The role of cold work and applied stress on surface oxidation of 304 stainless steel

Lozano-Pérez, Sergio; Kruska, Karen; Iyengar, Ilya; Terachi, Takumi; Yamada, Takuyo

doi:10.1016/j.corsci.2011.11.021

Cited by 121 publications

(50 citation statements)

References 19 publications

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“…In addition, no interaction between the c 0 free band and the oxide layer was observed in this study: localization bands were not preferential channels of oxide penetration in the base metal. This conclusion is in opposition to studies [16,20,22,23], reporting that the deformation bands present in 304L stainless steel exposed to PWR water may enhance the oxidation rate. For example, Lozano-Perez et al [23] indicate that prior cold work may facilitate oxidation in deformation bands by providing a density of dislocations acting as fast diffusion paths for oxygen and iron.…”

Section: Study Of Intergranular Oxide Penetrationcontrasting

confidence: 54%

Influence of localized plasticity on oxidation behaviour of austenitic stainless steels under primary water reactor

Cissé

Laffont

Lafont

et al. 2013

Journal of Nuclear Materials

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International audienceThe sensitivity of precipitation-strengthened A286 austenitic stainless steel to stress corrosion cracking was studied by means of slow-strain-rate tests. First, alloy cold working by low cycle fatigue (LCF) was investigated. Fatigue tests under plastic strain control were performed at different strain levels (Δεp/2 = 0.2%, 0.5%, 0.8% and 2%) to establish correlations between stress softening and the deformation microstructure resulting from the LCF tests. Deformed microstructures were identified through TEM investigations. The interaction between oxidation and localized deformation bands was also studied and it resulted that localized deformation bands are not preferential oxide growth channels. The pre-cycling of the alloy did not modify its oxidation behaviour. However, intergranular oxidation in the subsurface under the oxide layer formed after exposure to PWR primary water was shown

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Section: Study Of Intergranular Oxide Penetrationcontrasting

confidence: 54%

Influence of localized plasticity on oxidation behaviour of austenitic stainless steels under primary water reactor

Cissé

Laffont

Lafont

et al. 2013

Journal of Nuclear Materials

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“…10. The migration of O 2 and SO 2 was faster in dislocation aggregated areas than in grains, 18 resulting in forming the protective Cr rich layer easily in a simulated environment. A protective Cr rich layer effectively prevents the outward diffusion of Fe ions.…”

Section: Eds Analysis Results Of Samples From Bends 6 Eds Surface Anamentioning

confidence: 98%

High temperature corrosion of typical positions in SUS 30432 tubing bend tested in simulated environment

Sha

Liang

Suo

2014

Materials at High Temperatures

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The corrosion behaviour of typical positions in an SUS 30432 bend under simulated corrosive environments was investigated in this paper. A scanning electron microscope equipped with an energy dispersive spectrometer was used to characterise the surface and cross-section morphologies of specimens. Results show that the corrosion kinetics of all specimens were similar showing near parabolic law behaviour. The largest weight gain was located at the samples which were cut from the bottom of a bend. The corrosion scale consisted of an outer layer containing iron oxides and an inner layer containing Cr rich spinels and sulphides. The distances between grains in the samples from the bend were larger than that from the straight tube, which became smaller as the experimental time increased. It may be closely related to aggregation of dislocations near the grain boundaries after tube bending.

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“…Once tested, the cantilevers were then imaged in a FIB-SEM (Zeiss NVision), where the FIB 3D slicing technique was used to reconstruct the oxidized grain boundary portion of the cantilever in 3D. More details about this technique can be found in [5]. (S)TEM characterization was performed in a Jeol 3000F equipped with an ultrathin polymer window Oxford Instruments EDX detector and operated at 297keV.…”

Section: Methodsmentioning

confidence: 99%

Micromechanical testing of oxidized grain boundaries in Nickel alloys from nuclear reactors

et al. 2013

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The fracture behaviour of individual grain boundaries has been studied in order to understand the mechanisms controlling stress corrosion cracking in nuclear reactors. In particular, the role of oxidation in facilitating crack initiation and propagation has been reviewed. Nickel alloys from pressurized water reactors (PWRs) have been tested in simulated primary water conditions to induce grain boundary oxidation. Microcantilevers containing an oxidized grain boundary plane have been prepared and tested for fracture. The brittle nature of the oxide was demonstrated and the required stress to fracture measured.

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The role of cold work and applied stress on surface oxidation of 304 stainless steel

Cited by 121 publications

References 19 publications

Influence of localized plasticity on oxidation behaviour of austenitic stainless steels under primary water reactor

Influence of localized plasticity on oxidation behaviour of austenitic stainless steels under primary water reactor

High temperature corrosion of typical positions in SUS 30432 tubing bend tested in simulated environment

Micromechanical testing of oxidized grain boundaries in Nickel alloys from nuclear reactors

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