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Название: Recovery of actinides and fission products from spent nuclear fuel via electrolytic reduction: Thematic overview
Авторы: Galashev, A. Y.
Дата публикации: 2022
Издатель: John Wiley and Sons Ltd
Библиографическое описание: Galashev, AY 2022, 'Recovery of actinides and fission products from spent nuclear fuel via electrolytic reduction: Thematic overview', International Journal of Energy Research, Том. 46, № 4, стр. 3891-3905. https://doi.org/10.1002/er.7458
Galashev, A. Y. (2022). Recovery of actinides and fission products from spent nuclear fuel via electrolytic reduction: Thematic overview. International Journal of Energy Research, 46(4), 3891-3905. https://doi.org/10.1002/er.7458
Аннотация: Spent nuclear fuel (SNF) from modern light water or thermal reactors containing uranium oxide with small concentrations of plutonium and other actinide oxides is converted into metal by the electrolytic reduction. The obtained metal must be subjected to further processing (electrorefining). This review reflects the achievements in development SNF electrolytic processing, concepts of the technological operations, and a model describing the electrochemical process. The technological scheme for the electrochemical reduction of SNF and MOX fuel is considered. The complexity of a carbon anode application in the process of UO2 electrolytic reduction is reflected. The reduction processes of alkali, alkaline earth (AE), and rare earth metal oxides as well as oxide compounds of zirconium are demonstrated. The reduction of lanthanum oxide and oxy-chloride to the metallic form by adding metallic nickel to the molten salt is discussed. The solubility of Li2O in molten salts is interpreted depending on the amount of dissolved alkali and AE metal chlorides. The considered pyroprocessing technology enables a much greater release of the energy accumulated in uranium ore, and recycling all actinides allows reducing significantly the amount of nuclear waste and the time it must be isolated. © 2021 John Wiley & Sons Ltd.
Ключевые слова: ACTINIDE
FISSION PRODUCTS
PLUTONIUM
SALT MELT
SPENT NUCLEAR FUEL
URANIUM
CHLORINE COMPOUNDS
ELECTROLYTIC REDUCTION
FUSED SALTS
LIGHT WATER REACTORS
LITHIUM COMPOUNDS
METALS
MOLTEN SALT REACTOR
NUCLEAR FUEL REPROCESSING
ORES
RARE EARTHS
URANIUM DIOXIDE
ACTINIDE OXIDES
ELECTROREFINING
LIGHT WATER
MOLTEN SALT
SALT MELT
SMALL CONCENTRATION
SPENT NUCLEAR FUELS
THERMAL REACTORS
URANIA
WATER REACTORS
FISSION PRODUCTS
URI: http://elar.urfu.ru/handle/10995/132419
Условия доступа: info:eu-repo/semantics/openAccess
cc-by
Идентификатор РИНЦ: 49798526
Идентификатор SCOPUS: 85119977665
Идентификатор WOS: 000722746700001
Идентификатор PURE: ea26875b-44e9-4b0a-b8d5-b814422da9a3
29827292
ISSN: 0363-907X
DOI: 10.1002/er.7458
Сведения о поддержке: State Atomic Energy Corporation ROSATOM, ROSATOM
This work was supported by the State Atomic Energy Corporation Rosatom (Government agreement number H.4o.241.19.21.1070 dated 16 April 2021 «Development of the technology and facility for the pyrochemical reprocessing of the spent nuclear fuel of the fast neutron reactors. 2021 stage»).
Располагается в коллекциях:Научные публикации ученых УрФУ, проиндексированные в SCOPUS и WoS CC

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