Effect of Reactor Coolant Environment on Fatigue Performance of Alloy 690 Steam Generator Tubes

doi:10.11902/1005.4537.2014.102

Journal of Chinese Society for Corrosion and protection

2015, Vol. 35

Issue (3): 213-219 DOI: 10.11902/1005.4537.2014.102

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Effect of Reactor Coolant Environment on Fatigue Performance of Alloy 690 Steam Generator Tubes

Xiaoqiang LIU¹(

),Xuelian XU¹,Jibo TAN²,Yuan WANG²,Xinqiang WU²,Yuli ZHENG²,Fanjiang MENG¹,En-Hou HAN²

1. Shanghai Nuclear Engineering Research and Design Institute, Shanghai 200233, China
2. Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China

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Abstract

The low cycle fatigue behavior of alloy 690 steam generator tubes in three different environments was investigated, i.e. in air at ambient temperature and 325 ℃ respectively as well as in simulated PWR primary water at 325 ℃. Meanwhile, the influence of dissolved oxygen and strain rate on fatigue life was considered. The results show that the design related with the fatigue life for the alloy 690 steam generator tube is very conservative, and the effect of PWR coolant environment is limited; while the corrosion fatigue life of the alloy 690 is not susceptible to the effect of the dissolve oxygen and strain rate under this test condition. Therefore, it is conferred that the corrosion fatigue behavior may be controlled by film rupture slip/dissolution mechanism.

Key words: corrosion fatigue alloy 690 steam generator tube fatigue design

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	Xiaoqiang LIU
	Xuelian XU
	Jibo TAN
	Yuan WANG
	Xinqiang WU
	Yuli ZHENG
	Fanjiang MENG
	En-Hou HAN

Cite this article:

Xiaoqiang LIU,Xuelian XU,Jibo TAN,Yuan WANG,Xinqiang WU,Yuli ZHENG,Fanjiang MENG,En-Hou HAN. Effect of Reactor Coolant Environment on Fatigue Performance of Alloy 690 Steam Generator Tubes. Journal of Chinese Society for Corrosion and protection, 2015, 35(3): 213-219.

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https://www.jcscp.org/EN/10.11902/1005.4537.2014.102 OR https://www.jcscp.org/EN/Y2015/V35/I3/213

Fig.1 Schematic diagram of boat-shaped specimen

Fig.2 Fatigue ε-N behavior for Alloy 690TT tube in three different environments

Fig.3 Comparison of fatigue ε-N behavior for Alloy 690TT tube with the data published in NUREG CR6909^[8]

Fig.4 Effects of strain rate (a) and dissolved oxygen (b) on fatigue life of 690TT tube in simulated PWR water

Fig.5 Fatigue crack morphologies of 690TT tube in air at room temperature (a), air at 325 ℃ (b) and simulated PWR water (c)

Fig.6 Fatigue fracture surface morphologies of 690TT tube in simulated PWR environment: (a) ε_max=2.0%, (b) ε_max=1.0%

Fig.7 Fatigue fracture surface morphologies of 690TT tube at 1.0% strain amplitude in air at room temperature (a, d), air at 325 ℃ (b, e) and simulated PWR environment (c, f)

Fig.8 EDS analysis of fatigue fracture surface of 690TT tube in air at room temperature (a), air at 325 ℃ (b) and simulated PWR environment (c)

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