Effect of clays and metal containers in retaining Sm3+ and ZrO2+ and the process of reversibility

Knowledge and understanding about radionuclides retention processes on the materials composing the engineered barrier (clay mineral and metallic container waste) are required to ensure the safety and the long-term performance of radioactive waste disposal. Therefore, the present study focuses on the...

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Autores: El Mrabet, Said, Castro Arroyo, Miguel Ángel, Hurtado Bermúdez, Santiago José, Orta Cuevas, María del Mar, Pazos, M. Carolina, Villa Alfageme, María, Alba, María D.
Formato: artículo
Estado:Versión enviada para evaluación y publicación
Fecha de publicación:2014
País:España
Recursos:Universidad de Sevilla (US)
Repositorio:idUS. Depósito de Investigación de la Universidad de Sevilla
OAI Identifier:oai:idus.us.es:11441/133660
Acesso em linha:https://hdl.handle.net/11441/133660
https://doi.org/10.2138/am.2014.4665
Access Level:acceso abierto
Palavra-chave:Actinide
Clay minerals
Geological disposal
Metallic canister
Radionuclide waste
Sorption/desorption
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spelling Effect of clays and metal containers in retaining Sm3+ and ZrO2+ and the process of reversibilityEl Mrabet, SaidCastro Arroyo, Miguel ÁngelHurtado Bermúdez, Santiago JoséOrta Cuevas, María del MarPazos, M. CarolinaVilla Alfageme, MaríaAlba, María D.ActinideClay mineralsGeological disposalMetallic canisterRadionuclide wasteSorption/desorptionKnowledge and understanding about radionuclides retention processes on the materials composing the engineered barrier (clay mineral and metallic container waste) are required to ensure the safety and the long-term performance of radioactive waste disposal. Therefore, the present study focuses on the competitiveness of clay and the metallic container in the process of adsorption/desorption of the radionuclides simulators of Am3+ and UO22+. For this purpose, a comparative study of the interaction of samarium (chosen as chemical analog for trivalent americium) and zirconyl (as simulator of uranyl and tetravalent actinides) with both FEBEX bentonite and metallic container, under subcritical conditions, was carried out. The results revealed that the AISI-316L steel container, chemical composition detailed in Table 1, immobilized the high-radioactive waste (HRW), even during the corrosion process. The ZrO2+ was irreversibly adsorbed on the minireactor surface. In the case of samarium SEM/EDX analysis revealed the formation of an insoluble phase of samarium silicate on the container surface. There was no evidence of samarium diffusion through the metallic container. Samarium remained adsorbed by the container also after desorption experiment with water. Therefore, steel canister is actively involved in the HRW immobilization.ENRESA 0079000121Dirección General de Investigación Científica y Técnica (DGICYT) CTQ2010-14874Walter de GruyterQuímica InorgánicaFísica Aplicada IIQuímica AnalíticaDirección General de Investigación Científica y Técnica (DGICYT). España2014info:eu-repo/semantics/articleinfo:eu-repo/semantics/submittedVersionapplication/pdfapplication/pdfhttps://hdl.handle.net/11441/133660https://doi.org/10.2138/am.2014.4665reponame:idUS. Depósito de Investigación de la Universidad de Sevillainstname:Universidad de Sevilla (US)InglésAmerican Mineralogist, 99 (4), 696-703.0079000121CTQ2010-14874https://doi.org/10.2138/am.2014.4665info:eu-repo/semantics/openAccessoai:idus.us.es:11441/1336602026-06-17T12:51:07Z
dc.title.none.fl_str_mv Effect of clays and metal containers in retaining Sm3+ and ZrO2+ and the process of reversibility
title Effect of clays and metal containers in retaining Sm3+ and ZrO2+ and the process of reversibility
spellingShingle Effect of clays and metal containers in retaining Sm3+ and ZrO2+ and the process of reversibility
El Mrabet, Said
Actinide
Clay minerals
Geological disposal
Metallic canister
Radionuclide waste
Sorption/desorption
title_short Effect of clays and metal containers in retaining Sm3+ and ZrO2+ and the process of reversibility
