Microstructure and Failure Processes of Reactor Pressure Vessel Austenitic Cladding
This paper is dedicated to an experimental program focused on the evaluation of microstructure and failure mechanisms of WWER 440 type nuclear reactor pressure vessel cladding made from Sv 08Kh19N10G2B stainless steel. Static fracture toughness tests performed on standard precracked single edge bend...
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| Format: | Article |
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MDPI AG
2021-10-01
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| Series: | Metals |
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| Online Access: | https://www.mdpi.com/2075-4701/11/11/1676 |
| _version_ | 1797509380126539776 |
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| author | Jan Štefan Jan Siegl Jan Adámek Radim Kopřiva Michal Falcník |
| author_facet | Jan Štefan Jan Siegl Jan Adámek Radim Kopřiva Michal Falcník |
| author_sort | Jan Štefan |
| collection | DOAJ |
| description | This paper is dedicated to an experimental program focused on the evaluation of microstructure and failure mechanisms of WWER 440 type nuclear reactor pressure vessel cladding made from Sv 08Kh19N10G2B stainless steel. Static fracture toughness tests performed on standard precracked single edge bend specimens revealed extreme variations in fracture toughness values, <i>J</i><sub>0.2</sub>. Fractured halves of test specimens were subject to detailed fractographic and metallographic analyses in order to identify the causes of this behavior and to determine the relationship between local microstructure, failure mode and fracture toughness. Results indicated that fracture toughness of the cladding was adversely affected by the brittle cracking of sigma particles which caused a considerable decrease in local ductile tearing resistance. Extreme variations in relative amounts of sigma phase, as well as the extreme overall structural heterogeneity of the cladding determined in individual specimens, provided a reasonable explanation for variations in fracture toughness values. |
| first_indexed | 2024-03-10T05:16:53Z |
| format | Article |
| id | doaj.art-8cc26b3757894f9ca21a9e590fb3f364 |
| institution | Directory Open Access Journal |
| issn | 2075-4701 |
| language | English |
| last_indexed | 2024-03-10T05:16:53Z |
| publishDate | 2021-10-01 |
| publisher | MDPI AG |
| record_format | Article |
| series | Metals |
| spelling | doaj.art-8cc26b3757894f9ca21a9e590fb3f3642023-11-23T00:21:54ZengMDPI AGMetals2075-47012021-10-011111167610.3390/met11111676Microstructure and Failure Processes of Reactor Pressure Vessel Austenitic CladdingJan Štefan0Jan Siegl1Jan Adámek2Radim Kopřiva3Michal Falcník4Department of Impact and Waves in Solids, Institute of Thermomechanics of the Czech Academy of Sciences, Dolejškova 1402/5, 182 00 Praha, Czech RepublicDepartment of Materials, Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, Trojanova 13, 120 00 Praha, Czech RepublicDepartment of Materials, Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, Trojanova 13, 120 00 Praha, Czech RepublicDepartment of Mechanical Properties, ÚJV Řež, a. s., Hlavní 130, Řež, 250 68 Husinec, Czech RepublicDepartment of Mechanical Properties, ÚJV Řež, a. s., Hlavní 130, Řež, 250 68 Husinec, Czech RepublicThis paper is dedicated to an experimental program focused on the evaluation of microstructure and failure mechanisms of WWER 440 type nuclear reactor pressure vessel cladding made from Sv 08Kh19N10G2B stainless steel. Static fracture toughness tests performed on standard precracked single edge bend specimens revealed extreme variations in fracture toughness values, <i>J</i><sub>0.2</sub>. Fractured halves of test specimens were subject to detailed fractographic and metallographic analyses in order to identify the causes of this behavior and to determine the relationship between local microstructure, failure mode and fracture toughness. Results indicated that fracture toughness of the cladding was adversely affected by the brittle cracking of sigma particles which caused a considerable decrease in local ductile tearing resistance. Extreme variations in relative amounts of sigma phase, as well as the extreme overall structural heterogeneity of the cladding determined in individual specimens, provided a reasonable explanation for variations in fracture toughness values.https://www.mdpi.com/2075-4701/11/11/1676nuclear reactor pressure vesselaustenitic claddingweld overlayfracture toughness testfractographymetallography |
| spellingShingle | Jan Štefan Jan Siegl Jan Adámek Radim Kopřiva Michal Falcník Microstructure and Failure Processes of Reactor Pressure Vessel Austenitic Cladding Metals nuclear reactor pressure vessel austenitic cladding weld overlay fracture toughness test fractography metallography |
| title | Microstructure and Failure Processes of Reactor Pressure Vessel Austenitic Cladding |
| title_full | Microstructure and Failure Processes of Reactor Pressure Vessel Austenitic Cladding |
| title_fullStr | Microstructure and Failure Processes of Reactor Pressure Vessel Austenitic Cladding |
| title_full_unstemmed | Microstructure and Failure Processes of Reactor Pressure Vessel Austenitic Cladding |
| title_short | Microstructure and Failure Processes of Reactor Pressure Vessel Austenitic Cladding |
| title_sort | microstructure and failure processes of reactor pressure vessel austenitic cladding |
| topic | nuclear reactor pressure vessel austenitic cladding weld overlay fracture toughness test fractography metallography |
| url | https://www.mdpi.com/2075-4701/11/11/1676 |
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