Abstract
The presence of traces of water dissolved in a sodium molybdate melt and the interaction of this water with a metal surface (NP-2 nickel) in contact with the melt are confirmed. It is shown experimentally that U3O8 can be reduced to UO2 in sodium molybdate melt by the hydrogen that is released during such an interaction. A technological process of reprocessing spent oxide nuclear fuel using the phenomenon studied is described.
This is a preview of subscription content, log in via an institution to check access.
Similar content being viewed by others
References
O. A. Ustinov, “Physicochemical validation of the reprocessing of spent uranium-plutonium oxide fuel by recrystallization of molybdate melts,” At. Énerg., 82, No. 2, 100–104 (1997).
O. A. Ustinov, “Reprocessing of mixed U-Pu fuel by recrystallization in molten molybdates,” in: Proceedings of an International Symposium on MOX-Fuel Cycle Technologies for Medium and Long Term Deployment, OECD/NEA, France (2000), pp. 520–522.
O. A. Ustinov, L. P. Sukhanov, and S. A. Yakunin, “Reprocessing of spent oxide nuclear fuel by recrystallization in molybdate melts,” At. Énerg., 101, No. 4, 316–318 (2006).
L. E. Ivanovskii and V. N. Nekrasov, Gases and Ion Melts, Nauka, Moscow (1979).
V. K. Markov, Uranium and Methods of Analysis for Uranium, Atomizdat, Moscow (1964).
Author information
Authors and Affiliations
Additional information
__________
Translated from Atomnaya Énergiya, Vol. 102, No. 5, pp. 290–292, May, 2007.
Rights and permissions
About this article
Cite this article
Ustinov, O.A., Sukhanov, L.P. & Pogorelko, O.N. Reduction recrystallization of uranium oxides in molybdate melts. At Energy 102, 361–363 (2007). https://doi.org/10.1007/s10512-007-0056-5
Received:
Issue Date:
DOI: https://doi.org/10.1007/s10512-007-0056-5