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dc.creatorVilla Alfageme, Maríaes
dc.creatorHurtado Bermúdez, Santiago Josées
dc.creatorEl Mrabet, Saides
dc.creatorPazos Zarama, Mery Carolinaes
dc.creatorCastro Arroyo, Miguel Ángeles
dc.creatorAlba, María D.es
dc.date.accessioned2018-04-10T10:25:22Z
dc.date.available2018-04-10T10:25:22Z
dc.date.issued2015
dc.identifier.citationVilla Alfageme, M., Hurtado Bermúdez, S.J., El Mrabet, S., Pazos Zarama, M.C., Castro Arroyo, M.Á. y Alba, M.D. (2015). Uranium immobilization by FEBEX bentonite and steel barriers in hydrothermal conditions. Chemical Engineering Journal, 269, 279-287.
dc.identifier.issn1385-8947es
dc.identifier.urihttps://hdl.handle.net/11441/72278
dc.description.abstractFEBEX clay is considered a reference material in engineered barriers for safe storage of nuclear waste and uranium is a minor component of high-level radioactive waste (HLRW) and a main component of the spent nuclear fuel (SNF). Here, the kinetics of reaction of uranium with FEBEX was investigated in addition to the uranium immobilisation ability and the structural analysis of the reaction products. Hydrothermal treatments were accomplished with UO22+ and tetravalent actinide simulator ZrO2+, also present in HLRW. The quantification of the reaction was performed through gamma spectrometry of uranium. Two mechanisms for UO22+ retention by FEBEX were detected: adsorption and formation of stable and insoluble new phases. The structural analyses performed using ZrO2+, confirmed the uranium adsorption and the presence of new phases, ZrO2 and Zr(SiO4), that emphasise the existence of a chemical reaction with the bentonite. The analysis of the velocity of reaction uranium-clay minerals revealed temperature dependence. An exponential fitting suggested that the removal of uranium from solution at temperatures over 200 °C could be completed in less than a year. For lower temperatures, several years are needed. Milliequivalents of UO22+ immobilised by the clay depended on temperature and time and were over cation exchange capacity (CEC) of FEBEX even at 100 °C (reaching 600% of CEC). The reaction with steel, also temperature dependent, was finally analysed. At 200 °C 40–70% of uranium reacted with steel. But only 30–15% reacted at 300 °C and 100 °C. The reactions provide a stable immobilisation mechanism for uranium even when its sorption and swelling capacities fail. Our experiments will be of particular interest for very deep borehole disposals were higher temperatures and pressures are expected.es
dc.description.sponsorshipENRESA 0079000121es
dc.description.sponsorshipFEDER Junta de Andalucía P12-FQM-567es
dc.formatapplication/pdfes
dc.language.isoenges
dc.publisherElsevieres
dc.relation.ispartofChemical Engineering Journal, 269, 279-287.
dc.rightsAttribution-NonCommercial-NoDerivatives 4.0 Internacional*
dc.rights.urihttp://creativecommons.org/licenses/by-nc-nd/4.0/*
dc.subjectBentonitees
dc.subjectsmectitees
dc.subjectdisilicateses
dc.subjectsteeles
dc.subjecturaniumes
dc.subjectradioactive wastees
dc.titleUranium immobilization by FEBEX bentonite and steel barriers in hydrothermal conditionses
dc.typeinfo:eu-repo/semantics/articlees
dcterms.identifierhttps://ror.org/03yxnpp24
dc.type.versioninfo:eu-repo/semantics/submittedVersiones
dc.rights.accessRightsinfo:eu-repo/semantics/openAccesses
dc.contributor.affiliationUniversidad de Sevilla. Departamento de Química Inorgánicaes
dc.contributor.affiliationUniversidad de Sevilla. Departamento de Física Aplicada IIes
dc.relation.projectIDP12-FQM-567es
dc.relation.projectID0079000121es
dc.relation.publisherversionhttp://dx.doi.org/ http://dx.doi.org/es
dc.identifier.doihttp://dx.doi.org/es
idus.format.extent9 p.es
dc.journaltitleChemical Engineering Journales
dc.publication.volumen269es
dc.publication.initialPage279es
dc.publication.endPage287es
dc.contributor.funderENRESA
dc.contributor.funderJunta de Andalucía

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