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http://elar.urfu.ru/handle/10995/132312
Название: | Computer modeling of electrochemical processing of waste nuclear fuel |
Авторы: | Galashev, A. Y. Manzhurov, A. I. Zaikov, Y. P. |
Дата публикации: | 2021 |
Издатель: | John Wiley and Sons Ltd |
Библиографическое описание: | 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 |
Аннотация: | 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 |
Ключевые слова: | 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 |
Условия доступа: | info:eu-repo/semantics/openAccess |
Конференция/семинар: | 11 November 2022 through 13 November 2022 |
Дата конференции/семинара: | 2022 IEEE International Multi-Conference on Engineering, Computer and Information Sciences, SIBIRCON 2022 |
Идентификатор SCOPUS: | 85084228705 |
Идентификатор WOS: | 000529814500001 |
Идентификатор PURE: | d01e8af9-2b4d-44ce-a988-73cb4618ff5d 22104123 |
ISSN: | 0363-907X |
ISBN: | 978-166546480-2 |
DOI: | 10.1002/er.5462 |
Сведения о поддержке: | 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). |
Располагается в коллекциях: | Научные публикации ученых УрФУ, проиндексированные в SCOPUS и WoS CC |
Файлы этого ресурса:
Файл | Описание | Размер | Формат | |
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2-s2.0-85084228705.pdf | 2,85 MB | Adobe PDF | Просмотреть/Открыть |
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