Please use this identifier to cite or link to this item: http://elar.urfu.ru/handle/10995/132312
Title: Computer modeling of electrochemical processing of waste nuclear fuel
Authors: Galashev, A. Y.
Manzhurov, A. I.
Zaikov, Y. P.
Issue Date: 2021
Publisher: John Wiley and Sons Ltd
Citation: Galashev, AY, Manzhurov, AI & Zaikov, YP 2021, 'Computer modeling of electrochemical processing of waste nuclear fuel', International Journal of Energy Research, Том. 45, № 8, стр. 11664-11676. https://doi.org/10.1002/er.5462
Galashev, A. Y., Manzhurov, A. I., & Zaikov, Y. P. (2021). Computer modeling of electrochemical processing of waste nuclear fuel. International Journal of Energy Research, 45(8), 11664-11676. https://doi.org/10.1002/er.5462
Abstract: The purpose of the work is to study the influence of the electrodes geometry and the mutual arrangement of functional elements in the working space of a metallization electrolyzer on the distribution of the oxygen flux density in the electrolyte, as well as on the distribution of electric and temperature fields. In a computer model, the stationary operation mode of the electrolyzer for processing spent nuclear fuel immersed into the LiCl molten salt with the addition of Li2O was studied. The calculations were performed using the ANSYS software package. We studied eight designs of the electrolyzer, which differ in the immersion depth of the anodes into the melt as well in the types anode protective covers and the cathode baskets. Verification based on the comparison of the computer modeling with experimental data indicates the adequacy of the models used. The electrolyte velocity field and the temperature field are calculated, as well as the steady-state picture of the distribution of electric current density over the working space of the electrolyzer. The efficiency of the electrochemical cell is determined. © 2020 John Wiley & Sons Ltd
Keywords: CURRENT DENSITY
ELECTROLYZER
MODEL
SPENT NUCLEAR FUEL
URANIUM DIOXIDE
ANODES
CHLORINE COMPOUNDS
ELECTROLYTES
ELECTROLYTIC CELLS
MOLTEN SALT REACTOR
NUCLEAR FUELS
VELOCITY
ANSYS SOFTWARE PACKAGE
COMPUTER MODELING
ELECTROCHEMICAL PROCESSING
FUNCTIONAL ELEMENTS
OXYGEN FLUX DENSITY
PROTECTIVE COVER
SPENT NUCLEAR FUELS
STATIONARY OPERATIONS
LITHIUM COMPOUNDS
URI: http://elar.urfu.ru/handle/10995/132312
Access: info:eu-repo/semantics/openAccess
Conference name: 11 November 2022 through 13 November 2022
Conference date: 2022 IEEE International Multi-Conference on Engineering, Computer and Information Sciences, SIBIRCON 2022
SCOPUS ID: 85084228705
WOS ID: 000529814500001
PURE ID: d01e8af9-2b4d-44ce-a988-73cb4618ff5d
22104123
ISSN: 0363-907X
ISBN: 978-166546480-2
DOI: 10.1002/er.5462
Sponsorship: State Atomic Energy Corporation ROSATOM, ROSATOM, (17706413348200000540)
Funding text 1: The present paper is partly supported by the agreement No. 18, 04.06.2018 under support of the State Atomic Energy Corporation ROSATOM. The work was carried out as a part of R&D “Development of technology and equipment for the pyrochemical processing of SNF of fast neutron reactors” in the “Breakthrough” project area.
Funding text 2: The present paper is financially supported by the State Atomic Energy Corporation Rosatom (State contract No H.4o.241.19.20.1048 dated 17.04.2020, identifier 17706413348200000540).
Appears in Collections:Научные публикации ученых УрФУ, проиндексированные в SCOPUS и WoS CC

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