Study on Plugging Criteria for Thru-wall Axial Crack in Roll Transition Zone of Steam Generator Tube

증기발생기 전열관 확관천이부위 축방향 관통균열의 관막음 기준에 관한 연구

  • 박명규 (한국원자력 연구소 계통기계분야) ;
  • 김영종 (한국원자력 연구소 계통기계분야) ;
  • 전장환 (한국원자력 연구소 계통기계분야) ;
  • 김종민 (한국원자력 연구소 계통기계분야) ;
  • 박준수 (한국원자력 연구소 계통기계분야)
  • Published : 1996.09.01


The stream generator tubes represent an integral part of a major barrier against the fission product release to the environment. So, the rupture of these tubes could permit flow of reactor coolant into the secondary system and injure the safety of reactor coolant system. Therefore, if the crack was detected during In-Service Inspection of tubes the cracked tube should be evaluated by the pulgging criteria and plugged or not. In this study, the fracture mechanics evaluation is carried out on the thru-wall axial crack due to Primary Water Stress Corrosion Cracking in the roll transition aone of steam generator tube to help the assurence the integrity of tubes and estabilish the plugging criteria. Due to the Inconel which is used as tube material is more ductile than others, the plastic instability repture theory was used to calculate the critical and allowable crack length. Based on Leak Before Break concept the leak rate for the critical crack length and the allowable leak rate are compared and the safety of tubes was given.