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

  • E. M. Abou HusseinEmail author
Original Paper
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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.

Keywords

Vitrification Nuclear waste glass Gamma radiation Borosilicate Chemical durability 

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Copyright information

© Springer Nature B.V. 2019

Authors and Affiliations

  1. 1.Radiation Chemistry Department, National Center for Radiation Research and TechnologyAtomic Energy AuthorityNasr CityEgypt

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