Fabrication and Characterization of (U,Pu)O2 Ceramic Fuel Pellets from Powders after Thermochemical Denitration of Nitric Acid Solutions

IF 0.9 Q4 CHEMISTRY, INORGANIC & NUCLEAR

Radiochemistry Pub Date : 2025-02-17 DOI:10.1134/S106636222406002X

A. S. Aloy, K. Yu. Vergazov, M. V. Gorbachev, A. V. Davydov, R. V. Ismailov, V. A. Orlova, R. A. Serebryanskikh

引用次数: 0

Abstract

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.

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来源期刊

Radiochemistry CHEMISTRY, INORGANIC & NUCLEAR-

CiteScore

1.30

自引率

33.30%

发文量

期刊介绍： Radiochemistry is a journal that covers the theoretical and applied aspects of radiochemistry, including basic nuclear physical properties of radionuclides; chemistry of radioactive elements and their compounds; the occurrence and behavior of natural and artificial radionuclides in the environment; nuclear fuel cycle; radiochemical analysis methods and devices; production and isolation of radionuclides, synthesis of labeled compounds, new applications of radioactive tracers; radiochemical aspects of nuclear medicine; radiation chemistry and after-effects of nuclear transformations.