核用传热管表面划伤致应力腐蚀失效问题及研究进展
An Overview on the Stress Corrosion Cracking Caused by Scratches on Steam Generator Tubes
摘 要
综述了金属表面划伤的理论模型、划伤区的变形特点、影响因素及其对应力腐蚀影响的研究进展，介绍了压水堆核电站传热管的服役环境和表面划伤案例、来源及工程对策，讨论了表面划伤对蒸汽发生器传热管应力腐蚀失效的影响及研究进展。总结现有研究中亟待解决的问题，提出对进一步完善表面划伤理论模型、深入认识划伤影响区损伤特点和应力腐蚀机制、传热管表面划伤安全阈值评估、表面修复工艺等研究方向的展望。
变形
核电
传热管
应力腐蚀
scratch
deformation
nuclear power
steam generator tube
stress corrosion
Abstract
This paper summarizes the theoretical model of scratches on the metal surface, the characteristics of the deformation zone caused by scratch and its impacts on stress corrosion cracking. The failure cases caused by scratches on steam generator tubes in pressurized water reactor nuclear power plants are introduced, and so are the sources of surface scratches and the corresponding repair methods or strategies. The effects of surface scratches on the stress corrosion failure of steam generator tubes and the research progress are discussed. The potential research topics and directions in the future are also proposed, such as further improving the theoretical model of surface scratches, deepening the understanding of the damage characteristics and stress corrosion mechanism in the affected area by scratches, the safety scratch threshold evaluation and surface repair methods.
中图分类号 TG174 DOI 10.11973/fsyfh-202009001
所属栏目 核电设备的腐蚀与防护
基金项目 国家自然科学基金（51771211）；国家重点研发计划（2019YFB1900904）
收稿日期 2020/5/10
修改稿日期
网络出版日期
作者单位点击查看
引用该论文: WU Bin,MENG Fanjiang,HE Guangqing,MING Hongliang,ZHANG Zhiming,WANG Jianqiu. An Overview on the Stress Corrosion Cracking Caused by Scratches on Steam Generator Tubes[J]. Corrosion & Protection, 2020, 41(9): 1
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参考文献
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【2】SINHA S K. 180 Years of scratch testing[J]. Tribology International,2006,39(2):61-68.
【3】WILLIAMS J A. Analytical models of scratch hardness[J]. Tribology International,1996,29(8):675-694.
【4】RUDERMANN Y,IOST A,BIGERELLE M. Scratch tests to contribute designing performance maps of multilayer polymeric coatings[J]. Tribology International,2011,44(5):585-591.
【5】LEE Y H,PARK J H,KIM I H,et al. Enhanced wear resistance of CrAl-coated cladding for accident-tolerant fuel[J]. Journal of Nuclear Materials,2019,523:223-230.
【6】WANG J Z,LI X H,WANG J Q,et al. Development of a scratch electrode system in high temperature high pressure water[J]. Corrosion Science,2015,95:125-132.
【7】GONG J L,LIPOMI D J,DENG J D,et al. Micro and nanopatterning of inorganic and polymeric substrates by indentation lithography[J]. Nano Letters,2010,10(7):2702-2708.
【8】DALMAU A,RMILI W,JOLY D,et al. Tribological behavior of new martensitic stainless steels using scratch and dry wear test[J]. Tribology Letters,2014,56(3):517-529.
【9】WREDENBERG F,LARSSON P L. Scratch testing of metals and polymers:experiments and numerics[J]. Wear,2009,266(1/2):76-83.
【10】JIANG H,BROWNING R,SUE H J. Understanding of scratch-induced damage mechanisms in polymers[J]. Polymer,2009,50(16):4056-4065.
【11】DOMAN D A,BAUER R,WARKENTIN A. Experimentally validated finite element model of the rubbing and ploughing phases in scratch tests[J]. Proceedings of the Institution of Mechanical Engineers,Part B:Journal of Engineering Manufacture,2009,223(12):1519-1527.
【12】HAHN R S,LINDSAY R P. On the rounding-up process in high-production internal grinding machines by digital computer simulation[M]//Proceedings of the Twelfth International Machine Tool Design and Research Conference. London:Macmillan Education,1972:235-240.
【13】TAKENAKA N. A study on the grinding action by single grit[J]. Annals of the CIRP,1966,13(1):183-190.
