dK/da effects on the SCC growth rates of nickel base alloys in high-temperature water

Chen, Kai; Wang, Jiamei; Du, Dongping; Andresen, Peter L.; Zhang, Lefu

doi:10.1016/j.jnucmat.2018.02.032

Cited by 36 publications

(5 citation statements)

References 13 publications

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“…The experimental results reported for sensitized 304 stainless steel in oxygenated water at t = 288 °C are shown for comparison [29]. Further, empirical equation, the socalled EPRI2007 equation, is included, as defined in [30]. Crack growth rate calculation for mild steel, with the experimentally reported data, are shown in Fig.…”

Section: Validation Of Numerical Resultsmentioning

confidence: 99%

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Crack Growth Rate Analysis of Stress Corrosion Cracking

et al. 2021

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A theoretical film rupture model was used for computational procedure to predict the crack growth rate within the Stress Corrosion Cracking (SCC) conditions. Chemical, electrochemical and mechanical aspects of the SCC were analyzed and set into the computer program to calculate crack growth rate. Extended Finite Element Model (XFEM) was applied to calculate Stress Intensity Factor (SIF) in two loading modes -tensile test specimen and compact tension (CT) specimen. Elastic-plastic fracture mechanics (EPFM) was used for CT specimen. The computational model was verified with experimental results published in literature. Results have shown good agreement in two cases analysed here, stainless and common structural steel, indicating great potential of the XFEM to simulate the crack growth rate within the SCC conditions.

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Section: Validation Of Numerical Resultsmentioning

confidence: 99%

“…where λ is a parameter defined in [30]. However, K and dK/dt are not independent variables, since they are function of applied stress σ, crack size a and geometry-dependent factor, f(a/b).…”

Section: Mechanistic Aspects Of Sccmentioning

confidence: 99%

Crack Growth Rate Analysis of Stress Corrosion Cracking

et al. 2021

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“…erefore, Young's modulus of the oxide film at the crack tip is 140 GPa, and the Poisson ratio of the oxide film is 0.3. In experiment, stress intensity factor K I � 30 MPa•m 1/2 [10]. It is assumed that nickel-based 600 and 316L SS have the same creep parameters.…”

Section: Mechanical Modelmentioning

confidence: 99%

Effect of Cold Working on the Driving Force of the Crack Growth and Crack Growth Rate of Welded Joints under One Overload

Yang

Xue

Yang

et al. 2020

Advances in Materials Science and Engineering

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To understand the effect of cold working of welding heat-affected zone on the driving force of the crack growth and crack growth rate of stress corrosion cracking (SCC) near the welding fusion line, the finite element simulation method was used to analyze the effect of cold working on the tensile stress of the crack tip at different locations near the fusion line. On this basis, the strain rate of the crack tip in the Ford-Andresen model is replaced by the creep rate of the crack tip, and the creep rate of the crack tip is used as driving force for the crack growth of SCC. The effect of the cold working level at the heat-affected zone on the driving force of the crack growth and crack growth rate of SCC are analyzed, and driving force of the crack growth and crack growth rate of SCC after one overload was compared.

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“…Inconel 690 alloy (UNS N06690) has been widely used to make the steam generator tube sheets of nuclear power plant due to its excellent inter-crystalline corrosion resistance, high metallurgical stability, remarkable antioxidation property, and other good high-temperature mechanical properties [1,2]. When Inconel 690 alloy is used, its surface always needs to suffer different types of harsh wear behaviors due to the flow induced vibration, gas-liquid erosion, alternating thermal stress and other complex working environments, and all these conditions seriously threaten the safety of nuclear power plant operation [3].…”

Section: Introductionmentioning

confidence: 99%

Effect of ultrasonic surface rolling process on the impact wear behavior of Inconel 690 alloy at 25 °C and 300 °C

Yin¹,

Yin²,

Jiang³

2022

Surf. Topogr.: Metrol. Prop.

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As an important nuclear power material, Inconel 690 alloy always need to suffer various harsh impact wear behaviors during its service period. Therefore, how to further enhance its surface wear resistance and objectively reveal its fretting wear mechanism under various conditions have vital scientific values for improving its service performance. This study first applies specific ultrasonic surface rolling process (USRP) to treat the Inconel 690 alloy surface with two and four times separately. And then a controllable impact kinetic energy wear test rig is used to comparative investigate the impact wear behaviors of as-received and USRP treated samples at 25 ℃ and 300 ℃ temperature. Results indicate that USRP can effectively improve the near surface Nano-hardness, residual compressive stress and other mechanical properties of Inconel 690 alloy, thereby increasing its impact wear resistance. The impact wear mechanism at 25 ℃ is plastic deformation causes fatigue spalling, and some adhesion wear are found at the 300 ℃ wear condition.

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dK/da effects on the SCC growth rates of nickel base alloys in high-temperature water

Cited by 36 publications

References 13 publications

Crack Growth Rate Analysis of Stress Corrosion Cracking

Crack Growth Rate Analysis of Stress Corrosion Cracking

Effect of Cold Working on the Driving Force of the Crack Growth and Crack Growth Rate of Welded Joints under One Overload

Effect of ultrasonic surface rolling process on the impact wear behavior of Inconel 690 alloy at 25 °C and 300 °C

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