Fabrication and Characterization of (U,Pu)O2 Ceramic Fuel Pellets from Powders after Thermochemical Denitration of Nitric Acid Solutions
Thermochemical denitration of nitric acid solutions of U and Pu to obtain mixed uranium–plutonium formates was performed. It was followed by the reduction of the mixture in Ar–H2 (5 vol %) to obtain a powder of mixed U–Pu dioxide. The products obtained were studied and characterized by X-ray diffraction, X-ray fluorescence analysis, and Raman spectroscopy. The analysis of the powder revealed the formation of a (U,Pu)O2 solid solution containing 5 wt % Pu and of UO2. After the powder treatment by vortex mixing, high-density pellets of homogeneous structure were fabricated.
Authors
- V. A. Orlova
- M. V. Gorbachev (ORCID: https://orcid.org/0000-0002-9747-3554)
- R. V. Ismailov
- R. A. Serebryanskikh
- A. S. Aloy
- А. В. Давыдов
- K. Yu. Vergazov
Institutions
- V. G. Khlopin Radium Institute (RU)
- "VNIINM" named after AA Bochvar (RU)
Publication Details
- Journal
- Radiochemistry
- Published
- 2024-12-01
- DOI
- https://doi.org/10.1134/s106636222406002x
- Citations
- 3
- Primary Topic
- Radioactive element chemistry and processing
- Type
- article
- Field-Weighted Citation Impact
- 0.48