Corrosion Fatigue of Austenitic Stainless Steels for Nuclear Power Engineering

Significant 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...

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Main Authors: Irena Vlčková, Petr Jonšta, Zdeněk Jonšta, Petra Váňová, Taťána Kulová
Format: Article
Language:English
Published: MDPI AG 2016-12-01
Series:Metals
Subjects:
Online Access:http://www.mdpi.com/2075-4701/6/12/319
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author Irena Vlčková
Petr Jonšta
Zdeněk Jonšta
Petra Váňová
Taťána Kulová
author_facet Irena Vlčková
Petr Jonšta
Zdeněk Jonšta
Petra Váňová
Taťána Kulová
author_sort Irena Vlčková
collection DOAJ
description Significant 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 ∆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.
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spelling doaj.art-e367f25d2c90437597711ca5e480133c2022-12-21T22:59:27ZengMDPI AGMetals2075-47012016-12-0161231910.3390/met6120319met6120319Corrosion Fatigue of Austenitic Stainless Steels for Nuclear Power EngineeringIrena Vlčková0Petr Jonšta1Zdeněk Jonšta2Petra Váňová3Taťána Kulová4RMTSC, Material & Metallurgical Research Ltd., Remote Site Ostrava, VÚHŽ a.s., Dobrá 739 51, Czech RepublicDepartment of Materials Engineering, VŠB-Technical University of Ostrava, Ostrava 708 33, Czech RepublicDepartment of Materials Engineering, VŠB-Technical University of Ostrava, Ostrava 708 33, Czech RepublicDepartment of Materials Engineering, VŠB-Technical University of Ostrava, Ostrava 708 33, Czech RepublicDepartment of Materials Engineering, VŠB-Technical University of Ostrava, Ostrava 708 33, Czech RepublicSignificant 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 ∆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.http://www.mdpi.com/2075-4701/6/12/319austenitic stainless steelheat treatmentcorrosion fatiguefatigue crack growth rateintergranular corrosion
spellingShingle Irena Vlčková
Petr Jonšta
Zdeněk Jonšta
Petra Váňová
Taťána Kulová
Corrosion Fatigue of Austenitic Stainless Steels for Nuclear Power Engineering
Metals
austenitic stainless steel
heat treatment
corrosion fatigue
fatigue crack growth rate
intergranular corrosion
title Corrosion Fatigue of Austenitic Stainless Steels for Nuclear Power Engineering
title_full Corrosion Fatigue of Austenitic Stainless Steels for Nuclear Power Engineering
title_fullStr Corrosion Fatigue of Austenitic Stainless Steels for Nuclear Power Engineering
title_full_unstemmed Corrosion Fatigue of Austenitic Stainless Steels for Nuclear Power Engineering
title_short Corrosion Fatigue of Austenitic Stainless Steels for Nuclear Power Engineering
title_sort corrosion fatigue of austenitic stainless steels for nuclear power engineering
topic austenitic stainless steel
heat treatment
corrosion fatigue
fatigue crack growth rate
intergranular corrosion
url http://www.mdpi.com/2075-4701/6/12/319
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