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hal.structure.identifierService Plutonium Uranium et Actinides mineurs [SPUA]
dc.contributor.authorBERZATI, Ségolène
hal.structure.identifierService Plutonium Uranium et Actinides mineurs [SPUA]
dc.contributor.authorVAUDEZ, Stéphane
hal.structure.identifierService Plutonium Uranium et Actinides mineurs [SPUA]
dc.contributor.authorBELIN RENAUD, C.
hal.structure.identifierService Plutonium Uranium et Actinides mineurs [SPUA]
dc.contributor.authorLÉCHELLE, Jacques
hal.structure.identifierService Plutonium Uranium et Actinides mineurs [SPUA]
dc.contributor.authorMARC, Yves
hal.structure.identifierService Plutonium Uranium et Actinides mineurs [SPUA]
dc.contributor.authorRICHAUD, Jean-Christophe
hal.structure.identifierInstitut de Chimie de la Matière Condensée de Bordeaux [ICMCB]
dc.contributor.authorHEINTZ, Jean-Marc
dc.date.issued2014
dc.identifier.issn0022-3115
dc.description.abstractEnDiffusion mechanisms occurring during the sintering of oxide ceramics are affected by the oxygen content of the atmosphere, as it imposes the nature and the concentration of structural defects in the material. Thus, the oxygen partial pressure, p(O2), of the sintering gas has to be precisely controlled, otherwise a large dispersion in various parameters, critical for the manufacturing of ceramics such as nuclear oxides fuels, is likely to occur. In the present work, the densification behaviour and the solid solution formation of a mixed uranium-plutonium oxide (MOX) were investigated. The initial mixture, composed of 70% UO2 + 30% PuO2, was studied at p(O2) ranging from 10−15 to 10−4 atm up to 1873 K both with dilatometry and in situ high temperature X-ray diffraction. This study has shown that the initial oxides UO2+x and PuO2−x first densify during heating and then the solid solution formation starts at about 200 K higher. The densification and the formation of the solid solution both occur at a lower temperature when p(O2) increases. Based on this result, it is possible to better define the sintering atmosphere, eventually leading to optimized parameters such as density, oxygen stoichiometry and cations homogenization of nuclear ceramics and of a wide range of industrial ceramic materials.
dc.language.isoen
dc.publisherElsevier
dc.title.enControlling the oxygen potential to improve the densification and the solid solution formation of uranium-plutonium mixed oxides
dc.typeArticle de revue
dc.identifier.doi10.1016/j.jnucmat.2013.12.014
dc.subject.halChimie/Matériaux
bordeaux.journalJournal of Nuclear Materials
bordeaux.page115-124
bordeaux.volume447
bordeaux.issue1-3
bordeaux.peerReviewedoui
hal.identifierhal-00959316
hal.version1
hal.popularnon
hal.audienceInternationale
hal.origin.linkhttps://hal.archives-ouvertes.fr//hal-00959316v1
bordeaux.COinSctx_ver=Z39.88-2004&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.jtitle=Journal%20of%20Nuclear%20Materials&rft.date=2014&rft.volume=447&rft.issue=1-3&rft.spage=115-124&rft.epage=115-124&rft.eissn=0022-3115&rft.issn=0022-3115&rft.au=BERZATI,%20S%C3%A9gol%C3%A8ne&VAUDEZ,%20St%C3%A9phane&BELIN%20RENAUD,%20C.&L%C3%89CHELLE,%20Jacques&MARC,%20Yves&rft.genre=article


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