Abstract
Fabrication of ceramic UO2 fuel pellets using microwave radiation was studied. The UO2 powder was prepared by microwave denitration of a nitric acid solution containing 400 g L–1 uranium. The tapped density (2.39 g cm–3) and total specific surface area (2.70 m2 g–1) of the powder obtained met the requirements to the powder for nuclear fuel fabrication (TU (Technical Specification) 95 414–2005: Uranium Dioxide Powder of Ceramic Grade with the Uranium-235 Isotope Content Lower than 5.0%). Pellets were pressed from the UO2 powder under varied conditions including pressure, its application mode, pressing time, and presence of binder. The pressed pellets were sintered at 1650°С for 2 h in an Ar + 10 vol % H2 atmosphere under the action of microwave radiation. The density of the samples obtained, 10.40 ± 0.02 g cm–3, meets the requirements to ceramic fuel pellets used in thermal reactors.
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TU (Technical Specifi cation) 95 414–2005: Uranium Dioxide Powder of Ceramic Grade with the Uranium-235 Isotope Content Lower than 5.0%.
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The study was performed within the framework of the government assignment for the Vernadsky Institute of Geochemistry and Analytical Chemistry, Russian Academy of Sciences (theme 0137-2019-0022).
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Translated from Zhurnal Prikladnoi Khimii, No. 3, pp. 332–337, January, 2021 https://doi.org/10.31857/S0044461821030075
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Pilyushenko, K.S., Kulyako, Y.M., Trofimov, T.I. et al. Use of Microwave Radiation for Denitration of Uranyl Nitrate Solution and Subsequent Sintering of Uranium Dioxide Fuel Pellets. Russ J Appl Chem 94, 317–322 (2021). https://doi.org/10.1134/S1070427221030071
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DOI: https://doi.org/10.1134/S1070427221030071