【14】DOMAN D A. Rubbing & plowing phases in single grain grinding[M]. Ann Arbor:ProQuest,2009.
【15】KANNAPPAN S,MALKIN S. Effects of grain size and operating parameters on the mechanics of grinding[J]. Journal of Engineering for Industry,1972,94(3):833-842.
【16】SHAW M C. Energy conversion in cutting and grinding[J]. CIRP Annals,1996,45(1):101-104.
【17】ROWE W B. Grinding technology-theory and applications of machining with abrasives[J]. Tribology International,1990,23(6):443.
【18】GHOSH S,CHATTOPADHYAY A B,PAUL S. Modelling of specific energy requirement during high-efficiency deep grinding[J]. International Journal of Machine Tools and Manufacture,2008,48(11):1242-1253.
【19】WANG H,SUBHASH G. An approximate upper bound approach for the single-grit rotating scratch with a conical tool on pure metal[J]. Wear,2002,252(11/12):911-933.
【20】GODDARD J,WILMAN H. A theory of friction and wear during the abrasion of metals[J]. Wear,1962,5(2):114-135.
【21】BRINKSMEIER E,AURICH J C,GOVEKAR E,et al. Advances in modeling and simulation of grinding processes[J]. CIRP Annals,2006,55(2):667-696.
【22】BUCAILLE J,FELDER E,HOCHSTETTER G. Mechanical analysis of the scratch test on elastic and perfectly plastic materials with the three-dimensional finite element modeling[J]. Wear,2001,249(5/6):422-432.
【23】MACKERLE J. Finite-element analysis and simulation of machining:a bibliography (1976-1996)[J]. Journal of Materials Processing Technology,1999,86(1/2/3):17-44.
【24】DOMAN D A,WARKENTIN A,BAUER R. Finite element modeling approaches in grinding[J]. International Journal of Machine Tools and Manufacture,2009,49(2):109-116.
【25】WASMER K,PARLINSKA-WOJTAN M,GASSILLOUD R,et al. Plastic deformation modes of gallium arsenide in nanoindentation and nanoscratching[J]. Applied Physics Letters,2007,90(3):031902.
【26】BEN TKAYA M,ZIDI M,MEZLINI S,et al. Influence of the attack angle on the scratch testing of an aluminium alloy by cones:experimental and numerical studies[J]. Materials & Design,2008,29(1):98-104.
【27】WILLIAMS J A,XIE Y. The generation of wear surfaces by the interaction of parallel grooves[J]. Wear,1992,155(2):363-379.
【28】ELWASLI F,ZEMZEMI F,MKADDEM A,et al. A 3D multi-scratch test model for characterizing material removal regimes in 5083-Al alloy[J]. Materials & Design,2015,87:352-362.
【29】DAI H F,LI S B,CHEN G Y. Molecular dynamics simulation of subsurface damage mechanism during nanoscratching of single crystal silicon[J]. Proceedings of the Institution of Mechanical Engineers,Part J:Journal of Engineering Tribology,2019,233(1):61-73.
【30】RANDALL N X,FAVARO G,FRANKEL C H. The effect of intrinsic parameters on the critical load as measured with the scratch test method[J]. Surface and Coatings Technology,2001,137(2/3):146-151.
【31】GASSILLOUD R,BALLIF C,GASSER P,et al. Deformation mechanisms of silicon during nanoscratching[J]. Physica Status Solidi (a),2005,202(15):2858-2869.
【32】LIN L,BLACKMAN G S,MATHESON R R. Quantitative characterization of scratch and mar behavior of polymer coatings[J]. Materials Science and Engineering:A,2001,317(1/2):163-170.
【33】ADAMS M J,ALLAN A,BRISCOE B J,et al. An experimental study of the nano-scratch behaviour of poly (methyl methacrylate)[J]. Wear,2001,251:1579-1583.
【34】RABINOWICZ E,TANNER R I. Friction and wear of materials[J]. Journal of Applied Mechanics,1966,33(2):479.
【35】DIERCKS D R,SHACK W J,MUSCARA J. Overview of steam generator tube degradation and integrity issues[J]. Nuclear Engineering and Design,1999,194(1):19-30.
【36】CRUM J R,SCARBERRY R C. Corrosion testing of INCONEL alloy 690 for PWR steam generators[J]. Journal of Materials for Energy Systems,1982,4(3):125-130.
