Transport processes in steam generator crevices

Abella, Jordi; Balachov, Iouri; Macdonald, Digby D.; Millet, Peter J

doi:10.1016/s0010-938x(01)00029-4

Cited by 25 publications

(10 citation statements)

References 2 publications

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“…The importance of thermal gradients in contributing to corrosion of industrial equipment has been reported in numerous studies [17,[23][24][25][26][27][28][29][30]. Thermogalvanic corrosion resulting from temperature gradients can cause the early failure of copper pipes exposed to a sustained temperature gradient.…”

Section: Introductionmentioning

confidence: 99%

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Thermogalvanic corrosion of Alloy 31 in different heavy brine LiBr solutions

et al. 2012

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Thermogalvanic corrosion generated between two electrodes of Alloy 31, a highlyalloyed austenitic stainless steel (UNS N08031), has been investigated imposing different temperature gradients in three deaerated LiBr solutions, under open circuit conditions by using a zero-resistance ammeter (ZRA). Besides EIS spectra were acquired in order to explain the obtained results. On the whole, cold Alloy 31 electrodes were anodic to hot Alloy 31 electrodes, since an increase in temperature favoured the cathodic behaviour of the hot electrode. Thermogalvanic corrosion of Alloy 31 in the LiBr solutions studied was not severe, although it negatively affects the corrosion resistance of the cold anode. The protective properties of the passive film formed on the anode surface were found to improve with thermogalvanic coupling time.

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Section: Introductionmentioning

confidence: 99%

“…Other works have been directed at heat exchangers materials [27,28]. Several authors have noted thermogalvanic corrosion as a corrosion mechanism within pressurized water nuclear reactor steam generators (SGs) [29,30], as well as in supercritical water oxidation reactors [17].…”

Section: Introductionmentioning

confidence: 99%

Thermogalvanic corrosion of Alloy 31 in different heavy brine LiBr solutions

et al. 2012

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“…However, Alloy 690 is vulnerable to crevice corrosion damage during long-time operation of pressurized water reactors (PWRs) [ 6 , 7 , 8 ]. Alloy 690 located in the crevices between the SG tube and tube support plate, and the tube sheet or deposits are easily attacked by corrosion [ 8 , 9 , 10 , 11 , 12 , 13 , 14 ]. The enrichment of aggressive impurity ions occurs inside the crevice during crevice corrosion.…”

Section: Introductionmentioning

confidence: 99%

Crevice Corrosion Behavior of Alloy 690 in High-Temperature Aerated Chloride Solution

et al. 2022

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Crevice corrosion behavior of Alloy 690 in high-temperature aerated chloride solution was studied using a self-designed crevice device. The SEM, EDS, XRD, and XPS analyses results indicated that the oxide films outside the crevice consisted of Ni-Cr oxides containing a small amount of hydroxides, and the oxide films on crevice mouth consisted of a (Ni,Fe)(Fe,Cr)2O4 spinel oxides outer layer and a Cr(OH)3 inner layer, and the oxide films inside the crevice consisted of a α-CrOOH outer layer and a Cr(OH)3 inner layer. When crevice corrosion occurred, the hydrolysis of Cr3+ led to the formation of Cr(OH)3 inside the crevice, and caused the pH value of crevice solution to decrease, and Cl− migrated from outside the crevice into inside the crevice due to electrical neutrality principle and accumulation. When the water chemistry inside the crevice reached the critical value of active dissolution of metal, the active dissolution of metal inside the crevice occurred. In addition, (Ni,Fe)(Fe,Cr)2O4 spinel oxides on the crevice mouth were formed by the deposition of metal ions migrated from inside the crevice. The mechanism of crevice corrosion and the formation mechanism of oxide films at different regions were also discussed.

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“…However, it is quite difficult to carry out related experiments to investigate the coupled thermal–hydraulic behavior of SG with TSPs. 2–5 Computational fluid dynamics (CFD) is attracting more attention from researchers, who desire detailed knowledge of the thermal–hydraulic characteristics of nuclear SG with and without TSPs. A considerable amount of research efforts has been devoted to investigating the distributions of two-phase flow and boiling heat transfer in the secondary side of SG, but much of this research has neglected the geometrical characteristics of TSPs.…”

Section: Introductionmentioning

confidence: 99%

Computational fluid dynamics investigation of thermal–hydraulic characteristics for a steam generator with and without tube support plates

Yang

Sun

et al. 2013

Proceedings of the Institution of Mechanical Engineers, Part C:

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A three-dimensional computational fluid dynamics model with the thermal phase change model is used to investigate the thermal–hydraulic characteristics of a steam generator with and without quatrefoil tube support plates. The two types of modeled designs are a unit pipe with and one without tube support plates. The computational fluid dynamics simulations capture the boiling phenomena, vortex and recirculation distributions, and the periodic characteristics of the circumferential wall temperature in the regions surrounding the tube support plates. The cross-flow energy responsible for flow-induced vibration damage in the region of the U-bend tubes is obtained with the aid of these localized thermal–hydraulic distributions. A comparison between the key parameters of the unit pipe models with and without tube support plates clearly reveals the influence of tube support plates in guiding flow behavior and alleviating flow-induced vibration damage for a steam generator’s U-bend tube bundle. Therefore, this computational fluid dynamics model can provide technical support for optimizing tube support plate design and improving the thermal–hydraulic characteristics of steam generator.

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Transport processes in steam generator crevices

Cited by 25 publications

References 2 publications

Thermogalvanic corrosion of Alloy 31 in different heavy brine LiBr solutions

Thermogalvanic corrosion of Alloy 31 in different heavy brine LiBr solutions

Crevice Corrosion Behavior of Alloy 690 in High-Temperature Aerated Chloride Solution

Computational fluid dynamics investigation of thermal–hydraulic characteristics for a steam generator with and without tube support plates

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