Journal of Shanghai Jiaotong University ›› 2017, Vol. 51 ›› Issue (11): 1281-1286.doi: 10.16183/j.cnki.jsjtu.2017.11.001

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Corrosion Fatigue Crack Growth Behavior of Alloy 690 in PressurizedWater Reactor Environment

CHEN Kai,DU Donghai,ZHANG Lefu   

  1. School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China
  • Online:2017-11-30 Published:2017-11-30

Abstract: Corrosion fatigue crack growth rates of Alloy 690 have been measured in air and simulated pressurizedwater reactor (PWR) environment, and environmental acceleration of fatigue crack growth is observed. The effects of loading parameters including loading ratio R, frequency f and amplitude of stress intensity factors ΔK have been discussed and summarized by the timedomain method. Furthermore, the obtained experimental results are compared with FA (FordAndresen) model and ANL (Argonne National Lab) empirical curve, and they could fit fairly well. Fracture surface morphology reveals tansgranular crack in air fatigue and tansgranular with intergranular crack in hotwater environment, which accords well with the description of FA model.

Key words: corrosion fatigue, alloy 690, crack growth rates

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