Fatigue Crack Growth of Alloy 690 Tubing

Abstract

Abstract:

Abstract： Fatigue crack growth rate (FCGR) data of three kinds of alloy 690 by different manufacturing process were generated in air at room temperature and 325 ℃ using the pin-loading tension (PLT) specimen and direct current potential drop (DCPD) method. The testing data were modeled with the Paris-Erdogan equation, and a linear relation between log(da/dt) and log(ΔK) was observed, which indicated good veracity and reliability of results. The threshold stress intensity factor amplitude ΔKth of the three alloys was predicted from the fatigue crack growth curve at 325 ℃, and material B has the highest ΔKth, showing best fatigue resistance performance. Scanning electron microscopy (SEM) examination of the fatigue fracture surfaces revealed transgranular attack, and the transgranular regions of the fatigue fracture surface were covered with striationlike features, indicative of micro-plastic deformantion.

Key words: alloy 690, fatigue crack growth rate, pin-loading tension, direct current potential drop

CLC Number:

TL 341

CHEN Kai 1，DU Donghai1，LU Hui1，ZHANG Lefu1,SHI Xiuqiang2，XU Xuelian2. Fatigue Crack Growth of Alloy 690 Tubing[J]. Journal of Shanghai Jiaotong University, 2014, 48(11): 1639-1643.

References

［1］Young B A, Gao X, Srivatsan T S, et al. An investigation of the fatigue crack growth behavior of INCONEL 690［J］. Materials Science and Engineering: A, 2006, 416(1): 187191.

［2］Li X, Wang J, Han E H, et al. Corrosion behavior for Alloy 690 and Alloy 800 tubes in simulated primary water［J］. Corrosion Science, 2013, 67: 169178.

［3］Chai G, Liu P, Zhou N, et al. Low and high cycle fatigue behavior of nickelbase alloy at high temperatures［J］. Procedia Engineering, 2013, 55: 671676.

［4］MacDonald P E, Shah V N, Ward L W, et al. Steam generator tube failures［R］. Nuclear Regulatory Commission, Washington, DC (United States). Div. of Safety Programs; Idaho National Engineering Lab., Idaho Falls, ID (United States), 1996.

［5］AlRubaie K S, Godefroid L B, Lopes J A M. Statistical modeling of fatigue crack growth rate in Inconel alloy 600［J］. International Journal of Fatigue, 2007, 29(5): 931940.

［6］Grigoriev V, Josefsson B, Lind A, et al. A pinloading tension test for evaluation of thinwalled tubular materials［J］. Scripta Metallurgica et Materialia, 1995, 33(1): 109114.

［7］Yagnik S, Ramasubramian N, Grigoriev V, et al. RoundRobin testing of fracture toughness characteristics of thinwalled tubing［J］. Journal of ASTM International, 2008, 5(2): 121.

［8］Grigoriev V, Jakobsson R. Delayed hydrogen cracking velocity and Jintegral measurements on irradiated BWR cladding［J］. ASTM Special Technical Publication, 2006, 1467: 711.

［9］Coleman C, Grigoriev V, Inozemtsev V, et al. Delayed hydride cracking in zircaloy fuel cladding—An IAEA coordinated research programme［J］. Nuclear Engineering and Technology, 2009, 41: 18.

［10］Seok C S, Bae B K, Koo J M. DC potential drop method for evaluating material degradation［J］. KSME International Journal, 2004, 18(8): 13681374.

［11］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.

［12］Merah N. Detecting and measuring flaws using electric potential techniques［J］. Journal of Quality in Maintenance Engineering, 2003, 9(2): 160175.

［13］Andresen P L, Morra M M. IGSCC of nonsensitized stainless steels in high temperature water［J］. Journal of Nuclear Materials, 2008, 383(1): 97111.

［14］Paris P C, Erdogan F. A critical analysis of crack propagation laws［J］. Journal of Basic Engineering, 1963, 85(4): 528533.

［15］ASTM International. Standard Test Method for Measurement of Fatigue Crack Growth Rates［M］. West Conshohocken: ASTM International, 2011.

[1]	CHEN Kai,DU Donghai,ZHANG Lefu. Corrosion Fatigue Crack Growth Behavior of Alloy 690 in PressurizedWater Reactor Environment [J]. Journal of Shanghai Jiaotong University, 2017, 51(11): 1281-1286.
[2]	WANG Jiamei1，DUAN Zhengang1，ZHANG Lefu1，MENG Fanjiang2，SHI Xiuqiang2. Electrochemical Corrosion Behaviors of Alloy 690 in High-Temperature and Highpressure Water [J]. Journal of Shanghai Jiaotong University, 2016, 50(04): 514-520.