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Sorption of long-lived radionuclides from geologic repository underground waters by uranium oxidesстатья
Информация о цитировании статьи получена из
Scopus
Дата последнего поиска статьи во внешних источниках: 28 мая 2015 г.
- Авторы: Kazakovskaya T.V., Zakharova E.V., Shapovalov V.I., Haire M.J., Kalmykov S.N.
- Журнал: Proceedings - 10th International Conference on Environmental Remediation and Radioactive Waste Management, ICEM’05
- Том: 2005
- Год издания: 2005
- Первая страница: 1756
- Последняя страница: 1761
- Аннотация: Uranium dioxide (UO2) from unburned nuclear fuel is present in large quantities in spent nuclear fuel geologic repositories. Furthermore, depleted uranium dioxide (DUO2) can be used as a component of the geologic repository waste package as an absorbent for migrating radionuclides.. A potentially important use of DU oxides is to provide an additional engineered chemical barrier in the Yucca Mountain repository. If the DU oxides can be shown to substantially inhibit transport of important actinide elements and fission products, especially 237Np and 99Tc, out of the repository, then that would be a significant contribution to the repository safety. Interaction of cask material, SNF and depleted uranium dioxide with ground waters is the main natural factor, defining failure of cask and migration of radioactive products of SNF. This work is a part of joint Russian - American Program on Beneficial Use of Depleted Uranium. It is funded by the International Scientific Technical Center (the ISTC Project #2694). The U.S. Yucca Mountian geological repository was chosen as being representative of SNF repositories, in general. The paper describes DUO2 transformations in contact with various aqueous media (deionized water, J-13 solution - simulated Yucca Mountain ground water etc.) and sorption of long-lived radionuclides (237Np and 99Tc) from ground waters by depleted uranium dioxide. The samples of depleted uranium dioxide differed in the temperature of DUF6 pretreatment in the reducing media (600°C, 700°C, and 800°C respectively). The investigation was performed in static conditions under various pH. Samples were characterized by XRD, XPS, potentiometric titration, BET analysis, TEM and SEM. Increase of the pretreatment temperature results in formation of less oxidized DU compounds. The solubility of DUO 2 samples in J-13 solution is considerably higher than in deionized water. When pretreatment temperature decreases, the solubility of DUO 2 samples raises regardless of media. Neptunium is sorbed from aqueous solutions onto all samples. Copyright © 2005 by ASME.
- Добавил в систему: Калмыков Степан Николаевич