Corrosion Science and Technology

  • 제8권5호
  • /
  • Pages.188-192
  • /
  • 2009
  • /
  • 1598-6462(pISSN)
  • /
  • 2288-6524(eISSN)
한국부식방식학회 (The Corrosion Science Society of Korea)
권호 표지

누설 및 파열실험용 SCC 결함 전열관 제작 및 누설거동 평가

Production of SCC Flaws and Evaluation Leak Behavior of Steam Generator Tubes

  • 황성식 (한국원자력연구원, 원자력재료연구부) ;
  • 정만교 (한국원자력연구원, 원자력재료연구부) ;
  • 박장열 (한국원자력연구원, 원자력재료연구부) ;
  • 김홍표 (한국원자력연구원, 원자력재료연구부)
  • 투고 : 2009.08.03
  • 심사 : 2009.09.25
  • 발행 : 2009.10.01
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초록

A forced outage due to a steam generator tube leak in a Korean nuclear power plant was reported.1) Primary water stress corrosion cracking has occurred in many tubes in the plant, and they were repaired using sleeves or plugs. In order to develop proper repair criteria, it is necessary to understand the leak behavior of the tubes containing stress corrosion cracks. Stress corrosion cracks were developed in 0.1 M sodium tetrathionate solution at room temperature. Steam generator(SG) tubes with short cracks were successfully fabricated with a restricted solution contact method. The leak rates of the degraded tubes were measured at room temperature. Some tubes with 100 % through wall cracks showed an increase of leak rate with time at a constant pressure.

키워드

참고문헌

  1. J.S. Kim, S.S. Hwang et al., 'Destructive Analysis on Pulled Tubes from Ulchin Unit 4-Final Report' Korea Atomic Energy Research Institute, 2003
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