】张平柱,刘兴华,胡石林,等. 316Ti不锈钢环境敏感断裂起裂时间研究[J]. 原子能科学技术,1999,33(2):141-146.
【49】ANDRESEN P L. Perspective and direction of stress corrosion cracking in hot water[C]//Proc. 10th Int. Symp. Environmental Degradation of Materials in Nuclear Power Systems-Water Radiolysis. Lake Tahoe:[s.n.],2001:5-9.
【50】ANDRESEN P L,YOUNG L M. Characterization of the roles of electrochemistry,convection and crack chemistry in stress corrosion cracking[C]//Corrosionj 1995. Houston,TX (United States):NACE International,1995.
【51】ANDRESEN P L. Emerging issues and fundamental processes in environmental cracking in hot water[J]. Corrosion,2008,64(5):439-464.
【52】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.
【53】TAYLOR D F. Crevice corrosion of alloy 600 in high temperature aqueous environments[J]. Corrosion,1979,35(12):550-559.
【54】TURNBULL A. Modelling of crack chemistry in sensitized stainless steel in boiling water reactor environments[J]. Corrosion Science,1997,39(4):789-805.
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