Please use this identifier to cite or link to this item: http://elar.urfu.ru/handle/10995/132417
Title: Processing of fast neutron reactor fuel by electrorefining: Thematic overview
Authors: Galashev, A. Y.
Issue Date: 2021
Publisher: John Wiley and Sons Ltd
Citation: Galashev, AY 2021, 'Processing of fast neutron reactor fuel by electrorefining: Thematic overview', International Journal of Energy Research, Том. 45, № 8, стр. 11459-11478. https://doi.org/10.1002/er.6267
Galashev, A. Y. (2021). Processing of fast neutron reactor fuel by electrorefining: Thematic overview. International Journal of Energy Research, 45(8), 11459-11478. https://doi.org/10.1002/er.6267
Abstract: This work provides basic knowledge on the spent fuel management on the basis of the published literature data on electrorefining. This review examines three main areas of work devoted to electrorefining. These are electrodeposition and electrodissolution using solid and liquid electrodes, as well as mass transfer in phases present during electrorefining. As part of this research, the composition of the irradiated metallic fuel was estimated. Due to the great potential difference between solid cathodes, it is possible to separate actinides from lanthanides. The co-deposition of metallic Pu and U in the eutectic LiCl-KCl melt containing UCl3 and PuCl3 indicates stable co-precipitation of U and Pu at U3+ concentration less than ~0.2 wt. Periodically performed electrical transport of ions to liquid (Cd) and solid cathodes in the galvanic mode made it possible to deposit preferentially U on the solid cathode, and Pu and Am on the liquid cathode. Oxidation of these metals caused fluctuations in the anode potential. The electrode processing after electrorefining is investigated. This process consists of oxidizing the actinides remaining in the liquid electrode by adding CdCl2 and removing the associated chloride by high-temperature distillation. During the electrorefining of irradiated metallic fuel, the fission products accumulate in the molten salt. Reduction of uranium on a solid cathode from a spent molten salt using a liquid Cd-Li anode is considered. A model that describes electrorefining with a liquid metal anode, solid cathode, and molten LiCl-KCl salts, is presented. The formation of plutonium at the surface of a solid cathode is analyzed. In a one-dimensional model of an electrorefiner, it is shown that the concentration of Pu at the cathode cannot be predicted from the Cm concentration in the melt. © 2020 John Wiley & Sons Ltd
Keywords: ELECTROLYZER
EXPERIMENT
MODEL
PLUTONIUM
SPENT NUCLEAR FUEL
URANIUM
ACTINIDES
ANODES
BINARY ALLOYS
CADMIUM CHLORIDE
CATHODES
DEPOSITION
DISTILLATION
ELECTROMETALLURGY
FISSION PRODUCTS
FUSED SALTS
HIGH TEMPERATURE OPERATIONS
LIQUIDS
LITHIUM COMPOUNDS
MASS TRANSFER
METAL FUELS
NUCLEAR FUELS
POTASSIUM COMPOUNDS
ELECTRICAL TRANSPORT
ELECTRODE PROCESSING
FAST NEUTRON REACTORS
HIGH TEMPERATURE DISTILLATION
LIQUID METAL ANODES
ONE-DIMENSIONAL MODEL
POTENTIAL DIFFERENCE
SPENT FUEL MANAGEMENT
CHLORINE COMPOUNDS
URI: http://elar.urfu.ru/handle/10995/132417
Access: info:eu-repo/semantics/openAccess
cc-by
RSCI ID: 47090286
SCOPUS ID: 85097485108
WOS ID: 000597577100001
PURE ID: 638e0117-e839-48ac-87ad-fde6d3ed227f
22104062
ISSN: 0363-907X
DOI: 10.1002/er.6267
metadata.dc.description.sponsorship: State Atomic Energy Corporation ROSATOM, ROSATOM, (17706413348200000540)
This work was supported by the State Atomic Energy Corporation Rosatom (State Contract No. Н.4о.241.19.20.1048 dated April 17, 2020, identifier 17706413348200000540).
Appears in Collections:Научные публикации ученых УрФУ, проиндексированные в SCOPUS и WoS CC

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