Experimental and theoretical justification of passive heat removal system for irradiated fuel assemblies of the nuclear research reactor in a spent fuel pool
Электронный научный архив УРФУ
Информация об архиве | Просмотр оригинала| Поле | Значение | |
| Заглавие |
Experimental and theoretical justification of passive heat removal system for irradiated fuel assemblies of the nuclear research reactor in a spent fuel pool
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| Автор |
Van, Thuong, T.
Tashlykov, O. L. Glukhov, S. M. Shumkov, D. E. Volchikhina, Y. V. |
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| Тематика |
IRRADIATED FUEL ASSEMBLIES
NUCLEAR RESEARCH REACTOR PASSIVE HEAT REMOVAL SYSTEM RESIDUAL HEAT POWER SPENT FUEL POOL |
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| Описание |
The safety of nuclear installations is largely determined by the tightness of fuel elements cladding. As the Fukushima nuclear accident showed, the main task in case of loss of power supply is to ensure reliable removal of residual heat release from spent fuel pool (SFP) with irradiated fuel assemblies (IFAs). The paper presents the results of calculated-experimental studies and thermal-hydraulic modeling of temperature storage modes of IFAs in SFP. Experimental studies of SFP's temperature regime and calculated evaluation of residual heat removal due to the thermal conductivity of building structures surrounding the SFP were performed. To ensure the safe operation of research reactors, it's necessary to know the IFA's residual heat power (RHP) in the reactor and SFP, which is determined depending on the operating time of fuel assemblies (FAs) and the IFAs calculated holding time. The FAs operating time depends on the reactor energy output. The IFAs calculated holding time is determined by the fuel burnup, U-235 mass in the fuel, and reactor utilization factor. The IFAs fuel burnup was calculated using the MCU-PTR program. Also presented are the RHP's calculation results using some of the empirical dependencies. The concept of a passive heat removal system (PHRS) based on thermosyphon's operating principle was proposed. © 2023 Korean Nuclear Society
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| Дата |
2024-04-05T16:21:59Z
2024-04-05T16:21:59Z 2023 |
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| Тип |
Article
Journal article (info:eu-repo/semantics/article) |info:eu-repo/semantics/publishedVersion |
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| Идентификатор |
Thuong, TV, Tashlykov, OL, Glukhov, SM, Shumkov, DE & Volchikhina, YV 2023, 'Experimental and theoretical justification of passive heat removal system for irradiated fuel assemblies of the nuclear research reactor in a spent fuel pool', Nuclear Engineering and Technology, Том. 55, № 6, стр. 2088-2095. https://doi.org/10.1016/j.net.2023.02.028
Thuong, T. V., Tashlykov, O. L., Glukhov, S. M., Shumkov, D. E., & Volchikhina, Y. V. (2023). Experimental and theoretical justification of passive heat removal system for irradiated fuel assemblies of the nuclear research reactor in a spent fuel pool. Nuclear Engineering and Technology, 55(6), 2088-2095. https://doi.org/10.1016/j.net.2023.02.028 1738-5733 Final All Open Access, Gold https://www.scopus.com/inward/record.uri?eid=2-s2.0-85159089205&doi=10.1016%2fj.net.2023.02.028&partnerID=40&md5=563463933f0309f0b078a2d649bbfc66 https://doi.org/10.1016/j.net.2023.02.028 http://elar.urfu.ru/handle/10995/130473 10.1016/j.net.2023.02.028 85159089205 001003072400001 |
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| Язык |
en
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| Права |
Open access (info:eu-repo/semantics/openAccess)
cc-by-nc-nd https://creativecommons.org/licenses/by-nc-nd/4.0/ |
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| Формат |
application/pdf
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| Издатель |
Korean Nuclear Society
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| Источник |
Nuclear Engineering and Technology
Nuclear Engineering and Technology |
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