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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.1
- 수록면
- 304 - 313 (10page)
- DOI
- https://doi.org/10.1016/j.net.2020.06.022
이용수
초록· 키워드
오류제보하기
Nickel base Alloy X-750, which is used as fastener parts in light-water reactor (LWR), has experiencedmany failures by environmentally assisted cracking (EAC). In order to improve the reliability of passivecomponents for nuclear power plants (NPP's), it is necessary to study the failure mechanism and topredict crack growth behavior by developing a probabilistic failure model.
In this study, The Bayesian inference was employed to reduce the uncertainties contained in EACmodeling parameters that have been established from experiments with Alloy X-750. Corrosion fatiguecrack growth rate model (FCGR) was developed by fitting into Paris’ Law of measured data from theseveral fatigue tests conducted either in constant load or constant DK mode.
These parameters characterizing the corrosion fatigue crack growth behavior of X-750 were successfullyupdated to reduce the uncertainty in the model by using the Bayesian inference method. It isdemonstrated that probabilistic failure models for passive components can be developed by updating alaboratory model with field-inspection data, when crack growth rates (CGRs) are low and multiple inspectionscan be made prior to the component failure.
목차
등록된 정보가 없습니다.
참고문헌 (25)
참고문헌 신청
L.J. Bond / 2008 / Proactive Management of Materials Degradation e A Review of Principles and Programs
S.R. Doctor / 2009 / The proactive management of materials degradation (PMMD) and enhanced structural reliability / International Conference on Structural Mechanics in Reactor Technology (SMiRT 20)
A. N. Rumyantev / 2006 / Quantile estimate of the uncertainties of probabilistic safety analysis for objects of the nuclear power Industry / Atom. Energy 101(3):617~624
Iaea / 1998 / Component Reliability Data for Use in Probabilistic Safety Assessment
T. H. Lee / 2014 / A probabilistic environmentally assisted cracking model for steam generator tubes / ASME. J. Pressure Vessel Technol 137(2):021204~021204
S.R. Doctor / 2009 / The proactive management of materials degradation (PMMD) and enhanced structural reliability / International Conference on Structural Mechanics in Reactor Technology (SMiRT 20)
A. N. Rumyantev / 2006 / Quantile estimate of the uncertainties of probabilistic safety analysis for objects of the nuclear power Industry / Atom. Energy 101(3):617~624
Iaea / 1998 / Component Reliability Data for Use in Probabilistic Safety Assessment
T. H. Lee / 2014 / A probabilistic environmentally assisted cracking model for steam generator tubes / ASME. J. Pressure Vessel Technol 137(2):021204~021204
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