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Corrosion fatigue of austenitic stainless steels for nuclear power engineering

dc.contributor.authorVlčková, Irena
dc.contributor.authorJonšta, Petr
dc.contributor.authorJonšta, Zdeněk
dc.contributor.authorVáňová, Petra
dc.contributor.authorKulová, Taťána
dc.date.accessioned2017-03-15T10:03:06Z
dc.date.available2017-03-15T10:03:06Z
dc.date.issued2016
dc.identifier.citationMetals. 2016, vol. 6, issue 12, art. no. 319.cs
dc.identifier.issn2075-4701
dc.identifier.urihttp://hdl.handle.net/10084/116936
dc.description.abstractSignificant structural steels for nuclear power engineering are chromium-nickel austenitic stainless steels. The presented paper evaluates the kinetics of the fatigue crack growth of AISI 304L and AISI 316L stainless steels in air and in corrosive environments of 3.5% aqueous NaCl solution after the application of solution annealing, stabilizing annealing, and sensitization annealing. Comparisons were made between the fatigue crack growth rate after each heat treatment regime, and a comparison between the fatigue crack growth rate in both types of steels was made. For individual heat treatment regimes, the possibility of the development of intergranular corrosion was also considered. Evaluations resulted in very favourable corrosion fatigue characteristics of the 316L steel. After application of solution and stabilizing annealing at a comparable Delta K level, the fatigue crack growth rate was about one half compared to 304L steel. After sensitization annealing of 316L steel, compared to stabilizing annealing, the increase of crack growth rate during corrosion fatigue was slightly higher. The obtained results complement the existing standardized data on unconventional characteristics of 304L and 316L austenitic stainless steels.cs
dc.format.extent2894967 bytes
dc.format.mimetypeapplication/pdf
dc.language.isoencs
dc.publisherMDPIcs
dc.relation.ispartofseriesMetalscs
dc.relation.urihttp://dx.doi.org/10.3390/met6120319cs
dc.rights© 2016 by the authors; licensee MDPI, Basel, Switzerland. This article is an open access article distributed under the terms and conditions of the Creative Commons Attribution (CC-BY) license.cs
dc.rights.urihttp://creativecommons.org/licenses/by/4.0/cs
dc.subjectaustenitic stainless steelcs
dc.subjectheat treatmentcs
dc.subjectcorrosion fatiguecs
dc.subjectfatigue crack growth ratecs
dc.subjectintergranular corrosioncs
dc.titleCorrosion fatigue of austenitic stainless steels for nuclear power engineeringcs
dc.typearticlecs
dc.identifier.doi10.3390/met6120319
dc.rights.accessopenAccess
dc.type.versionpublishedVersioncs
dc.type.statusPeer-reviewedcs
dc.description.sourceWeb of Sciencecs
dc.description.volume6cs
dc.description.issue12cs
dc.description.firstpageart. no. 319cs
dc.identifier.wos000393041700003


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© 2016 by the authors; licensee MDPI, Basel, Switzerland. This article is an open access article distributed under the terms and conditions of the Creative Commons Attribution (CC-BY) license.
Except where otherwise noted, this item's license is described as © 2016 by the authors; licensee MDPI, Basel, Switzerland. This article is an open access article distributed under the terms and conditions of the Creative Commons Attribution (CC-BY) license.