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Scrap oxidation of uranium carbide heavy ion accelerator target material

  • Materials (Organic, Inorganic, Electronic, Thin Films)
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Korean Journal of Chemical Engineering Aims and scope Submit manuscript

Abstract

The use of uranium carbide for extracting uranium, a rare and valuable material, has garnered significant research interest. The long-term storage of uranium scrap is challenging due to the risk of ignition and contents of nuclear materials. Thus, scrap treatment is required for safe storage and volume reduction. We investigated the oxidation behavior of different types of multi-walled carbon nanotube-containing uranium scraps (green and sintered) in different forms (fragmented and powdered) using thermogravimetric/differential thermal analysis and volatilization studies. An air flow and oxidation temperature of 500 cm3/min and 900 °C, respectively, were suitable for the effective recovery of inert U3O8 for safe storage or recycling. For optimal results, scrap in powder form should be used. These findings provide insights for recycling uranium from uranium carbide scrap, with potential applications in research and industry.

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Acknowledgements

This study was supported by the Rare Isotope Accelerator Development Project through the Ministry of Science and ICT, National Research Foundation of Korea, and Institute for Basic Science (Study Number: NRF-2019-M7A1A1-032994).

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Authors and Affiliations

  1. Kepco Nuclear Fuel Company, Daejeon, 34057, Korea

    Bohyun Jo & Youngho Shim

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  1. Bohyun Jo
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  2. Youngho Shim
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Correspondence to Bohyun Jo.

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Jo, B., Shim, Y. Scrap oxidation of uranium carbide heavy ion accelerator target material. Korean J. Chem. Eng. 39, 2810–2816 (2022). https://doi.org/10.1007/s11814-022-1108-1

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  • DOI: https://doi.org/10.1007/s11814-022-1108-1

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