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dc.contributor.authorSTUMPF Silviaen_GB
dc.contributor.authorSEIBERT ALICEen_GB
dc.contributor.authorGOUDER Thomasen_GB
dc.contributor.authorHUBER Franken_GB
dc.contributor.authorWISS Thierryen_GB
dc.contributor.authorRÖMER J.en_GB
dc.date.accessioned2010-02-25T14:49:52Z-
dc.date.available2009-03-04en_GB
dc.date.available2010-02-25T14:49:52Z-
dc.date.created2009-03-04en_GB
dc.date.issued2009en_GB
dc.date.submitted2009-03-04en_GB
dc.identifier.citationJOURNAL OF NUCLEAR MATERIALS vol. 385 p. 208-211en_GB
dc.identifier.issn0022-3115en_GB
dc.identifier.urihttp://www.elsevier.com/locate/jnucmaten_GB
dc.identifier.urihttp://publications.jrc.ec.europa.eu/repository/handle/JRC50733-
dc.description.abstractThe presented work aims to reproducibly prepare UO2¿Pd thin film model systems for spent nuclear fuel in order to further investigate surface reactions of these films under relevant redox conditions. The sputter co-deposition of U and Pd (fission product) in the presence of O2 results in the homogenous distribution of Pd in a crystalline UO2 matrix. Heating the films causes the diffusion of film components. Hereby, the formation of e-particles has to be clarified. First electrochemical studies show the influence of the nobel metal Pd on the redox behaviour of UO2. With increasing Pd concentration the matrix dissolution is decreased. However, we could demonstrate that blocked oxidation processes are of temporary nature. The passivation of the Pd reactive sites with increasing number of cycles finally induces the approximation of the mixed system to the redox behaviour of the pure UO2 system.en_GB
dc.description.sponsorshipJRC.E.6-Actinides researchen_GB
dc.format.mediumPrinteden_GB
dc.languageENGen_GB
dc.publisherELSEVIER SCIENCE BVen_GB
dc.relation.ispartofseriesJRC50733en_GB
dc.titleDevelopment of Fuel-model Interfaces: Investigations by XPS, TEM, SEM and AFMen_GB
dc.typeArticles in periodicals and booksen_GB
dc.identifier.doi10.1016/j.jnucmat.2008.08.061en_GB
JRC Directorate:Nuclear Safety and Security

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