Article
Comparison of Solvent Extraction and Extraction Chromatography Resin Techniques for Uranium Isotopic Characterization in High-Level Radioactive Waste and Barrier Materials
Author/s | Hurtado Bermúdez, Santiago José
Villa Alfageme, María Más Balbuena, José Luis Alba Carranza, María Dolores |
Department | Universidad de Sevilla. Departamento de Física Aplicada II Universidad de Sevilla. Departamento de Física Aplicada I |
Publication Date | 2018-07 |
Deposit Date | 2024-01-16 |
Published in |
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Abstract | The development of Deep Geological Repositories (DGP) to the storage of high-level radioactive waste (HLRW) is mainly focused in systems of multiple barriers based on the use of clays, and particularly bentonites, as natural ... The development of Deep Geological Repositories (DGP) to the storage of high-level radioactive waste (HLRW) is mainly focused in systems of multiple barriers based on the use of clays, and particularly bentonites, as natural and engineered barriers in nuclear waste isolation due to their remarkable properties. Due to the fact that uranium is the major component of HLRW, it is required to go in depth in the analysis of the chemistry of the reaction of this element within bentonites. The determination of uranium under the conditions of HLRW, including the analysis of silicate matrices before and after the uranium-bentonite reaction, was investigated. The performances of a state-of-the-art and widespread radiochemical method based on chromatographic UTEVA resins, and a well-known and traditional method based on solvent extraction with tri-n-butyl phosphate (TBP), for the analysis of uranium and thorium isotopes in solid matrices with high concentrations of uranium were analysed in detail. In the development of this comparison, both radiochemical approaches have an overall excellent performance in order to analyse uranium concentration in HLRW samples. However, due to the high uranium concentration in the samples, the chromatographic resin is not able to avoid completely the uranium contamination in the thorium fraction. |
Funding agencies | Ministerio de Ciencia e Innovación (MICIN). España MAT2015-63929-R |
Project ID. | MAT2015-63929-R |
Citation | Hurtado Bermúdez, S.J., Villa Alfageme, M., Mas Balbuena, J.L. y Alba Carranza, M.D. (2018). Comparison of Solvent Extraction and Extraction Chromatography Resin Techniques for Uranium Isotopic Characterization in High-Level Radioactive Waste and Barrier Materials. Applied Radiation and Isotopes, 137, 177-183. https://doi.org/10.1016/j.apradiso.2018.04.008. |
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ARI-LLX-UTEVA.pdf | 969.0Kb | [PDF] | View/ | Artículo pricnipal, incluye los datos experimentales |