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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Auteurs principaux: Jan Štefan, Jan Siegl, Jan Adámek, Radim Kopřiva, Michal Falcník
Format: article
Langue:EN
Publié: MDPI AG 2021
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Accès en ligne:https://doaj.org/article/8cc26b3757894f9ca21a9e590fb3f364
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