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Radioactive waste treatment using natural Syrian bentonite

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Abstract

The uptake of137Cs and90Sr/90Y onto Syrian bentonite has been studed, using batch and column tracer techniques in order to investigate its utilization for aqueous radioactive effluent treatment. Parameters influencing the percent uptake considered and studied in this work are: nuclide concentration, pH of the aqueous phase, heat treatment and particle size. Leaching experiments using natural sea and ground waters were carried out on bentonite/cement composites. They demonstrated the effectiveness of calcination and cement containment.

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  1. Atomic Energy Commission of Syria, P.O. Box 6091, Damascus, (Syria)

    J. Kh. Abou-Jamous

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  1. J. Kh. Abou-Jamous
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Abou-Jamous, J.K. Radioactive waste treatment using natural Syrian bentonite. Journal of Radioanalytical and Nuclear Chemistry, Articles 162, 325–338 (1992). https://doi.org/10.1007/BF02035393

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  • DOI: https://doi.org/10.1007/BF02035393

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