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Laboratorial technique for fabrication of outer diameter stress corrosion cracking on steam generator tubing

증기발생기 전열관 2차측 응력부식균열의 실험실적 모사 방법

  • Lee, Jae-Min (Nuclear Materials Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Kim, Sung-Woo (Nuclear Materials Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Hwang, Seong-Sik (Nuclear Materials Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Kim, Hong-Pyo (Nuclear Materials Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Kim, Hong-Deok (Machinery & Materials Laboratory, KHNP Central Research Institute)
  • 이재민 (한국원자력연구원, 원자력재료안전연구부) ;
  • 김성우 (한국원자력연구원, 원자력재료안전연구부) ;
  • 황성식 (한국원자력연구원, 원자력재료안전연구부) ;
  • 김홍표 (한국원자력연구원, 원자력재료안전연구부) ;
  • 김홍덕 (한국수력원자력(주) 중앙연구원, 기계재료연구소)
  • Received : 2014.06.24
  • Accepted : 2014.06.27
  • Published : 2014.06.30

Abstract

In this work, it is aimed to develop the fabrication method of axial stress corrosion cracking (SCC) defects having various sizes, on the outer diameter surface of the steam generator (SG) tubings. To control the length of the artificial SCC defect, the specific area of the SG tubing samples was exposed to an acidic solution after a sensitization heat treatment. During the exposure to an acidic solution, a direct current potential drop (DCPD) method was adopted to monitor the crack depth. The size of the SCC defect was first evaluated by an eddy current test (ECT), and then confirmed by a destructive examination. From the comparison, it was found that the actual crack length was well controlled to be similar to the length of the surface exposed to an acidic solution (5, 10, 20 or 30 mm in this work) with small standard deviation. From in-situ monitoring of the crack depth using the DCPD method, it was possible to distinguish a non-through wall crack from a through wall crack, even though the depth of the non-through wall crack was not able to be precisely controlled. The fabrication method established in this work was useful to simulate the SCC defect having similar size and ECT signals as compared to the field cracks in the SG tubings of the operating Korean PWRs.

Keywords

References

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