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Sorption of strontium on uranyl peroxide: implications for a high-level nuclear waste repository
Sureda Pastor, Rosa María; Martínez Lladó, Xavier; Rovira Boixaderas, Miquel; Pablo Ribas, Joan de; Casas Pons, Ignasi; Giménez Izquierdo, Francisco Javier
Universitat Politècnica de Catalunya. Departament d'Enginyeria Química; Universitat Politècnica de Catalunya. SETRI - Grup de Tècniques de Separació i Tractament de Residus Industrials
Strontium-90 is considered the most important radioactive isotope in the environment and one of the most frequently occurring radionuclides in groundwaters at nuclear facilities. The uranyl peroxide studtite (UO2O2 center dot 4H(2)O) has been observed to be formed in spent nuclear fuel leaching experiments and seems to have a relatively high sorption capacity for some radionuclides. In this work, the sorption of strontium onto studtite is studied as a function of time. strontium concentration in solution and pH. The main results obtained are (a) sorption is relatively fast although slower than for cesium; (b) strontium seems to be sorbed via a monolayer coverage of the studtite surface, (c) sorption has a strong dependence on ionic strength, is negligible at acidic pH, and increases at neutral to alkaline pH (almost 100% of the strontium in solution is sorbed above pH 10). These results point to uranium secondary solid phase formation on the spent nuclear fuel as an important mechanism for strontium retention in a high-level nuclear waste repository (HLNW). (C) 2010 Elsevier B.V. All rights reserved.
Peer Reviewed
Àrees temàtiques de la UPC::Desenvolupament humà i sostenible::Política i gestió ambiental::Gestió de residus
Radioactive wastes
Strontium
Spent nuclear fuel
High-level nuclear waste repository
Sorption
Langmuir isotherm
Residus radioactius
Attribution-NonCommercial-NoDerivs 3.0 Spain
http://creativecommons.org/licenses/by-nc-nd/3.0/es/
info:eu-repo/semantics/publishedVersion
Article
Elsevier
         

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