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dc.contributor.authorMartínez Torrents, Albert
dc.contributor.authorSerrano Purroy, Daniel
dc.contributor.authorSureda, R.
dc.contributor.authorCasas Pons, Ignasi
dc.contributor.authorPablo Ribas, Joan de
dc.contributor.otherUniversitat Politècnica de Catalunya. Departament d'Enginyeria Química
dc.date.accessioned2017-05-12T07:44:19Z
dc.date.available2017-05-12T07:44:19Z
dc.date.issued2017-05-01
dc.identifier.citationMartinez, A., Serrano-Purroy, D., Sureda, R., Casas, I., Pablo, J. Instant release fraction corrosion studies of commercial UO2 BWR spent nuclear fuel. "Journal of nuclear materials", 1 Maig 2017, vol. 488, p. 302-313.
dc.identifier.issn0022-3115
dc.identifier.urihttp://hdl.handle.net/2117/104344
dc.description.abstractThe instant release fraction of a spent nuclear fuel is a matter of concern in the performance assessment of a deep geological repository since it increases the radiological risk. Corrosion studies of two different spent nuclear fuels were performed using bicarbonate water under oxidizing conditions to study their instant release fraction. From each fuel, cladded segments and powder samples obtained at different radial positions were used. The results were normalised using the specific surface area to permit a comparison between fuels and samples. Different radionuclide dissolution patterns were studied in terms of water contact availability and radial distribution in the spent nuclear fuel. The relationship between the results of this work and morphological parameters like the grain size or irradiation parameters such as the burn-up or the linear power density was studied in order to increase the understanding of the instant release fraction formation.
dc.format.extent12 p.
dc.language.isoeng
dc.publisherElsevier
dc.subjectÀrees temàtiques de la UPC::Enginyeria química
dc.subject.lcshNuclear power plants
dc.titleInstant release fraction corrosion studies of commercial UO2 BWR spent nuclear fuel
dc.typeArticle
dc.subject.lemacCentrals nuclears
dc.contributor.groupUniversitat Politècnica de Catalunya. SETRI - Grup de Tècniques de Separació i Tractament de Residus Industrials
dc.identifier.doi10.1016/j.jnucmat.2017.03.022
dc.relation.publisherversionhttp://www.sciencedirect.com/science/article/pii/S0022311517304233
dc.rights.accessOpen Access
local.identifier.drac19857545
dc.description.versionPreprint
local.citation.authorMartinez, A.; Serrano-Purroy, D.; Sureda, R.; Casas, I.; Pablo, J.
local.citation.publicationNameJournal of nuclear materials
local.citation.volume488
local.citation.startingPage302
local.citation.endingPage313


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