Mechano-Chemical Aspects of High Temperature Oxidation: A Mesoscopic Model Applied to Zirconium Alloys

Favergeon, Jérôme; Montésin, Tony; Bertrand, Gilles

doi:10.1007/s11085-005-6563-7

Cited by 32 publications

(12 citation statements)

References 34 publications

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“…This discrepancy is negligible and may be attributed to the specimen`s geometry, different microstructure, difference between flat and curved surfaces, different environment (air instead of steam) and, in consequence, different oxide growth. The higher inner oxide thickness the Zircaloy-2 tubes oxidized at high temperatures comparing to the outer oxide after oxidation at 1373 K is contradictory to some previous observations [26]. The origin of this difference is unclear.…”

Section: Fig 4 Oxide Mass Per Unit Area and Volume Fraction Of Reaccontrasting

confidence: 79%

“…The observed damage was dependent on oxidation temperature and surface geometry of specimens (curved internal and external surfaces). The increase in temperature results in increased compressive stresses, the highest at the interface oxide/metal [26]. The stresses originated by different curvature of specimen have different effects: they are independent of temperature, compressive at internal surface of the oxide and longitudinal at external surface of the oxide.…”

Section: Forms Of Oxide Damagementioning

confidence: 99%

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X-Ray Computer Tomography Study of Degradation of the Zircaloy-2 Tubes Oxidized at High Temperatures

Trybuś

Olivé

Lenoir

et al. 2019

Advances in Materials Science

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The investigations of high-temperature oxidation of zirconium alloys, applied for fuel pellets in nuclear power plants, are usually limited to oxidation kinetics, phase transformations and microstructural characterization. The purpose of this research was to characterize the degradation phenomena occurring within oxide layer and at the interface oxide/metal, on internal and external Zircaloy-2 tube surfaces, below and over crystalline transformation temperature of zirconium oxides. The commercial tubes were oxidized at 1273 K and 1373 K in calm air for 30 min and then examined with a technique novel for such purpose, namely a high-resolution X-ray computer tomography. The light microscopy was used to examine the cross-surfaces. The obtained results show that the form and intensity of oxide damage is significant and it is in a complicated way related to oxidation temperature and on whether external or internal tube surface is studied. The found oxide layer damage forms include surface cracks, the detachment of oxide layers, the appearance of voids, and nodular corrosion. The oxidation effects and damage appearance are discussed taking into account the processes such as formation of oxides, their phase transformation, stress-enhanced formation and propagation of cracks, diffusion of vacancies, formation of nitrides, diffusion of hydrogen into interface oxide-metal, incubation of cracks on second phase precipitates are taken into account to explain the observed phenomena.

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Section: Fig 4 Oxide Mass Per Unit Area and Volume Fraction Of Reaccontrasting

confidence: 79%

Section: Forms Of Oxide Damagementioning

confidence: 99%

X-Ray Computer Tomography Study of Degradation of the Zircaloy-2 Tubes Oxidized at High Temperatures

Trybuś

Olivé

Lenoir

et al. 2019

Advances in Materials Science

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“…A previous study [5] showed that for such an axisymmetric configuration, the gradient of ! ij " ij is very small in the zirconia layer and then, the mechanical effect on diffusion flux is insignificant.…”

Section: Numerical Resolutionmentioning

confidence: 97%

“…It has been shown that, as the zirconia layer grows, mechanical stresses develop in the zirconia layer but also in the ! -Zr(O) phase and could explain differences between experimental isothermal kinetics and analytical kinetics derived from the Wagner's theory [5]. [4] and 360 [3], in out-of-pile corrosion loop at 346 [4] and in-pile kinetics for innerside temperatures between 360 and 400 [6].…”

Section: Introductionmentioning

confidence: 99%

Coupled Modelling of ZrO2/α-Zr(O) Layers Growth under Thermal and Mechanical Gradients

Minne

Optasanu

Montésin

2019

J. Mater. Sci. Technol. Res.

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The oxidation process of a nuclear reactor fuel rod clad made of zirconium is simulated. It is assumed that the oxygen is transported by anionic diffusion in the zirconia layer (ZrO2). Part of this oxygen reacts at the interface between the zirconia layer and the metal, while the rest diffuses in the oxygen-enriched metal volume (a-Zr(O)) to the core of the metal by an interstitial mechanism. The model is based on the thermodynamics of irreversible processes and takes into account the influence of driving forces on the oxygen migration in the metal such as the oxygen concentration gradient, the temperature gradient [1] and the mechanical stress gradient [2]. The growth of both ZrO2 and a-Zr(O) layers are simulated using the finite element software CAST3M. This model has been applied on an axisymmetric geometry by imposing a heat flow on the fuel side and a constant temperature on the waterside of the clad. The differences obtained in the inner and outer sides of the nuclear clad concerning the oxidation kinetics and oxygen distribution are related to some coupling parameters. Several values of those parameters are used in the simulations to highlight their influence on the oxidation behavior. Thus, we show that negative values for the heat of transport, which relates the gradient of ocncentration and the gradient of temperature, give coherent results with experimental observations on oxidation kinetics for both sides of the clad.

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“…Kim et al [1] investigated the corrosion behaviour of the unalloyed Zr at 360°C in water and found that the oxidation rate of the (11 " 20) prismatic plane was faster than that of the (0002) basal plane. Aiming at the problem of corrosion anisotropy, a lot of researches have been done and many achievements were made [2][3][4][5][6][7]. Investigation of the fine-grained Zircaloy-4 specimens with rolling texture corroded at 360°C in lithiated aqueous solution showed the growth of oxide layer on the rolling surface (S N ) with maximum (0001) texture factors had a worse corrosion resistance than the surface with minimum (0001) texture factors [4].…”

Section: Introductionmentioning

confidence: 99%

Oxide Layers on (0001) Plane of Zircaloy-4 After Corrosion at 360 °C in Lithiated Aqueous Solution

Shaoqiu

Zhou

Yao

et al. 2015

Acta Metall. Sin. (Engl. Lett.)

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The microstructures of the oxide layers formed on near (0001) plane of Zircaloy-4 were investigated by autoclave tests at 360°C in lithiated aqueous solution. Oxygen-rich regions with hcp structure were observed at the undulating O/M interface, and the inner surface morphology of the oxide layers formed on (0001) was only concaveconvex. Monoclinic, tetragonal and cubic phases and a kind of zirconium sub-oxide with bcc structure were detected in the oxide layer near the metal matrix. This zirconium sub-oxide layer had a coherent relationship with a-Zr matrix, and the growth direction of the zirconium sub-oxide layer was nearly parallel to the [0001] direction of a-Zr regardless of the orientation of metal matrix. The orientations scattering of columnar grains formed on near (0001) plane differ from that formed on near (10 " 10) plane.

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Mechano-Chemical Aspects of High Temperature Oxidation: A Mesoscopic Model Applied to Zirconium Alloys

Cited by 32 publications

References 34 publications

X-Ray Computer Tomography Study of Degradation of the Zircaloy-2 Tubes Oxidized at High Temperatures

X-Ray Computer Tomography Study of Degradation of the Zircaloy-2 Tubes Oxidized at High Temperatures

Coupled Modelling of ZrO2/α-Zr(O) Layers Growth under Thermal and Mechanical Gradients

Oxide Layers on (0001) Plane of Zircaloy-4 After Corrosion at 360 °C in Lithiated Aqueous Solution

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