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hal.structure.identifierService d'Etudes Mécaniques et Thermiques [SEMT]
dc.contributor.authorDOYEN, Olivier
hal.structure.identifierService d'Etudes Mécaniques et Thermiques [SEMT]
hal.structure.identifierInstitut de Chimie de la Matière Condensée de Bordeaux [ICMCB]
dc.contributor.authorGLOANNEC, Brendan Le
hal.structure.identifierScience et Ingénierie des Matériaux et Procédés [SIMaP ]
dc.contributor.authorDESCHAMPS, Alexis
hal.structure.identifierScience et Ingénierie des Matériaux et Procédés [SIMaP ]
dc.contributor.authorGEUSER, Frédéric De
hal.structure.identifierInstitut de Recherche Dupuy de Lôme [IRDL]
dc.contributor.authorPOUVREAU, Cédric
hal.structure.identifierInstitut de Chimie de la Matière Condensée de Bordeaux [ICMCB]
dc.contributor.authorPOULON-QUINTIN, Angeline
dc.date.issued2019-05
dc.identifier.issn0022-3115
dc.description.abstractEnDevelopment and characterization of clad-to-plug resistance upset welds is presented for two oxide dispersion strengthened steels candidates for sodium-cooled fast reactors fuel cladding: 9Cr ferrito-martensitic steel and 14Cr ferritic steel. A comparative approach is adopted regarding these two materials implying weldability studies and weld mechanical strength tests. A special attention is paid on welding metallurgical effects on the specific microstructure of these materials. Among others, some major grain property modifications by dynamic recrystallization and a slight modification of precipitate sizes and volume fraction are found and discussed.
dc.language.isoen
dc.publisherElsevier
dc.rights.urihttp://creativecommons.org/licenses/by-nc/
dc.subject.enMicrostructure
dc.subject.enNuclear fuel cladding
dc.subject.enODS steel
dc.subject.enResistance upset welding
dc.subject.enNano-precipitates
dc.subject.enEBSD
dc.subject.enSAXS
dc.title.enFerritic and martensitic ODS steel resistance upset welding of fuel claddings: Weldability assessment and metallurgical effects
dc.typeArticle de revue
dc.identifier.doi10.1016/j.jnucmat.2019.03.013
dc.subject.halChimie/Matériaux
bordeaux.journalJournal of Nuclear Materials
bordeaux.page326-333
bordeaux.volume518
bordeaux.peerReviewedoui
hal.identifierhal-02090827
hal.version1
hal.popularnon
hal.audienceInternationale
hal.origin.linkhttps://hal.archives-ouvertes.fr//hal-02090827v1
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