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
- 2020.12
- 수록면
- 2,949 - 2,957 (9page)
- DOI
- https://doi.org/10.1016/j.net.2020.06.001
이용수
초록· 키워드
오류제보하기
Fatigue crack growth model has been developed for dissimilar metal weld joints of a piping componentunder cyclic loading, where in the crack is located at the center of the weld in the circumferential direction. The fracture parameter, Stress Intensity Factor (SIF) has been computed by using principle ofsuperposition as KH þ KM. KH is evaluated by assuming that, the complete specimen is made of thematerial containing the notch location. In second stage, the stress field ahead of the crack tip, accountingfor the strength mismatch, the applied load and geometry has been characterized to evaluate SIF (KM).
For each incremental crack depth, stress field ahead of the crack tip has been quantified by using J-integral (elastic), mismatch ratio, plastic interaction factor and stress parallel to the crack surface. Theassociated constants for evaluation of KM have been computed by using the quantified stress field withrespect to the distance from the crack tip. Net SIF (KH þ KM) computed, has been used for the crackgrowth analysis and remaining life prediction by Paris crack growth model. To validate the model, SIF andremaining life has been predicted for a pipe made up of (i) SA312 Type 304LN austenitic stainless steeland SA508 Gr. 3 Cl. 1. Low alloy carbon steel (ii) welded SA312 Type 304LN austenitic stainless-steel pipe.
From the studies, it is observed that the model could predict the remaining life of DMWJ piping components with a maximum difference of 15% compared to experimental observations
목차
등록된 정보가 없습니다.
참고문헌 (30)
참고문헌 신청
H. T. Wang / 2013 / Fracture mechanism of a dissimilar metal welded joint in nuclear power plant / Eng. Fail. Anal 28:134~148
PWR Material Realiability Project / 2001 / Interim Alloy 600 Safety Assessment for U.S. PWR Plants, Part 1: Alloy82/182 Pipe Butt Welds
R. Celin / 2011 / Degradation of a Ni-Cr-Fe alloy in a pressurised water nuclear power plant / Mater. Technol 45:151~157
A. Jenssen / 2001 / Assessment of cracking in dissimilar metal welds / Proc. Of Tenth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
S. Farley / 2004 / An overview of non destructive inspection service in nuclear power plants / International Conference on Nuclear Energy for New Europe
PWR Material Realiability Project / 2001 / Interim Alloy 600 Safety Assessment for U.S. PWR Plants, Part 1: Alloy82/182 Pipe Butt Welds
R. Celin / 2011 / Degradation of a Ni-Cr-Fe alloy in a pressurised water nuclear power plant / Mater. Technol 45:151~157
A. Jenssen / 2001 / Assessment of cracking in dissimilar metal welds / Proc. Of Tenth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
S. Farley / 2004 / An overview of non destructive inspection service in nuclear power plants / International Conference on Nuclear Energy for New Europe
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