High-temperature interaction of components of spent uranium nuclear fuel with alkali metal carbonates in the course of voloxidation in the Carbex process


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Interaction of UO2, U3O8, ZrO2, Nb2O5, CeO2, Ce2O3, Pr6O11, Eu2O3, Yb2O3, Tb7O12, and Re metal with lithium, sodium, and potassium carbonates in the temperature interval 300–900°С was studied using methods of thermal analysis and X-ray diffraction. The major products of the high-temperature reactions are alkali metal uranates and diuranates, and in the case of ZrO2, Nb2O5, and lanthanide oxides, oxides of metals in higher oxidation states and salts of the corresponding metal-containing acids, formed by reactions of the oxides with sodium carbonate.

Sobre autores

A. Chekmarev

Mendeleev University of Chemical Technology of Russia; Frumkin Institute of Physical Chemistry and Electrochemistry

Email: chao_step@mail.ru
Rússia, Miusskaya pl. 9, Moscow, 125047; Leninskii pr. 31, korp. 4, Moscow, 119071

M. Vazhenkov

Mendeleev University of Chemical Technology of Russia

Email: chao_step@mail.ru
Rússia, Miusskaya pl. 9, Moscow, 125047

S. Stepanov

Mendeleev University of Chemical Technology of Russia; Frumkin Institute of Physical Chemistry and Electrochemistry

Autor responsável pela correspondência
Email: chao_step@mail.ru
Rússia, Miusskaya pl. 9, Moscow, 125047; Leninskii pr. 31, korp. 4, Moscow, 119071

A. Boyarintsev

Mendeleev University of Chemical Technology of Russia

Email: chao_step@mail.ru
Rússia, Miusskaya pl. 9, Moscow, 125047

A. Tsivadze

Frumkin Institute of Physical Chemistry and Electrochemistry

Email: chao_step@mail.ru
Rússia, Leninskii pr. 31, korp. 4, Moscow, 119071

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