title_full Effect of clays and metal containers in retaining Sm3+ and ZrO2+ and the process of reversibility
title_fullStr Effect of clays and metal containers in retaining Sm3+ and ZrO2+ and the process of reversibility
title_full_unstemmed Effect of clays and metal containers in retaining Sm3+ and ZrO2+ and the process of reversibility
title_sort Effect of clays and metal containers in retaining Sm3+ and ZrO2+ and the process of reversibility
dc.creator.none.fl_str_mv El Mrabet, Said
Castro Arroyo, Miguel Ángel
Hurtado Bermúdez, Santiago José
Orta Cuevas, María del Mar
Pazos, M. Carolina
Villa Alfageme, María
Alba, María D.
author El Mrabet, Said
author_facet El Mrabet, Said
Castro Arroyo, Miguel Ángel
Hurtado Bermúdez, Santiago José
Orta Cuevas, María del Mar
Pazos, M. Carolina
Villa Alfageme, María
Alba, María D.
author_role author
author2 Castro Arroyo, Miguel Ángel
Hurtado Bermúdez, Santiago José
Orta Cuevas, María del Mar
Pazos, M. Carolina
Villa Alfageme, María
Alba, María D.
author2_role author
author
author
author
author
author
dc.contributor.none.fl_str_mv Química Inorgánica
Física Aplicada II
Química Analítica
Dirección General de Investigación Científica y Técnica (DGICYT). España
dc.subject.none.fl_str_mv Actinide
Clay minerals
Geological disposal
Metallic canister
Radionuclide waste
Sorption/desorption
topic Actinide
Clay minerals
Geological disposal
Metallic canister
Radionuclide waste
Sorption/desorption
description Knowledge and understanding about radionuclides retention processes on the materials composing the engineered barrier (clay mineral and metallic container waste) are required to ensure the safety and the long-term performance of radioactive waste disposal. Therefore, the present study focuses on the competitiveness of clay and the metallic container in the process of adsorption/desorption of the radionuclides simulators of Am3+ and UO22+. For this purpose, a comparative study of the interaction of samarium (chosen as chemical analog for trivalent americium) and zirconyl (as simulator of uranyl and tetravalent actinides) with both FEBEX bentonite and metallic container, under subcritical conditions, was carried out. The results revealed that the AISI-316L steel container, chemical composition detailed in Table 1, immobilized the high-radioactive waste (HRW), even during the corrosion process. The ZrO2+ was irreversibly adsorbed on the minireactor surface. In the case of samarium SEM/EDX analysis revealed the formation of an insoluble phase of samarium silicate on the container surface. There was no evidence of samarium diffusion through the metallic container. Samarium remained adsorbed by the container also after desorption experiment with water. Therefore, steel canister is actively involved in the HRW immobilization.
publishDate 2014
dc.date.none.fl_str_mv 2014
dc.type.none.fl_str_mv info:eu-repo/semantics/article
info:eu-repo/semantics/submittedVersion
format article
status_str submittedVersion
dc.identifier.none.fl_str_mv https://hdl.handle.net/11441/133660
https://doi.org/10.2138/am.2014.4665
url https://hdl.handle.net/11441/133660
https://doi.org/10.2138/am.2014.4665
dc.language.none.fl_str_mv Inglés
language_invalid_str_mv Inglés
dc.relation.none.fl_str_mv American Mineralogist, 99 (4), 696-703.
0079000121
CTQ2010-14874
https://doi.org/10.2138/am.2014.4665
dc.rights.none.fl_str_mv info:eu-repo/semantics/openAccess
eu_rights_str_mv openAccess
dc.format.none.fl_str_mv application/pdf
application/pdf
dc.publisher.none.fl_str_mv Walter de Gruyter
publisher.none.fl_str_mv Walter de Gruyter
dc.source.none.fl_str_mv reponame:idUS. Depósito de Investigación de la Universidad de Sevilla
instname:Universidad de Sevilla (US)
instname_str Universidad de Sevilla (US)
reponame_str idUS. Depósito de Investigación de la Universidad de Sevilla
collection idUS. Depósito de Investigación de la Universidad de Sevilla
repository.name.fl_str_mv
repository.mail.fl_str_mv
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score 15,301603

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