Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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EVALUATION OF PRIMARY WATER STRESS CORROSION CRACKING GROWTH RATES BY USING THE EXTENDED FINITE ELEMENT METHOD

  • LEE, SUNG-JUN (Department of Nuclear Engineering, Kyung Hee University) ;
  • CHANG, YOON-SUK (Department of Nuclear Engineering, Kyung Hee University)
  • Received : 2015.06.17
  • Accepted : 2015.08.03
  • Published : 2015.12.25
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Abstract

Background: Mitigation of primary water stress corrosion cracking (PWSCC) is a significant issue in the nuclear industry. Advanced nickel-based alloys with lower susceptibility have been adopted, although they do not seem to be entirely immune from PWSCC during normal operation. With regard to structural integrity assessments of the relevant components, an accurate evaluation of crack growth rate (CGR) is important. Methods: For the present study, the extended finite element method was adopted from among diverse meshless methods because of its advantages in arbitrary crack analysis. A user-subroutine based on the strain rate damage model was developed and incorporated into the crack growth evaluation. Results: The proposed method was verified by using the well-known Alloy 600 material with a reference CGR curve. The analyzed CGR curve of the alternative Alloy 690 material was then newly estimated by applying the proven method over a practical range of stress intensity factors. Conclusion: Reliable CGR curves were obtained without complex environmental facilities or a high degree of experimental effort. The proposed method may be used to assess the PWSCC resistance of nuclear components subjected to high residual stresses such as those resulting from dissimilar metal welding parts.

Keywords

Acknowledgement

Supported by : Korea Institute of Energy Technology Evaluation and Planning (KETEP)

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