Issues concerning fuel cycle closure are discussed. It is shown that from the standpoint of full utilization of reprocessed nuclear materials the main problems are associated with repeated recycling of uranium, the reason being that limitations are imposed on the content of the isotope 232U in fresh fuel produced from reprocessed materials. The losses of the isotope 235U on repeated recycling of reprocessed uranium in the form of fuel from uranium regenerate and mixtures of processed uranium and plutonium oxides are evaluated. For a light-water reactor, a method of fuel cycle closure making it possible to reduce the 235U losses almost to zero on purification of reprocessed uranium from 232U is shown.
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References
V. Yu. Blandinskii, V. A. Nevinitsa, A. Yu. Smirnov, et al., “A coordinated approach to modeling radiation burnup and molecular selective processes in a separation cascade for assessment of the prospects for separate recycling of reprocessed uranium fuel in a light water reactor,” Vopr. At. Nauki Tekhn. Ser. Yad.-Reakt. Konst., No. 1, 68–75 (2018).
E. A. Bobrov, P. A. Fomichenko, A. V. Grol, et al., “Evaluation of technical and economic indicators of REMIX fuel application in the LWR fuel cycle,” in: Proc. Int. Conf. on Management of Spent Fuel Nuclear Power Reactors: Learning from the Past, Enabling for the Future, Vienna, Austria, June 24–28, 2019.
A. A. Orlov, A. V. Kravchenko, E. S. Titov, and A. Ya. Lebedev, “Review of promising methods of uranium recycling in the nuclear fuel cycle,” Izv. Vyssh. Uchebn. Zaved. Fizika, 58, No. 2/2, 35–40 (2015).
V. N. Prusakov, A. A. Sazykin, L. Yu. Sosnin, et al., “Correction of the isotopic composition of regenerated uranium by 232U by the centrifugal method with the introduction of a carrier gas,” At. Energ., 105, No. 3, 150–156 (2008).
A. Yu. Smirnov, G. A. Sulaberidze, V. A. Nevinitsa, et al., “Cascade schemes for studying changes in the isotopic composition of repeatedly regenerated uranium,” Yad. Fiz. Inzhinir., 3, No. 5, 396–403 (2012).
V. A. Palkin, “Purification of regenerated uranium in cascades with 235U enrichment to 5%,” At. Energ., 115, No. 1, 28–33 (2013).
V. A. Palkin and E. V. Maslyukov, “Purification of regenerated uranium in an additional product of an R-cascade and its enrichment in an ordinary cascade,” Teor. Osn. Khim. Tekhnol., 50, No. 5, 711–717 (2016).
A. Yu. Smirnov, V. A. Nevinitsa, P. A. Fomichenko, et al., “Enrichment of regenerated uranium in a double-cascade of gas centrifuges with its full return to fuel breeding,” Vest. NIYaU MIFI, 7, No. 6, 449–457 (2018).
A. V. Kuryndin, A. M. Kirkin, I. V. Gusakov-Stanyukovich, et al., “Implemented and promising approaches to the return of spent nuclear fuel processing products to the supplier state,” Vopr. At. Nauki Tekhn., Ser. Materialoved. Novye Mater., No. 2 (98), 48–59 (2019).
A. Yu. Smirnov, A. M. Pavlovichev, A. I. Shcherenko, et al., “Fuel cycle of a light water reactor with full use of regenerated uranium,” Vest. NIYaU MIFI, 8, No. 6, 498–506 (2019).
I. A. Belov, A. V. Grol, V. A. Nevinitsa, et al., “Radiolysis of 232,234U-enriched regenerated uranium hexafluoride at the stage of temporary storage at a separation facility,” At. Energ., 126, No. 5, 268–272 (2019).
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Translated from Atomnaya Énergiya, Vol. 128, No. 4, pp. 208–216, April, 2020.
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Smirnov, A.Y., Gusev, V.E., Sulaberidze, G.A. et al. Physical and Technical Problems of Reprocessed Uranium Enrichment with Repeated Recycling in Light-Water Reactors and Ways to Solve Them. At Energy 128, 223–231 (2020). https://doi.org/10.1007/s10512-020-00681-9
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DOI: https://doi.org/10.1007/s10512-020-00681-9