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- In relation to this article, we declare that there is no conflict of interest.
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Received January 10, 2022
Accepted March 14, 2022
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This is an Open-Access article distributed under the terms of the Creative Commons Attribution Non-Commercial License (http://creativecommons.org/licenses/bync/3.0) which permits
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Scrap oxidation of uranium carbide heavy ion accelerator target material
Kepco Nuclear Fuel Company, Daejeon 34057, Korea
bhcho@knfc.co.kr
Korean Journal of Chemical Engineering, October 2022, 39(10), 2810-2816(7), 10.1007/s11814-022-1108-1
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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 ℃, 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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Biasetto L, Zanonato P, Carturan S, Di Bernardo P, Colombo P, Andrighetto A, Prete G, J. Nucl. Mater., 404, 68 (2010)
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Monetti A, Bark RA, Andrighetto A, Beukes P, Conradie JL, Corradetti S, Fourie D, Lussi C, Manzolaro M, Meneghetti G, Eur. Phys. J., Appl. Phys, 52, 168 (2016)
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