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...
Main Authors: | , , , , |
---|---|
Format: | Article |
Language: | English |
Published: |
MDPI AG
2016-12-01
|
Series: | Metals |
Subjects: | |
Online Access: | http://www.mdpi.com/2075-4701/6/12/319 |
_version_ | 1818570456887721984 |
---|---|
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. |
first_indexed | 2024-12-14T13:41:33Z |
format | Article |
id | doaj.art-e367f25d2c90437597711ca5e480133c |
institution | Directory Open Access Journal |
issn | 2075-4701 |
language | English |
last_indexed | 2024-12-14T13:41:33Z |
publishDate | 2016-12-01 |
publisher | MDPI AG |
record_format | Article |
series | Metals |
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 |
work_keys_str_mv | AT irenavlckova corrosionfatigueofausteniticstainlesssteelsfornuclearpowerengineering AT petrjonsta corrosionfatigueofausteniticstainlesssteelsfornuclearpowerengineering AT zdenekjonsta corrosionfatigueofausteniticstainlesssteelsfornuclearpowerengineering AT petravanova corrosionfatigueofausteniticstainlesssteelsfornuclearpowerengineering AT tatanakulova corrosionfatigueofausteniticstainlesssteelsfornuclearpowerengineering |