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Dissolution of Actinide Oxides in Carbonate Solutionsстатья
- Авторы: Chervyakov N.M., Boyarintsev A.V., Kostikova G.V., Stepanov S.I.
- Журнал: Radiochemistry
- Том: 65
- Номер: 3
- Год издания: 2023
- Издательство: Pleiades Publishing, Inc.
- Местоположение издательства: New York, USA
- Первая страница: 274
- Последняя страница: 285
- DOI: 10.1134/S1066362223030025
- Аннотация: The dissolution step of uranium and mixed oxide uranium-plutonium spent nuclear fuel is a key initialstep of a new alternative hydrometallurgical method⸺the CARBEX process. The study considers carbonate oxidizingsystems NaHCO3/Na2CO3–H2O2/2Na2CO3·3H2O2/М2S2O8, where M = Na, K, or NH4+, for dissolving actinideoxide powders. The chemical and physical factors that determine the rate of oxidative dissolution of powderedindividual oxides UO2, U3O8, PuO2 and NpO2 in carbonate media were found. The results obtained are importantfor the development of the oxidative and sonochemical options of dissolution of highly calcined crystalline samplesof uranium, plutonium and neptunium oxides, as well of spent nuclear fuel in carbonate media.
- Добавил в систему: Костикова Галина Валерьевна