New method of uranium and plutonium extraction in reprocessing of the spent nuclear fuel
V. I. Volk, Konstantin Nikolaevich Dvoeglazov, S. Veslov, V. N. Rubisov, V. N. Alekseenko, Y. Krivitsky, S. N. Alekseenko, V. V. Bondin
Abstract
V. I. Volk, Konstantin Nikolaevich Dvoeglazov, S. Veslov, V. N. Rubisov, V. N. Alekseenko, Y. Krivitsky, S. N. Alekseenko, V. V. Bondin
Abstract
It is shown that a two-stage process of uranium and plutonium extraction during the reprocessing of spent nuclear fuel solves the problem of obtaining a high-concentrated extract without increasing the loss risk with raffinate and avoids the accumulation of plutonium in the unit. A possible further optimization of the process would be the creation of steps inside the stages.
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It is shown that a two-stage process of uranium and plutonium extraction during the reprocessing of spent nuclear fuel solves the problem of obtaining a high-concentrated extract without increasing the loss risk with raffinate and avoids the accumulation of plutonium in the unit. A possible further optimization of the process would be the creation of steps inside the stages.
Key concepts: Plutonium, Raffinate, Uranium, Spent nuclear fuel, Nuclear reprocessing, Extraction (chemistry), Plutonium-240, Enriched uranium