Stress Corrosion Crack Growth Evaluation in Primary Loop of Nuclear Power Plant

원전 주배관의 응력부식 가상결함 성장에 대한 잔류응력 영향 평가

  • 양준석 (한국전력공사 전력연구원 원자력연구실) ;
  • 박치용 (한국전력공사 전력연구원 원자력연구실) ;
  • 윤기석 (한국전력기술(주) 원자로설계개발단) ;
  • 강선예 (한국전력기술(주) 원자로설계개발단) ;
  • 오종근 (한국수력원자력(주) 고리원자력본부)
  • Published : 2004.04.28

Abstract

The most important mode of subcritical crack growth is primary water stress corrosion crack, which was the reported mechanism from the root cause analysis of the crack in the bimetallic welds. Stress corrosion crack growth evaluations was carried out for several flaw shapes of both axial and circumferential flaws, using the steady-state stresses including residual stresses. This evaluation considered the possibility of additional flaws in the primary loops of nuclear power plant, even though no such flaws have been identified by Ultrasonic Test. Consequently, Results show that the predicted flaw sizes will determine acceptability for continued service and maintenance.

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