Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Corrosion fatigue crack growth behavior of 316LN stainless steel in high-temperature pressurized water

  • Zhang, Ziyu (CAS Key Laboratory of Nuclear Materials and Safety Assessment, Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences) ;
  • Tan, Jibo (CAS Key Laboratory of Nuclear Materials and Safety Assessment, Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences) ;
  • Wu, Xinqiang (CAS Key Laboratory of Nuclear Materials and Safety Assessment, Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences) ;
  • Han, En-Hou (CAS Key Laboratory of Nuclear Materials and Safety Assessment, Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences) ;
  • Ke, Wei (CAS Key Laboratory of Nuclear Materials and Safety Assessment, Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences)
  • Received : 2020.11.30
  • Accepted : 2021.03.18
  • Published : 2021.09.25
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Abstract

Corrosion fatigue crack growth (FCG) behavior of 316LN stainless steel was investigated in high-temperature pressurized water at different temperatures, load ratios (R = Kmax/Kmin) and rise times (tR). The environmental assisted effect on FCG rate was observed when both the R and tR exceeded their critical values. The FCG rate showed a linear relation with stress intensity factor range (ΔK) in double logarithmic coordinate. The environmental assisted effect on FCG rate depended on the ΔK and quantitative relations were proposed. Possible mechanisms of environmental assisted FCG rate under different testing conditions are also discussed.

Keywords

Acknowledgement

This study was jointly supported by the Natural Science Foundation of Liaoning Province of China (2020-BS-005), the Open Foundation of CAS Key Laboratory of Nuclear Materials and Safety Assessment (292020000038), the National Science and Technology Major Project (2017ZX06002003-004-002) and CNNC Science Fund for Talented Young Scholars.

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