A non-isothermal reactive transport model of the long-term geochemical evolution at the disposal cell scale in a HLW repository in granite

UDC.coleccionInvestigaciónes_ES
UDC.departamentoEnxeñaría Civiles_ES
UDC.grupoInvXestión Sostible dos Recursos Hídricos e do Chan (AQUATERRA)es_ES
UDC.journalTitleApplied Clay Sciencees_ES
UDC.startPage107018es_ES
UDC.volume242es_ES
dc.contributor.authorMontenegro, Luis
dc.contributor.authorSamper, Javier
dc.contributor.authorMon, Alba
dc.contributor.authorDe Windt, Laurent
dc.contributor.authorGarcía, Enrique
dc.contributor.authorSamper, Aurora C.
dc.date.accessioned2023-10-23T18:59:12Z
dc.date.available2023-10-23T18:59:12Z
dc.date.issued2023
dc.descriptionFinanciado para publicación en acceso aberto: Universidade da Coruña/CISUGes_ES
dc.description.abstract[Abstract:] The assessment of the long-term performance of the engineered barrier systems of high-level radioactive waste (HLW) repositories requires the use of reactive transport models. Here a non-isothermal reactive transport model of the long-term geochemical evolution of a HLW disposal cell in a granitic host rock is presented. The model includes the vitrified waste (40 cm in diameter), the carbon-steel canister (5 cm thick), the saturated FEBEX bentonite buffer (75 cm thick) and the reference granitic rock. The model accounts for the thermal transient stage and assumes generalized steel corrosion under anaerobic conditions with a corrosion rate equal to 1.41 m/y. Canister failure is assumed to occur when the remaining canister thickness is equal to 3.5 cm at t = 25,000 years. Canister corrosion caused an increase in pH. The computed pH in the canister just before canister failure (t = 25,000 years) was equal to 9.25 and ranged from 7.82 to 9.25 in the bentonite. Magnetite, the main corrosion product, precipitated in the bentonite and especially in the canister. The thickness of magnetite precipitation band in the bentonite was 1 cm. Siderite precipitated at both sides of the canister/bentonite interface. The precipitation front penetrated >1 cm into the bentonite. Nuclear glass started dissolving after canister failure (t > 25,000 years). The concentration of dissolved silica increased in the inner part of the glass until t = 30,000 years and decreased in the outer part of the glass due to the out diffusion of dissolved silica into the canister and the bentonite. This diffusive flux caused the precipitation of greenalite at the glass/canister and canister/bentonite interfaces. The pH at the end of the simulation (t = 50,000 years) ranged from 7.93 to 7.89 in the glass, from 7.89 to 8.66 in the canister and from 7.87 to 8.6 in the bentonite. Magnetite precipitated in the canister while there was carbon steel to corrode. Once the canister was fully corroded, magnetite redissolved near the glass/canister interface. Greenalite precipitated in the canister and the bentonite, especially at the glass/canister interface and siderite precipitated at the canister/bentonite interface. The simulation results should be useful for the performance assessment of engineered barriers of radioactive waste repositories in granitic host rocks.es_ES
dc.description.sponsorshipThe research leading to these results was funded by ENRESA within the Work Package ACED of EURAD (European Joint Programme on Radioactive Waste Management of the European Union, EC grant agreement nº 847593), the Spanish Ministry of Science and Innovation (PID2019-109544RB-I00) and the Galician Regional Government (Grant ED431C2021/54). Funding for open access charge was provided by Universidade da Coru˜na/CISUG. We thank Diederik Jacques, leader of the ACED Work Package, and the ACED members for many enriching discussions, suggestions and recommendations, Erika Neeft (COVRA) for providing the temperature curves, and the special editor and the two anonymous reviewers for their comments and corrections.es_ES
dc.description.sponsorshipXunta de Galicia; ED431C2021/54es_ES
dc.identifier.citationMontenegro, L., Samper, J., Mon, A., De Windt, L., Samper, A. C., García, E. (2023). A non-isothermal reactive transport model of the long-term geochemical evolution at the disposal cell scale in a HLW repository in granite. Applied Clay Science, 242, 107018. https://doi.org/10.1016/j.clay.2023.107018es_ES
dc.identifier.doi10.1016/j.clay.2023.107018
dc.identifier.urihttp://hdl.handle.net/2183/33897
dc.language.isoenges_ES
dc.publisherElsevieres_ES
dc.relation.projectIDinfo:eu-repo/grantAgreement/EC/H2020/847593es_ES
dc.relation.projectIDinfo:eu-repo/grantAgreement/AEI/Plan Estatal de Investigación Científica y Técnica y de Innovación 2017-2020/PID2019-109544RB-I00es_ES
dc.relation.urihttps://doi.org/10.1016/j.clay.2023.107018es_ES
dc.rightsLicenza Creative Commons BY-NC-NDes_ES
dc.rights.accessRightsopen accesses_ES
dc.rights.urihttps://creativecommons.org/licenses/by-nc-nd/4.0/deed.es
dc.subjectTHC modeles_ES
dc.subjectBentonitees_ES
dc.subjectCorrosion productses_ES
dc.subjectReactive transportes_ES
dc.subjectCanister corrosiones_ES
dc.subjectInternational Simple Glasses_ES
dc.titleA non-isothermal reactive transport model of the long-term geochemical evolution at the disposal cell scale in a HLW repository in granitees_ES
dc.typejournal articlees_ES
dspace.entity.typePublication
relation.isAuthorOfPublication3a6c1aa9-0798-4171-8e5e-b12ca73126aa
relation.isAuthorOfPublication58f7776d-63f2-44d5-9d30-940254781c57
relation.isAuthorOfPublication24ca47ff-2db8-4f95-97f8-1520dc9dd34c
relation.isAuthorOfPublication.latestForDiscovery3a6c1aa9-0798-4171-8e5e-b12ca73126aa

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