Application of Quasi-Ideal Cascades and the Dilution Operation for Purification of Regenerated Uranium Hexafluoride
- 40 Downloads
Purification of regenerated uranium in a two-cascade scheme with a dilution operation is proposed. The first cascade has one feed flow, two product flows, and one waste flow. It is calculated as an ideal cascade with adjustment of the obtained 235U concentration to a prescribed content in the exterior flows. Lowenrichment uranium hexafluoride, intended for the fabrication of nuclear fuel, is obtained in the primary product. A product with the same 235U concentration as in the feed flow and reduced 232,234U is produced in the intermediate product of the cascade. This product is enriched with 235U in the second cascade, which is an R-cascade with the key components 235,236UF6. The enriched uranium hexafluoride obtained in the product is diluted to 235U concentration below 5%. The 236U content decreases as a result.
Unable to display preview. Download preview PDF.
- 1.B. V. Nikipelov and V. B. Nikipelov, “Fate of uranium regenerate,” Byull. At. Energii, No. 9, 34–43 (2002).Google Scholar
- 2.A. A. Vlasov, V. V. Vodolazkikh, V. I. Mazin, et al., Patent No. 2236053 RF, “Method of isotope recovery of reprocessed uranium,” subm. Sept. 10, 2004, Byull. Izobret. Polezn. Modeli, No. 25, 562 (2004).Google Scholar
- 3.G. A. Sulaberidze, V. D. Borisevich, and Tsyuansin Xie, “Quasi-ideal cascades with an additional stream for separation of multicomponent isotope mixtures,” Teor. Osn. Khim. Tekhnol., 40, No. 1, 7–16 (2006).Google Scholar
- 5.V. V. Vodolazkikh, N. P. Glukhov, V. A. Palkin, et al., Patent No. 2377674 RF, “A method of reprocessing contaminated raw uranium,” subm. Dec. 27, 2009, Byull. Izobret. Polezn. Modeli, No. 36, 1207–1208 (2009).Google Scholar
- 6.V. A. Palkin, “The separation of uranium isotopes in a cascade with an intermediate product,” Persp. Mater., 8, 11–14 (2010).Google Scholar
- 7.A. A. Vlasov, V. V. Vodolazkikh, V. G. Gridnev, et al., Patent No. 2242812 RF, “Method isotope recovery of regenerated uranium,” subm. July 20, 2004, Byull. Izobret. Polezn. Modeli, No. 35, 804–805 (2004).Google Scholar
- 8.V. V. Vodolazkikh, V. A. Kozlov, V. I. Mazin, et al., Patent No. 2282904 RF, “Method isotope recovery of reprocessed uranium,” subm. Aug. 27, 2006, Byull. Izobret. Polezn. Modeli, No. 24, 549–550 (2006).Google Scholar
- 10.G. A. Sulaberidze, V. A. Borisevich, and Tsyuansin Xie, “On separation problems in bringing reprocessed uranium into the fuel cycle,” in: 9th All-Russ. Sci. Conf. on the Physical and Chemical Processes in the Selection of Atoms and Molecules, Zvenigorod (2004), pp. 78–85.Google Scholar
- 11.A. A. Sazykin, “The thermodynamic approach to isotope separation,” in : Isotopes: Properties, Production, Applications, V. Y. Baranov (ed.), IzdAT, Moscow (2000), pp. 72–108.Google Scholar
- 14.V. A. Palkin, N. A. Sbitnev, and E. S. Frolov, “Calculation of optimal parameters of a cascade for the separation of multicomponent isotopic mixtures,” At. Energ., 92, No. 2, 130–133 (1002).Google Scholar