Fatigue crack growth behavior of reactor pressure vessel steels in air and high-temperature water environments

Huang, J. Y.; Yeh, J. J.; Kuo, R.C.; Jeng, Sheng-Long; Young, M.C.

doi:10.1016/j.ijpvp.2008.08.003

Cited by 15 publications

(5 citation statements)

References 7 publications

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“…SEM fractographs of the fatigued specimens indicated that the fatigue crack initiated at inclusion sites. From the previous study [26,27], the fatigue crack growth rate shows no dependence on the sulfur contents of A533B3 steels in air, but it is related to the specimen orientation. For the specimens with 0.016 wt.% and 0.027 wt.% sulfur tested in air at room temperature and 300°C, the fatigue crack growth rates were faster with the crack propagation direction parallel to the rolling direction than those with the crack direction perpendicular to the specimen orientation.…”

Section: Effects Of Orientation On Fatigue Crack Growth Ratementioning

confidence: 91%

Corrosion fatigue behavior of low alloy steels under simulated BWR coolant conditions

Huang

Young

Jeng

et al. 2010

Journal of Nuclear Materials

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Section: Effects Of Orientation On Fatigue Crack Growth Ratementioning

confidence: 91%

Corrosion fatigue behavior of low alloy steels under simulated BWR coolant conditions

Huang

Young

Jeng

et al. 2010

Journal of Nuclear Materials

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“…KnE Energy crack propagation characteristics of the reactor components and associated factors have been intensively performed [5,6].…”

Section: Iconets Conference Proceedingsmentioning

confidence: 99%

Fatigue Strength Evaluation Of Pressurizer Wall Structure In Pressurized Water Reactor

Himawan¹

2016

KEn

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Fatigue strength evaluations have been performed to the pressurizer component in Pressurized Water Reactor. Fatigue is the main failure mechanism of material during system in operation. Therefore, this evaluation becomes important to be performed since the pressurizer has a very important function in the reactor's system. Analysis . This value still far enough below failure criteria, which a value is 1. Therefore, the pressurizer design has already fulfilled the design qualification in term of fatigue aspect.

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“…As surveyed through SCOPUS database, lot of experimental investigations are being conducted by the researchers on long fatigue crack MATEC Web of Conferences 165, 13001 (2018) https://doi.org/10.1051/matecconf/201816513001 FATIGUE 2018 propagation in this steel. These investigations are related to the effect of cyclic loading ratio [8], testing environment [9][10][11][12] and heat treatment [13] on the long fatigue crack propagation in this LAS. Apart from long fatigue crack propagation studies only one research paper regarding the experimental study related to the difference in short and long fatigue crack propagation rates in the LAS is available in literature [14].…”

Section: Introductionmentioning

confidence: 99%

On the transition of short cracks into long fatigue cracks in reactor pressure vessel steels

et al. 2018

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Abstract. Short fatigue cracks, having dimension less than 1 mm, propagate at much faster rates (da/dN) even at lower stress intensity factor range (da/dN) as compared to the threshold stress intensity factor range obtained from long fatigue crack growth studies. These short cracks originate at the sub-grain level and some of them ultimately transit into critical long cracks over time. Therefore, designing the components subjected to fatigue loading merely on the long crack growth data and neglecting the short crack growth behavior can overestimate the component's life. This aspect of short fatigue cracks become even more critical for materials used for safety critical applications such as reactor pressure vessel (RPV) steel in nuclear plants. In this work, the transition behaviour of short fatigue crack gowth into long fatigue crack is studied in SA508 Grade 3 Class I low alloy steel used in RPVs. In-situ characterization of initiation, propagation and transition of short fatigue cracks is performed using fatigue stage for Scanning Electron Microscope (SEM) in addition to digital microscopes fitted over a servo-hydraulic fatigue machine and correlated with the microtructural information obtained using electron backscatter diffraction (EBSD). SA508 steel having an upper bainitic microstructure have several microstructural interfaces such as phase and grain boundaries that play a significant role in controlling the short fatigue crack propagation. Specially designed and prepared short fatigue specimens (eletro-polished) with varying initial crack lengths of the order of tens of microns are used in this study. The transition of such short initial cracks into long cracks is then tracked to give detailed insight into the role of each phase and phase/grain boundary with an objective of establishing Kitagawa-Takahashi diagram for the given RPV steel. The behavior of the transited long cracks is then compared with the crack propagation behavior obtained using conventional CT specimens. The outcome of this research will enhance information on the integrity of the components made from RPV steel used in Indian nuclear power plants.

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Fatigue crack growth behavior of reactor pressure vessel steels in air and high-temperature water environments

Cited by 15 publications

References 7 publications

Corrosion fatigue behavior of low alloy steels under simulated BWR coolant conditions

Corrosion fatigue behavior of low alloy steels under simulated BWR coolant conditions

Fatigue Strength Evaluation Of Pressurizer Wall Structure In Pressurized Water Reactor

On the transition of short cracks into long fatigue cracks in reactor pressure vessel steels

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