Review on effect of cyclic loading on environmental assisted cracking of alloy 600 in typical nuclear coolant waters

Congleton, J.; Charles, E.A.; Sui, G.

doi:10.1016/s0010-938x(01)00023-3

Cited by 10 publications

(5 citation statements)

References 14 publications

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“…Slip-oxidation is the mechanism for crack advancement in which mechanism, crack advances through an iterative process of surface film rupture during straining that exposes the material to corrosive environment and passivation by film formation [28]. The effect of cyclic loading on environmentally-assisted cracking of Alloy 600 in typical nuclear coolant waters has been reviewed by Congleton et al [29]. The review [29] shows that Alloy 600 exhibits enhanced crack growth rates relative to those in air when tested in PWR primary coolant and in oxygenated pure water.…”

Section: Alloy 600mentioning

confidence: 99%

“…The effect of cyclic loading on environmentally-assisted cracking of Alloy 600 in typical nuclear coolant waters has been reviewed by Congleton et al [29]. The review [29] shows that Alloy 600 exhibits enhanced crack growth rates relative to those in air when tested in PWR primary coolant and in oxygenated pure water. The enhancements are found to be larger in oxygenated pure water as compared to that in PWR primary coolant [29].…”

Section: Alloy 600mentioning

confidence: 99%

“…The review [29] shows that Alloy 600 exhibits enhanced crack growth rates relative to those in air when tested in PWR primary coolant and in oxygenated pure water. The enhancements are found to be larger in oxygenated pure water as compared to that in PWR primary coolant [29]. Kamaya and Totsuka [30] have investigated stress corrosion crack propagation of Alloy 600 in simulated PWR primary coolant and have concluded that interaction between multiple cracks might be a key factor in crack growth acceleration after 1500 h (5.4 Ms).…”

Section: Alloy 600mentioning

confidence: 99%

See 2 more Smart Citations

Corrosion aspects of Ni–Cr–Fe based and Ni–Cu based steam generator tube materials

Dutta

2009

Journal of Nuclear Materials

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Section: Alloy 600mentioning

confidence: 99%

Section: Alloy 600mentioning

confidence: 99%

Section: Alloy 600mentioning

confidence: 99%

See 1 more Smart Citation

Corrosion aspects of Ni–Cr–Fe based and Ni–Cu based steam generator tube materials

Dutta

2009

Journal of Nuclear Materials

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“…The residual life of these components is typically determined by using fatigue crack growth rate (FCGR) curves. Experiments and analysis for FCGR of different nickel alloys have been conducted, including alloy 600, alloy 690, and alloy 617, [33,[35][36][37][38] in a pure water environment at higher temperatures. These experiments aimed to analyze the effects of high temperature, water chemistry, and stress intensity on CGR.…”

Section: Introductionmentioning

confidence: 99%

Effect of temperature and medium environment on corrosion fatigue behavior of Inconel 625

Ghazi

Khan

Farooq

et al. 2023

Materials & Corrosion

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Inconel 625 is a nickel‐based alloy with exceptional creep and corrosion resistance properties. It has emerged as a candidate material for operational and structural use in critical and supercritical power generation plants. Supercritical power plants work at high temperatures, pressure and in an erosive environment that makes metallic materials more vulnerable to corrosion fatigue. This study aimed to evaluate the fatigue crack growth rate (FCGR) at elevated temperatures (550–650°C) in a steam and supercritical water environment. All the experiments were performed at a water oxygen level of 8000 ppb. A cyclic stress of 1 Hz frequency and sine waveform was applied for the test. A 0.6 stress ratio was applied with a maximum stress intensity factor of 32 MPa√m. A direct current potential drop method was applied to detect the crack growth rate (CGR). For the given parameters, fractographic analysis validated the role of corrosion‐fatigue interaction as the primary source of variation in the FCGR. Results revealed that the CGR was enhanced with a rise in temperature under all test environments. The influencing mechanism of temperature on CGR was also discussed.

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“…It has been a subject of experimental and analytical research for more than a century [1]. Aggressive environment introduces corrosion and adds to further degradation of the material and shortens the life of structural members [2][3][4][5][6][7]. A widely used hypothesis for the environment assisted crack growth is that of dissolution [8,9] which is localized at the surface region where the metal is exposed and experiences the highest strains.…”

Section: Introductionmentioning

confidence: 99%

Evolution of fatigue crack corrosion from surface irregularities

Jivkov

2003

Theoretical and Applied Fracture Mechanics

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A moving boundary model is presented for crack nucleation and growth from surface flaws. It concerns with chemical attack that results in material dissolution. A controlling mechanism for evolution is the rupture of a brittle corrosion-protective film that is built up along the corroding surface. The evolution rate is a function of the degree of protective film damage caused by the surface straining. The problem is formulated for an elastic body containing a single and double pits. Low-frequency cyclic loading is considered. Numerical solution is proposed. The behaviours of a growing crack and of two competing cracks are described. Stages of incubation, blunting and steady-state growth characterise a single crack evolution. The steady-state growth rate is found independent of the initial geometry. Stages of independent growth, interactive growth and arrest of one crack characterise the evolution of two competing cracks. The lengths of the arrested cracks are presented as functions of the ratio between the pit depth for a series of different distances between the pits. It is emphasized that the solutions correspond to a homogeneous material. Further work is required to account for the material microstructure.

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Review on effect of cyclic loading on environmental assisted cracking of alloy 600 in typical nuclear coolant waters

Cited by 10 publications

References 14 publications

Corrosion aspects of Ni–Cr–Fe based and Ni–Cu based steam generator tube materials

Corrosion aspects of Ni–Cr–Fe based and Ni–Cu based steam generator tube materials

Effect of temperature and medium environment on corrosion fatigue behavior of Inconel 625

Evolution of fatigue crack corrosion from surface irregularities

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