Effect of the chromium content on the corrosion of nickel based alloys in primary water of pressurised nuclear reactors

Delabrouille, F.; Viguier, Bernard; Legras, L.; Andrieu, Éric

doi:10.1179/mht.2005.033

Cited by 9 publications

(10 citation statements)

References 6 publications

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“…12 I IV V. .1 1. . D Du up pl le ex x o ox xi id de e l la ay ye er r The oxide scale presents a duplex aspect with a Cr rich inner film and an outer one rich in Ni and Fe, as expected from previous analyses performed on Ni-base systems [3], [5] and [6]. More precisely, the protective oxide scale mainly consists of a continuous Ni (1−x) Fe x Cr 2 O 4 spinel layer surmounting chromia particles at the inner oxide/alloy interface, as already evidenced in former works [1] and [2].…”

Section: Discussionsupporting

confidence: 66%

“…No chromium depletion was observed in the alloy, at the alloy/oxide interface. Nevertheless, in previous works [3], [4], [5] and [6], a chromium depleted zone was observed beneath the oxide scale, in Ni-base alloys exposed to PWR primary conditions. For some of them [3], [4] and [6], the presence of this chromium depleted layer was concomitant with a disturbed microstructure characterised by small grains of alloy and a strong dislocation density.…”

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confidence: 79%

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Oxidation kinetics and mechanisms of Ni-base alloys in pressurised water reactor primary conditions: Influence of subsurface defects

et al. 2011

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International audienceOxidation of Alloy 690 in PWR primary water conditions has been investigated, considering particularly the role played by subsurface structural defects. To simulate a defective surface state, Xe implantation has been set up on samples. Corrosion experiments were thereafter performed in a corrosion loop simulating the PWR medium with durations between 24 h and 1000 h. Microstructural observations and NRA measurements underlined the role played by defects on the crystallinity of the continuous oxide spinel layer, on the nucleation of Cr2O3 nodules and on the oxidation rate. The higher defects concentration seemed to modify the oxygen diffusion in the oxide scale

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Section: Discussionsupporting

confidence: 66%

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confidence: 79%

Oxidation kinetics and mechanisms of Ni-base alloys in pressurised water reactor primary conditions: Influence of subsurface defects

et al. 2011

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“…Others results obtained, by SEM, TEM, GIXRD, and SIMS mainly, on alloys 600 or 690 exposed to hydrogenated water at 360 °C [2 ppm Li, 1200 or 1000 ppm B, and P(H 2 ) = 0.3 or 0.17 bar, respectively, in Soustelle et al ., Delabrouille et al ., or Panter et al ] reported an external scale made of Fe and Ni‐rich spinel oxide and an internal oxide rich in Cr. These last papers are in good agreement with the description made by Carrette et al …”

Section: Introductionmentioning

confidence: 97%

“…The oxide scales formed on nickel base alloys exposed to high temperature hydrogenated water (ranging from 285 to 360 °C), in order to simulate corrosion phenomena in PWR primary medium, have always been described as a multilayer structure …”

Section: Introductionmentioning

confidence: 99%

XPS study of Ni‐base alloys oxide films formed in primary conditions of pressurized water reactor

Marchetti

Miserque

Perrin

et al. 2015

Surface & Interface Analysis

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International audienceThe oxide scales formed on alloy 690 during its exposure to pressurized water reactor primary simulated media at 325 °C for different periods, ranging between 24 and 858 h have been characterized through XPS analysis. These results have been compared with the data obtained on Cr₂O₃, NiCr₂O₄, NiFe₂O₄, and Ni(OH)₂ reference compounds. This comparison leads to the following conclusions about the scale formed on alloy 690: (i) the deconvolution of Cr-2p_3/2 core level spectra seems to show that the internal oxide scale is made of a mix of chromite and chromia; (ii) the evolution of the height ratio between satellite and principal peaks, on the Ni-2p_3/2 core level, has highlighted the presence of nickel hydroxide for all corrosion durations; and (iii) XPS analysis can be used to study the kinetics of nickel ferrite precipitation. In order to obtain a more complete description of such oxide scales based upon XPS measurements, reference data, obtained on nickel ferrites and chromites in which Fe is partially substituted to Ni, are needed. The comparison of published data and reference spectra performed in this work also leads to conclude that core level fits are dependent on the energy resolution, which can be achieved with specific spectrometer and analysis procedures. Therefore, reference compound spectra need to be recorded in the very identical analytical configuration before dealing with results obtained on corroded specimen

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“…The existence of a continuous inner layer of Cr 2 O 3 associated or not with a Cr-depleted layer in the substrate was previously reported in the literature for nickel-base alloys exposed to primary water at 325°C [41] or 360°C [44,45]. Other authors also report the existence of a Crrich (up to 80% of the metallic elements) oxide inner scale associated with a Cr-depleted layer after oxidation at 360°C [25,46] but they don't conclude on the oxide phase formed.…”

Section: Comparison Between Oxidation In Hydrogenated Steam and In Simentioning

confidence: 83%

Characterization of oxide scales formed on alloy 82 in nominal PWR primary water at 340 °C and in hydrogenated steam at 400 °C

et al. 2018

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International audienceAlloy 82, used as weld metal in Pressurized Water Reactor (PWR), was exposed to hydrogenated steam at 400 °C and to simulated primary water at 340 °C. A comparative study of the oxide layer formed on the alloy surface in both environments was performed to confirm that steam conditions were representative of accelerated primary water conditions. For this purpose, the oxidation products were investigated at a nanometer scale using Scanning Electron Microscopy (SEM), X-ray Photoelectron Spectrometry (XPS) and Transmission Electron Microscopy (TEM). Results obtained in both conditions are compared and the influences of heat treatment, test duration and surface preparation are studied

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Effect of the chromium content on the corrosion of nickel based alloys in primary water of pressurised nuclear reactors

Cited by 9 publications

References 6 publications

Oxidation kinetics and mechanisms of Ni-base alloys in pressurised water reactor primary conditions: Influence of subsurface defects

Oxidation kinetics and mechanisms of Ni-base alloys in pressurised water reactor primary conditions: Influence of subsurface defects

XPS study of Ni‐base alloys oxide films formed in primary conditions of pressurized water reactor

Characterization of oxide scales formed on alloy 82 in nominal PWR primary water at 340 °C and in hydrogenated steam at 400 °C

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Effect of the chromium content on the corrosion of nickel based alloys in primary water of pressurised nuclear reactors

Cited by 9 publications

References 6 publications

Oxidation kinetics and mechanisms of Ni-base alloys in pressurised water reactor primary conditions: Influence of subsurface defects

Oxidation kinetics and mechanisms of Ni-base alloys in pressurised water reactor primary conditions: Influence of subsurface defects

XPS study of Ni‐base alloys oxide films formed in primary conditions of pressurized water reactor

Characterization of oxide scales formed on alloy 82 in nominal PWR primary water at 340 °C and in hydrogenated steam at 400 °C

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Characterization of oxide scales formed on alloy 82 in nominal PWR primary water at 340 °C and in hydrogenated steam at 400 °C