304L不锈钢在高温高压水中的腐蚀疲劳裂纹扩展行为
Corrosion Fatigue Crack Growth Behavior of 304L Stainless Steel in High Temperature and High Pressure Water
摘 要
基于直流电压降方法（direct current potential drop，DCPD）测量得到了304L不锈钢在325℃空气和含氧超纯水中的疲劳裂纹扩展速率；采用FORD-ANDRESEN模型、Bechtel Bettis模型和PSI模型进行结果分析比较；用扫描电镜观察了断口形貌。结果表明：低频低载荷下，腐蚀对疲劳的加速作用高达1 000倍，高频高载荷下则只有1.5倍；FORD-ANDRESEN模型对于解释腐蚀疲劳机理和预测腐蚀疲劳裂纹扩展速率更加合理与准确，Bechtel Bettis模型和PSI模型可以对试验结果进行比较，但无法给出各种因素对裂纹扩展的影响；疲劳断口形貌观察到明显的疲劳辉纹，疲劳破坏形式为穿晶断裂。
腐蚀疲劳
裂纹扩展速率
模型
304L stainless steel
corrosion fatigue
crack growth rate
model
Abstract
The fatigue crack growth rate of 304L SS was measured at 325℃ in air and oxygenous ultrapure water based on direct current potential drop (DCPD) method. Results were predicted and analyzed with FORD-ANDRESEN model, Bechtel Bettis model and PSI model. The fatigue fracture surface was observed by scanning electron microscopy (SEM). The results showed that the fatigue crack growth rate was accelerated as high as 1 000x at lower frequency & lower load; while only 1.5x at higher frequency & high load. FORD-ANDRESEN model was more proper and accurate for explaining the mechanism of corrosion fatigue and predicting the corrosion fatigue crack growth rate. Bechtel Bettis model and PSI model could estimate and compare the experimental results, but could give explanation of the effects of various parameters on crack growth. The fatigue fracture surfaces revealed obvious fatigue striations, and fatigue failure was transgranular attack.
中图分类号 TL341 DOI 10.11973/fsyfh-201801004
所属栏目 试验研究
基金项目 大型先进压水堆核电站重大专项资助（2010ZX06004-018）
收稿日期 2016/7/26
修改稿日期
网络出版日期
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引用该论文: CHEN Kai,DU Donghai,LU Hui,ZHANG Lefu. Corrosion Fatigue Crack Growth Behavior of 304L Stainless Steel in High Temperature and High Pressure Water[J]. Corrosion & Protection, 2018, 39(1): 17
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参考文献
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【19】WIRE G L, EVANS W M, MILLS W J. Fatigue crack propagation of 304 stainless steel in high temperature water:additional tests and data correlation[C]//ASME 2005 Pressure Vessels and Piping Conference.[S.l.]:American Society of Mechanical Engineers, 2005:207-222.
【2】CHEN X, JIN D, KIM K S. Fatigue life prediction of type 304 stainless steel under sequential biaxial loading[J]. International Journal of Fatigue, 2006, 28(3):289-299.
【3】SMITH K V. Application of the dissipated energy criterion to predict fatigue crack growth of type 304 stainless steel following a tensile overload[J]. Engineering Fracture Mechanics, 2011, 78(18):3183-3195.
【4】BABU M N, DUTT B S, VENUGOPAL S, et al. On the anomalous temperature dependency of fatigue crack growth of SS 316(N) weld[J]. Materials Science and Engineering:A, 2010, 527(20):5122-5129.
【5】JOHAN S P, MUKHOPADHYAY C K, JAYAKUMAR T, et al. Understanding fatigue crack propagation in AISI 316(N) weld using Elber's crack closure concept:experimental results from GCMOD and acoustic emission techniques[J]. International Journal of Fatigue, 2007, 29(12):2170-2179.
【6】BOWLER N. Theory of four-point direct-current potential drop measurements on a metal plate[J]. Research in Nondestructive Evaluation, 2006, 17(1):29-48.
【7】ANDRESEN P L, HICKLING J, AHLUWALIA K S, et al. Effects of hydrogen on SCC growth rate of Ni alloys in high temperature water[J]. Corrosion, 2008, 64(9):707-720.
【8】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.
【9】CHOPRA O K, RAO A S. A review of irradiation effects on LWR core internal materials-IASCC susceptibility and crack growth rate of austenitic stainless steels[J]. Journal of Nuclear Materials 2011(409):235-256.
【10】DU D, CHEN K, YU L, et al. SCC crack growth rate of cold worked 316L stainless steel in PWR environment[J]. Journal of Nuclear Materials, 2015, 456:228-234.
【11】SHOJI T, TAKAHASHI H, SUZUKI M, et al. A new parameter for characterizing corrosion fatigue crack growth[J]. Journal of Engineering Materials and Technology, 1981, 103(4):298-304.
【12】ANDRESEN P L, FORD F P. Modeling and life prediction of stress corrosion cracking in sensitized stainless steel in high-temperature water[J]. Predictive Capabilities in Environmentally Assisted Cracking, 1985(3):17-38.
【13】ANDRESEN P L. Critical processes to model in predicting stress corrosion response in hot water[J]. Corrosion Science,2005(10):610-629.
【14】FORD F P, EMIGH P W. The prediction of the maximum corrosion fatigue crack propagation rate of the low alloy steel in oxygenated water system at 288℃[J]. Corrosion science, 1985, 25(8):673-692.
【15】FORD F P. Quantitative prediction of environmentally assisted cracking[J]. Corrosion, 1996, 52(5):375-395.
【16】FORD F P, TAYLOR D F, ANDRESEN P L, et al. Corrosion assisted cracking of stainless steel and low alloy steels in LWR environments[R]. Palo Alto:EPRI,1987.
【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】LU Z, TAKEDA Y, SHOJI T. Some fundamental aspects of thermally activated processes involved in stress corrosion cracking in high temperature aqueous environments[J]. Journal of Nuclear Materials, 2008, 383(1):92-96.
【19】WIRE G L, EVANS W M, MILLS W J. Fatigue crack propagation of 304 stainless steel in high temperature water:additional tests and data correlation[C]//ASME 2005 Pressure Vessels and Piping Conference.[S.l.]:American Society of Mechanical Engineers, 2005:207-222.
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