【37】ZINKLE S J,WAS G S. Materials challenges in nuclear energy[J]. Acta Materialia,2013,61(3):735-758.
【38】LU Y. Effect of hazardous impurities on steam generator tube degradation[C]//18th International Conference on Nuclear Engineering. Xi'an:American Society of Mechanical Engineers Digital Collection,2010:283-291.
【39】LU B T,LUO J L,LU Y C. A mechanistic study on lead-induced passivity-degradation of nickel-based alloy[J]. Journal of the Electrochemical Society,2007,154(8):C379.
【40】STAEHLE R W. Bases for predicting the earliest penetrations due to SCC for alloy 600 on the secondary side of PWR steam generators[M]. Washington DC:Nuclear Regulatory Commission,2001.
【41】臧希年. 核电厂系统及设备[M]. 北京:清华大学出版社,2010.
【42】KUCHIRKA P J,BLASZKIEWICZ M,BYERS W A,et al. EPRI report TR-106863:Oconee 2 steam generator tube examination[R]. EPRI.[S.l.]:[s.n.],1997.
【43】SYKES L J,SHERBURNE P A. EPRI report TR-106484:Analysis of steam generator tubing from oconee Unit 1 nuclear station[R]. EPRI.[S.l.]:[s.n.],1997.
【44】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.
【45】MOUGINOT R,SARIKKA T,HEIKKILÄ M,et al. Thermal ageing and short-range ordering of Alloy 690 between 350 and 550℃[J]. Journal of Nuclear Materials,2017,485:56-66.
【46】MOUGINOT R,SARIKKA T,HEIKKILÄ M,et al. Development of short-range order and intergranular carbide precipitation in alloy 690 TT upon thermal ageing[M]//The Minerals,Metals & Materials Series. Cham:Springer International Publishing,2017:321-334.
【47】YOUNG G A. Long range ordering in model Ni-Cr-X alloys[C]//Proceedings of the International Symposium Fontevraud 8 on the Contribution of Materials Investigations and Operating Experience to LWRs' Safety,Performance and Reliability. Avignon:[s.n.],2014.
【48】丁训慎. 蒸汽发生器传热管的破损及其监督和检查[J]. 动力工程,1997(6):79-85.
【49】李翠翠,和广庆. 核电蒸汽发生器胀接接头质量事故分析及应对措施研究[J]. 压力容器,2019,36(11):70-73.
【50】SUOMINEN F M L,KLASSEN R J,MCINTYRE N S,et al. Texture,residual strain,and plastic deformation around scratches in alloy 600 using synchrotron X-ray Laue micro-diffraction[J]. Journal of Nuclear Materials,2008,374(3):482-487.
【51】孟凡江,王俭秋,韩恩厚,等. 690TT合金划痕显微组织及划伤诱发的应力腐蚀[J]. 金属学报,2011,47(7):839-846.
【52】ANDRESEN P L,FORD F. Fundamental modeling of environmental cracking for improved design and lifetime evaluation in BWRs[J]. International Journal of Pressure Vessels and Piping,1994,59(1/2/3):61-70.
【53】FORD F P. Quantitative prediction of environmentally assisted cracking[J]. Corrosion,1996,52(5):375-395.
【54】ARIOKA K,YAMADA T,MIYAMOTO T,et al. Dependence of stress corrosion cracking of alloy 690 on temperature,cold work,and carbide precipitation-role of diffusion of vacancies at crack tips[J]. Corrosion,2011,67(3):035006-1-035006-18.
【55】HOU J,PENG Q J,LU Z P,et al. Effects of cold working degrees on grain boundary characters and strain concentration at grain boundaries in Alloy 600[J]. Corrosion Science,2011,53(3):1137-1142.
【56】ANDRESEN P L,MORRA M M,AHLUWALIA K. SCC of alloy 690 and its weld metals[M]//Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. Cham:Springer International Publishing,2011:161-178.
【57】WANG S,SHOJI T,KAWAGUCHI N. Initiation of environmentally assisted cracking in high-temperature water[J]. Corrosion,2005,61(2):137-144.
【58】ARIOKA K,ⅡJIMA Y,MIYAMOTO T. Rapid nickel diffusion in cold-worked carbon steel at 320-450℃[J]. Philosophical Magazine,2015,95(32):3577-3589.
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