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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Autores principales:	Jan Štefan, Jan Siegl, Jan Adámek, Radim Kopřiva, Michal Falcník
Formato:	article
Lenguaje:	EN
Publicado:	MDPI AG 2021
Materias:	nuclear reactor pressure vessel austenitic cladding weld overlay fracture toughness test fractography metallography Mining engineering. Metallurgy TN1-997
Acceso en línea:	https://doaj.org/article/8cc26b3757894f9ca21a9e590fb3f364
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spelling	oai:doaj.org-article:8cc26b3757894f9ca21a9e590fb3f3642021-11-25T18:21:08ZMicrostructure and Failure Processes of Reactor Pressure Vessel Austenitic Cladding10.3390/met111116762075-4701https://doaj.org/article/8cc26b3757894f9ca21a9e590fb3f3642021-10-01T00:00:00Zhttps://www.mdpi.com/2075-4701/11/11/1676https://doaj.org/toc/2075-4701This 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.Jan ŠtefanJan SieglJan AdámekRadim KopřivaMichal FalcníkMDPI AGarticlenuclear reactor pressure vesselaustenitic claddingweld overlayfracture toughness testfractographymetallographyMining engineering. MetallurgyTN1-997ENMetals, Vol 11, Iss 1676, p 1676 (2021)
institution	DOAJ
collection	DOAJ
language	EN
topic	nuclear reactor pressure vessel austenitic cladding weld overlay fracture toughness test fractography metallography Mining engineering. Metallurgy TN1-997
spellingShingle	nuclear reactor pressure vessel austenitic cladding weld overlay fracture toughness test fractography metallography Mining engineering. Metallurgy TN1-997 Jan Štefan Jan Siegl Jan Adámek Radim Kopřiva Michal Falcník Microstructure and Failure Processes of Reactor Pressure Vessel Austenitic Cladding
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.
format	article
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
title	Microstructure and Failure Processes of Reactor Pressure Vessel Austenitic Cladding
title_short	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_sort	microstructure and failure processes of reactor pressure vessel austenitic cladding
publisher	MDPI AG
publishDate	2021
url	https://doaj.org/article/8cc26b3757894f9ca21a9e590fb3f364
work_keys_str_mv	AT janstefan microstructureandfailureprocessesofreactorpressurevesselausteniticcladding AT jansiegl microstructureandfailureprocessesofreactorpressurevesselausteniticcladding AT janadamek microstructureandfailureprocessesofreactorpressurevesselausteniticcladding AT radimkopriva microstructureandfailureprocessesofreactorpressurevesselausteniticcladding AT michalfalcnik microstructureandfailureprocessesofreactorpressurevesselausteniticcladding
_version_	1718411270342836224

Microstructure and Failure Processes of Reactor Pressure Vessel Austenitic Cladding

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