지원사업
학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
커뮤니티
연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2011.10
- 수록면
- 543 - 551 (9page)
이용수
초록· 키워드
오류제보하기
Steam generator tubes for nuclear power plants contain the local shape transitions on their inner or outer surface such as dent, bulge, over-expansion, eccentricity, deflection, and so on by the application of physical force during the tube manufacturing and steam generator assembling and by the sludge (that is, corrosion products) produced during the plant operation. The structural integrity of tubes will be degraded by generating the corrosive crack at that location. The profilometry using the traditional bobbin probes which are currently applied for measuring the profile change of tubes gives us basic information such as axial locations and average magnitudes of deformations. However, the three-dimensional quantitative evaluation on circumferential locations, distributional angle, and size of deformations will have to be conducted to understand the effects of residual stresses increased by local deformations on corrosive cracking of tubes. Steam generator tubes of Korean standard nuclear power plants expanded within their tube-sheets by the explosive expansion method and suffered from corrosive cracks in the early stage of power operation. Thus, local deformations of steam generator tubes at the top of tube-sheet were measured with an advanced rotating probe and a laser profiling system for the two cases where the tubes expanded by the explosive expansion method and hydraulic expansion. Also, the trends of eccentricity, deflection, and over-expansion of tubes were evaluated. The advanced eddy current profilometry was confirmed to provide accurate information of local deformations compared with laser profilometry.
목차
Abstract
1. Introduction
2. Advanced Eddy Current Probe
3. Experimental Method
4. Results and Discussion
5. Conclusions
References
참고문헌 (8)
참고문헌 신청
1. [학술지(정기간행물)] - J. Siegel / 1996 / Detecting SG tube cracks in difficult places / Nuclear Engineering International 41 : 18 ~
2. [보고서] - NDE / 1997 / PWR Steam Generator Examination Guidelines, Rev. 5, V. 1: Requirements
3. [보고서] - K. J. Karwoski / 1997 / Circumferential cracking of steam generator tubes : 6.1 ~ 7.26
4. [보고서] - I. G. Park / 2003 / Final report of analysis on alternate repair criteria of ODSCC circumferential crack for explosive expansion tubes of steam generators, In Contract Research Report for KAERI : 161 ~
5. [보고서] - J. H. Han / 2003 / Examination and analysis on steam generator tubes pulled from Yonggwang Unit 4 : 146 ~
2. [보고서] - NDE / 1997 / PWR Steam Generator Examination Guidelines, Rev. 5, V. 1: Requirements
3. [보고서] - K. J. Karwoski / 1997 / Circumferential cracking of steam generator tubes : 6.1 ~ 7.26
4. [보고서] - I. G. Park / 2003 / Final report of analysis on alternate repair criteria of ODSCC circumferential crack for explosive expansion tubes of steam generators, In Contract Research Report for KAERI : 161 ~
5. [보고서] - J. H. Han / 2003 / Examination and analysis on steam generator tubes pulled from Yonggwang Unit 4 : 146 ~
이 논문의 저자 정보
최근 본 자료
댓글(0)
0
UCI(KEPA) : I410-ECN-0101-2014-500-003269876