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8783253 
Journal Article 
Use of Microwave Radiation for Denitration of Uranyl Nitrate Solution and Subsequent Sintering of Uranium Dioxide Fuel Pellets 
Pilyushenko, K; Kulyako, Y; Trofimov, T; Perevalov, S; Savel'Ev, B; Vinokurov, S; Myasoedov, B 
2021 
1 
Russian Journal of Applied Chemistry
ISSN: 1070-4272
EISSN: 1608-3296 
94 
3 
317-322 
English 
WOS:000653905200007 
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 m(2) 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 degrees C for 2 h in an Ar + 10 vol % H-2 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. 
microwave radiation; denitration; uranyl nitrate solutions; actinides; uranium dioxide; pellet sintering; nuclear fuel