The effect of temperature on fatigue crack growth behaviour of a low alloy pressure vessel steel in a simulated BWR environment

Katada, Yasuyuki; Nagata, Norio

doi:10.1016/0010-938x(85)90006-x

Cited by 25 publications

(16 citation statements)

References 2 publications

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“…Earlier data obtained by Katada et al [44] and Atkinson et al [52] also revealed the susceptibility of pressure vessel steels to the EAC in high-temperature water environments to coincide with the DSA behavior. Therefore, the role of DSA, and especially its combination with hydrogen, in enhancing EAC cannot be neglected.…”

Section: B Hydrogen Effects In the Cyclic Deformation Processmentioning

confidence: 53%

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Hydrogen-involved tensile and cyclic deformation behavior of low-alloy pressure vessel steel

Katada

Kim

et al. 2004

Metall Mater Trans A

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The temperature-and strain-rate-dependent tensile behavior of hydrogen-charged low-alloy pressure vessel steel ASTM A508 C1.3 has been investigated. The fatigue crack initiation and propagation behavior of the steel in high-temperature water environments has also been evaluated. It was found that hydrogen played significant roles in both tensile and cyclic deformation processes, especially in the temperature and strain-rate region of dynamic strain aging (DSA). The presence of hydrogen resulted in a distinct softening in tensile strength and a certain loss in tensile ductility in the DSA region. Remarkable degradation in fatigue crack initiation and propagation resistance in high-temperature water environments was observed in the DSA strain-rate region. Typical hydrogen-induced cracking features also appeared on the corresponding fatigue fracture surfaces. The interactions between hydrogen and DSA in tensile and cyclic deformation processes are discussed as well as their combined effects on the environmentally assisted cracking (EAC) mechanism of pressure vessel steels in high-temperature water environments.

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Section: B Hydrogen Effects In the Cyclic Deformation Processmentioning

confidence: 53%

“…[44][45][46][47][48][49] It is generally believed that the inclusions in materials, especially MnS, play a key role in the process of corrosion fatigue. The present experimental results are also in agreement with this viewpoint.…”

Section: B Hydrogen Effects In the Cyclic Deformation Processmentioning

confidence: 99%

Hydrogen-involved tensile and cyclic deformation behavior of low-alloy pressure vessel steel

Katada

Kim

et al. 2004

Metall Mater Trans A

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“…During past several decades, many efforts have been made to clarify the influence of LWR environmental, loading and material parameters on fatigue lives of the RPV steels as well as the related EAC mechanisms [2][3][4][5][6][7][8][9][10][11][12][13][14][15][16][17][18]. It has been shown that LWR environments surely degraded fatigue resistance of the RPV steels and should be addressed in current code design fatigue curves.…”

Section: Introductionmentioning

confidence: 99%

Influence of surface finish on fatigue cracking behavior of reactor pressure vessel steel in high temperature water

Wu¹,

Guan

Han

et al. 2006

Materials & Corrosion

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The low cycle fatigue behavior of a low-alloy reactor pressure vessel (RPV) steel was investigated in high temperature water. Main attention was paid to the effects of surface finish of specimens on fatigue cracking behavior. It was found that the influence of surface finish on fatigue resistance of the steel was strain-rate dependent in high temperature water. Pretty obvious degradation of fatigue resistance appeared at fast strain rate with rougher surface finish. At slow strain rate, surface circumferential scratches promoted crack initiation and propagation. The fracture surface showed relatively flat and slight crack-arrest features. At fast strain rate, surface scratches also promoted crack initiation, but seemed not to dominate crack propagation. The fracture surface showed typical terraced and fan-like features. The above fatigue cracking behavior can be rationalized by a strain-rate dependent environmentally assisted cracking process of low-alloy RPV steel in high temperature water.

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“…Detailed investigations of its deformation behavior over a range of temperatures and strain rates were undertaken in order to develop constitutive behavior of the alloy. Due to the degrading effect of DSA on mechanical properties and observed synergism with other failure phenomena such as stress corrosion cracking, hydrogen embrittlement, [44,45] low-cycle fatigue, [33,48,49] and EAC [45][46][47] reported in earlier investigations, the emphasis in the present studies is to examine its extent of influence on uniaxial properties in the new generation alloy.…”

mentioning

confidence: 99%

“…[37][38][39][40][41][42][43] Further, there is also growing evidence that fatigue crack growth rates within the DSA temperatures of vessel steels increase, enhancing their susceptibility toward environmental assisted cracking (EAC). [44][45][46][47] These studies convey that despite the early knowledge and investigations into the occurrence of DSA, a study of the attendant influence of PLC effect and its synergistic role with the operating failure mechanism of the destined component application is required. As a result, there is a sustained need for characterizing the manifestation of DSA in either the newly developed alloys destined for structural applications or in those materials being used for structural components, where it has not been studied as yet.…”

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confidence: 99%

Dynamic Strain Aging in New Generation Cr-Mo-V Steel for Reactor Pressure Vessel Applications

Gupta

Chakravartty

Banerjee

2010

Metall Mater Trans A

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A new generation nuclear reactor pressure vessel steel (CrMoV type) having compositional similarities with thick section 3Cr-Mo class of low alloy steels and adapted for nuclear applications was investigated for various manifestations of dynamic strain aging (DSA) using uniaxial tests. The steel investigated herein has undergone quenched and tempered treatment such that a tempered bainite microstructure with Cr-rich carbides was formed. The scope of the uniaxial experiments included tensile tests over a temperature range of 298 K to 873 K (25°C to 600°C) at two strain rates (10 À3 and 10 À4 s À1 ), as well as suitably designed transient strain rate change tests. The flow behavior displayed serrated flow, negative strain rate sensitivity, plateau behavior of yield, negative temperature (T), and strain rate _ e ð Þ dependence of flow stress over the temperature range of 523 K to 673 K (250°C to 400°C) and strain rate range of 5 9 10 À3 s À1 to 3 9 10 À6 s À1 , respectively. While these trends attested to the presence of DSA, a lack of work hardening and near negligible impairment of ductility point to the fact that manifestations of embrittling features of DSA were significantly enervated in the new generation pressure vessel steel. In order to provide a mechanistic understanding of these unique combinations of manifestations of DSA in the steel, a new approach for evaluation of responsible solutes from strain rate change tests was adopted. From these experiments and calculation of activation energy by application of vacancy-based models, the solutes responsible for DSA were identified as carbon/nitrogen. The lack of embrittling features of DSA in the steel was rationalized as being due to the beneficial effects arising from the presence of dynamic recovery effects, presence of alloy carbides in the tempered bainitic structure, and formation of solute clusters, all of which hinder the possibilities for strong aging of dislocations.

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The effect of temperature on fatigue crack growth behaviour of a low alloy pressure vessel steel in a simulated BWR environment

Cited by 25 publications

References 2 publications

Hydrogen-involved tensile and cyclic deformation behavior of low-alloy pressure vessel steel

Hydrogen-involved tensile and cyclic deformation behavior of low-alloy pressure vessel steel

Influence of surface finish on fatigue cracking behavior of reactor pressure vessel steel in high temperature water

Dynamic Strain Aging in New Generation Cr-Mo-V Steel for Reactor Pressure Vessel Applications

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