Recovery of actinides and fission products from spent nuclear fuel via electrolytic reduction: Thematic overview
Электронный научный архив УРФУ
Информация об архиве | Просмотр оригинала| Поле | Значение | |
| Заглавие |
Recovery of actinides and fission products from spent nuclear fuel via electrolytic reduction: Thematic overview
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| Автор |
Galashev, A. Y.
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| Тематика |
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 |
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| Описание |
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.
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»). |
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| Дата |
2024-04-22T15:53:18Z
2024-04-22T15:53:18Z 2022 |
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| Тип |
Review
Review (info:eu-repo/semantics/review) Published version (info:eu-repo/semantics/publishedVersion) |
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| Идентификатор |
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 0363-907X Final All Open Access; Bronze Open Access https://doi.org/10.1002/er.7458 https://doi.org/10.1002/er.7458 http://elar.urfu.ru/handle/10995/132419 49798526 10.1002/er.7458 85119977665 722746700001 |
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| Язык |
en
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| Права |
Open access (info:eu-repo/semantics/openAccess)
cc-by |
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| Формат |
application/pdf
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| Издатель |
John Wiley and Sons Ltd
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| Источник |
International Journal of Energy Research
International Journal of Energy Research |
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