• 검색어에 아래의 연산자를 사용하시면 더 정확한 검색결과를 얻을 수 있습니다.
  • 검색연산자
검색연산자 기능 검색시 예
() 우선순위가 가장 높은 연산자 예1) (나노 (기계 | machine))
공백 두 개의 검색어(식)을 모두 포함하고 있는 문서 검색 예1) (나노 기계)
예2) 나노 장영실
| 두 개의 검색어(식) 중 하나 이상 포함하고 있는 문서 검색 예1) (줄기세포 | 면역)
예2) 줄기세포 | 장영실
! NOT 이후에 있는 검색어가 포함된 문서는 제외 예1) (황금 !백금)
예2) !image
* 검색어의 *란에 0개 이상의 임의의 문자가 포함된 문서 검색 예) semi*
"" 따옴표 내의 구문과 완전히 일치하는 문서만 검색 예) "Transform and Quantization"
쳇봇 이모티콘
ScienceON 챗봇입니다.
궁금한 것은 저에게 물어봐주세요.

논문 상세정보


It is commonly required that tubes with defects exceeding $40\%$ of wall thickness in depth should be plugged; however, this criterion is too conservative for some locations and for some types of defects. Many studies have been done with the aim of developing an alternative plugging criteria, and these studies have shown that steam generator tubes with a certain range of axial through-wall cracks could remain in service without any safety or reliability problems. However, these studies have been limited, thus far, to consideration of single cracked tubes, necessitating a study on multiple cracks, which are commonly found. A crack coalescence model applicable to steam generator tubes with two collinear axial through-wall cracks was proposed in the previous study. In this paper, the investigation is extended to the parallel axial cracks spaced in a circumferential direction, because parallel axial cracks are more frequently detected during in-service inspections than collinear axial cracks. Interaction effects between two parallel cracks are evaluated by performing elastic and elastic-plastic finite element analyses.

참고문헌 (20)

  1. USNRC, 'NUREG/CR-6365, Steam Generator Tube Failures' (1996) 
  2. USNRC,' Regulatory guide 1.121, Bases for Plugging Degraded PWR Steam Generator Tubes' (1976) 
  3. ASME,' Rules for Construction of Nuclear Power Plant Components,' ASME Code, Sec. III (1998) 
  4. Cochet, B. and Flesch, B.,' Crack Stability Criteria in Steam Generator Tubes,' 9th Int. Conference on SMiRT, Vol. D, pp.413-419 (1987) 
  5. Yu, Y.J., Kim, J.H., Kim, Y., and Kim, Y.J.,' Development of Steam Generator Tube Plugging Criteria for Axial Crack,' ASME PVP, Vol. 280, pp.79-83 (1994) 
  6. Gorman, J. A., Harris, J. E., and Lowenstein, D.B., Steam Generator Tube Fitness-for-Service Guidelines, AECB Report No. 2.228.2 (1995) 
  7. Lee, J.H., Park, Y.W., Song, M.H., Kim, Y.J. and Moon, S.I.,' 'Determination of Equivalent Single Crack based on Coalescence Criterion of Collinear Axial Cracks,' Nuclear Engineering and Design, Vol. 205, pp. 1-11 (2001) 
  8. Kim, J.S. et al.,' Investigation Report for Steam Generator Tubes Pulled out from Ulchin Unit 1' (1999) 
  9. Knag, S.C. et al.,' Regulatory Technical Report on the Steam Generator Tubes Safety of Nuclear Power Plants,' KINS/AR-669 (1999) 
  10. Erdogan, F.,' Ductile Failure Theories for Pressurized Pipes and Containers,' Int. J. PVP, Vol. 4 (1976) 
  11. Kiefner, J. F., Maxey, W. A., Eiber, R. J., and Duffy, A. R., 'Failure Stress Levels of Flaws in Pressurized Cylinders,' ASTM STP536, pp.461-481 (1973) 
  12. Majumdar, S., Shack, W. J., Diercks, D. R., Mruk, K., Franklin, J., and Knoblich, L.,' Failure Behavior of Internally Pressurized Flawed and Unflawed Steam Generator Tubing at High Temperatures ? Experiments and Comparison with Model Predictions,' NUREG/CR-6575, ANL-97/17 (1998) 
  13. Kim, Y. J., Choy, Y. S., and Lee, J. H.,' Development of Fatigue Life Prediction Program for Multiple Surface Cracks,' ASTM STP 1189, pp.536-550 (1993) 
  14. Shibata, K., Yokoyama, N., Ohba, T., Kawamura, T., and Miyazono, S.,' Growth Evaluation of Fatigue Cracks from Multiple Surface Flaws (I),' J. Japanese Nuclear Society, Vol. 27, No. 3 pp.250-262 (1985) 
  15. Shibata, K., Yokoyama, N., Ohba, T., Kawamura, T., and Miyazono, S.,' Growth Evaluation of Fatigue Cracks from Multiple Surface Flaws (II),' J. Japanese Nuclear Society, Vol. 28, No. 3, pp.258-265 (1986) 
  16. Murakami, Y.,' Stress Intensity Factors Handbook,' pp.204-205 (1987) 
  17. Cho, Y.J.,' A Study on the Interaction Effect of Adjacent Semi-Elliptical Crack,' Thesis for M.S., Sungkyunkwan University (1990) 
  18. Framatome,' Steam Generator Tube Integrity,' EPRI Report NP-6865-L, Vol. 1 (1991) 
  19. Argonne National Laboratory,' Steam Generator Tube Integrity Program,' Monthly Pregress Report of ANL, April 3 & 28 (2000) 
  20. Moon, S.I, Kim, Y.J., and Lee, J.H,' Estimation of Plastic Collapse Load of Steam Generator with Two Parallel Axial Through-Wall Cracks,' ASME PVP, Vol. 464, pp.223-230 (2003) 

이 논문을 인용한 문헌 (0)

  1. 이 논문을 인용한 문헌 없음


원문 PDF 다운로드

  • ScienceON :

원문 URL 링크

원문 PDF 파일 및 링크정보가 존재하지 않을 경우 KISTI DDS 시스템에서 제공하는 원문복사서비스를 사용할 수 있습니다. (원문복사서비스 안내 바로 가기)

상세조회 0건 원문조회 0건

DOI 인용 스타일