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Vitrified Municipal Waste for the Immobilization of Radioactive Waste: Preparation and Characterization of Borosilicate Glasses Modified with Metal Oxides

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Abstract

Municipal solid waste is used as a raw material for the production of borosilicate glasses by melting annealing technique. Many chemical and physical measurements are studied to test their possibility in the immobilization of radioactive wastes. The results show good behaviors against gamma radiation doses such as suitable density and microhardness values, stable behaviors towards low and high doses of gamma radiation indicated by IR and EPR techniques. As well as good chemical durability in H2O and NaOH leaching solutions. The network structure of borosilicate glasses consists of tetrahedral silicate units SiO4 and the triangle BO3 or tetrahedral BO4 groups which strengthen the structure of glasses and enhance their desired properties for achieving the goal of immobilizing nuclear wastes.

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  1. Radiation Chemistry Department, National Center for Radiation Research and Technology, Atomic Energy Authority, P. O. Box 8029, Nasr City, Cairo, 11371, Egypt

    E. M. Abou Hussein

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Abou Hussein, E.M. Vitrified Municipal Waste for the Immobilization of Radioactive Waste: Preparation and Characterization of Borosilicate Glasses Modified with Metal Oxides. Silicon 11, 2675–2688 (2019). https://doi.org/10.1007/s12633-018-0056-1

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  • DOI: https://doi.org/10.1007/s12633-018-0056-1

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