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Development and demonstration of basics for plasma reprocessing of spent nuclear fuel.

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Title: Development and demonstration of basics for plasma reprocessing of spent nuclear fuel.
Authors: Antonov, N. N.1 (AUTHOR), Valinurov, M. A1 (AUTHOR), Gavrikov, A. V.1 (AUTHOR), Kuzmichev, S. D1 (AUTHOR), Melnikov, A. D.1 (AUTHOR), Oiler, A. P.1 (AUTHOR), Samoylov, I. S.1 (AUTHOR), Smirnov, V. P.1 (AUTHOR), Timirkhanov, R. A.1 (AUTHOR), Usmanov, R. A.1 (AUTHOR) usmanov.r@ihed.ras.ru, Shumova, V. V.1 (AUTHOR), Mochalov, Yu. S.2 (AUTHOR), Savchits, S. M.2 (AUTHOR), Sukhanov, L. P.2 (AUTHOR)
Source: Atomic Energy. May2025, Vol. 138 Issue 1/2, p54-60. 7p.
Subjects: Plasma materials processing, Reactor fuel reprocessing, Nuclear energy, Process control systems, Isotope separation, Uranium, Empirical research
Geographic Terms: Russia
Abstract: The paper presents the results of the research conducted by the JIHT RAS (Moscow, Russian Federation) on plasma reprocessing of spent fuel. The method is developed within the framework of the "Proryv" project direction as one of the operations in the reprocessing of spent nuclear fuel from industrial energy complexes. Experiments were carried out with substances simulating the elements moving in separating plasma. The physical viability of the selected concept for plasma mass separation is substantiated both theoretically and experimentally. The results will be used in a model of a plasma unit with a capacity of up to 0.2 kg/h for the mass separation of spent nuclear fuel. The model is planned for construction to practice technological processes and engineering solutions on various simulating compositions, including those based on depleted uranium. [ABSTRACT FROM AUTHOR]
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Database: Engineering Source
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Abstract:The paper presents the results of the research conducted by the JIHT RAS (Moscow, Russian Federation) on plasma reprocessing of spent fuel. The method is developed within the framework of the "Proryv" project direction as one of the operations in the reprocessing of spent nuclear fuel from industrial energy complexes. Experiments were carried out with substances simulating the elements moving in separating plasma. The physical viability of the selected concept for plasma mass separation is substantiated both theoretically and experimentally. The results will be used in a model of a plasma unit with a capacity of up to 0.2 kg/h for the mass separation of spent nuclear fuel. The model is planned for construction to practice technological processes and engineering solutions on various simulating compositions, including those based on depleted uranium. [ABSTRACT FROM AUTHOR]
ISSN:10634258
DOI:10.1007/s10512-025-01226-8