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Radionuclide liquid waste treatment of 68[superscript]Ge by graphene oxide based nanomaterials

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dc.contributor.advisor Lekala, Mantile Leslie
dc.contributor.advisor Khenfouch, Mohammed
dc.contributor.author Genu, Aurelia Khanyiswa
dc.date.accessioned 2019-08-27T09:30:22Z
dc.date.available 2019-08-27T09:30:22Z
dc.date.issued 2019-06
dc.date.submitted 2019-08
dc.identifier.uri http://hdl.handle.net/10500/25715
dc.description.abstract Radionuclide liquid wastes generated from nuclear facilities can affect humans and the environment, thus substantial attention for their safe management has been received worldwide. Treatment of radionuclide liquid wastes is an important step in its management. In the present work, new composite nanomaterials, graphene oxide base nanomaterial (GO) are developed for treatment purpose. Graphene oxide (GO), one of the most graphene derivatives, its unique properties, such as chemical stability, hydrophilicity, large surface area and functional groups, make them able to form strong chemical bonds with radionuclides. GO was successfully synthesized via Hummers method, characterized by Raman spectroscopy, X-Ray Diffraction (XRD), UV/Vis Spectroscopy, Fourier transform infrared spectroscopy (FTIR) and Scanning electron microscopy (SEM) and applied as an adsorbent in removal of the metallic long-lived radionuclide 68Ge from of aqueous solution The method used for evaluation of nanomaterials retention properties was sorption experiment, being based on contact of solid material with tracer solution under defined boundary conditions (solid/solution ratio, solution composition etc.). Two sorption experimental methods were used in this study. Firstly, an aqueous solution of 68Ge radionuclide solution mixed with GO solution, the solution was filtered using syringe filter membrane unit and the aliquot was quantified by gamma spectrometry. Secondly, the 68Ge radionuclide was mixed with GO solid powder, suspension rotated in a mechanical shaker, centrifuged, an aliquot of 1.0 ml sample taken for gamma spectroscopy and the supernatant was put in an oven to dry overnight for characterization analysis. The results obtained from experiments were the evaluated, using sorption percentage equation and showed that the GO had much low sorption capacity for the pre-concentration of radionuclides from aqueous solutions. The function of the pH, the ionic strength and the reduction of GO will be investigated for future studies for the improvement of the research results. en
dc.format.extent 1 online resource (xi, 72 leaves) : illustrations (some color), graphs (some color) en
dc.language.iso en en
dc.subject 68[superscript]Ge radionuclides en
dc.subject Carbon en
dc.subject Carbon based nanomaterials en
dc.subject Graphene en
dc.subject Graphene oxide en
dc.subject Hummers methods en
dc.subject Adsorbent en
dc.subject Adsorption en
dc.subject Characterization techniques en
dc.subject.ddc 620.115
dc.subject.lcsh Carbon -- Absorption and adsorption en
dc.subject.lcsh Radioisotopes en
dc.subject.lcsh Graphene en
dc.subject.lcsh Nanostructured materials en
dc.title Radionuclide liquid waste treatment of 68[superscript]Ge by graphene oxide based nanomaterials en
dc.type Dissertation en
dc.description.department Physics en
dc.description.degree M. Sc. (Physics)


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