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In the presented work, new composite nanomaterials, based on graphene oxide and styrene, have been developed for the retention purpose. 85Sr and 137Cs represent two of the main fission products being present in radioactive wastes from nuclear power cycle. The graphene oxide samples were prepared from natural graphite using high intensity cavitation field in a pressurized (6 bar) batch-ultrasonic reactor. Graphene oxide polystyrene composite was synthesized using direct emulsion polymerization of styrene in the presence of graphene oxide at 90 °C. The basic method used for the evaluation of nanomaterial retention properties was batch sorption methodology, based on a contact of solid material with a tracer solution under defined boundary conditions (solid/solution ratio, time, solution composition as pH and ionic strength).
Keywords: graphene oxide, sorption, radionuclides© This is an open access article distributed under the Creative Commons Attribution License which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.