Criticality analysis of pyrochemical reprocessing apparatuses for mixed uranium-plutonium nitride spent nuclear fuel using the MCU-FR and MCNP program codes
Электронный научный архив УРФУ
Информация об архиве | Просмотр оригинала| Поле | Значение | |
| Заглавие |
Criticality analysis of pyrochemical reprocessing apparatuses for mixed uranium-plutonium nitride spent nuclear fuel using the MCU-FR and MCNP program codes
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| Автор |
Kizub, P. A.
Blokhin, A. I. Blokhin, P. A. Mitenkova, E. F. Mosunova, N. A. Kovrov, V. A. Shishkin, A. V. Zaikov, Y. P. Rakhmanova, O. R. |
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| Тематика |
CRITICALITY ANALYSIS
EFFECTIVE NEUTRON MULTIPLICATION FACTOR MCNP MCU PYROCHEMICAL APPARATUSES PYROCHEMICAL REPROCESSING SPENT NUCLEAR FUEL |
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| Описание |
A preliminary criticality analysis for novel pyrochemical apparatuses for the reprocessing of mixed uranium-plutonium nitride spent nuclear fuel from the BREST-OD-300 reactor was performed. High-temperature processing apparatuses, “metallization” electrolyzer, refinery remelting apparatus, refining electrolyzer, and “soft” chlorination apparatus are considered in this work. Computational models of apparatuses for two neutron radiation transport codes (MCU-FR and MCNP) were developed and calculations for criticality were completed using the Monte Carlo method. The criticality analysis was performed for different loads of fissile material into the apparatuses including overloading conditions. Various emergency situations were considered, in particular, those associated with water ingress into the chamber of the refinery remelting apparatus. It was revealed that for all the considered computational models nuclear safety rules are satisfied. © 2022 Korean Nuclear Society
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| Дата |
2024-04-05T16:20:58Z
2024-04-05T16:20:58Z 2023 |
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| Тип |
Article
Journal article (info:eu-repo/semantics/article) |info:eu-repo/semantics/publishedVersion |
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| Идентификатор |
Kizub, PA, Blokhin, AI, Blokhin, PA, Mitenkova, EF, Mosunova, NA, Kovrov, VA, Shishkin, AV, Zaikov, YP & Rakhmanova, OR 2023, 'Criticality analysis of pyrochemical reprocessing apparatuses for mixed uranium-plutonium nitride spent nuclear fuel using the MCU-FR and MCNP program codes', Nuclear Engineering and Technology, Том. 55, № 3, стр. 1097-1104. https://doi.org/10.1016/j.net.2022.11.020
Kizub, P. A., Blokhin, A. I., Blokhin, P. A., Mitenkova, E. F., Mosunova, N. A., Kovrov, V. A., Shishkin, A. V., Zaikov, Y. P., & Rakhmanova, O. R. (2023). Criticality analysis of pyrochemical reprocessing apparatuses for mixed uranium-plutonium nitride spent nuclear fuel using the MCU-FR and MCNP program codes. Nuclear Engineering and Technology, 55(3), 1097-1104. https://doi.org/10.1016/j.net.2022.11.020 1738-5733 Final All Open Access, Gold https://www.scopus.com/inward/record.uri?eid=2-s2.0-85144989584&doi=10.1016%2fj.net.2022.11.020&partnerID=40&md5=0144683562cb12216a8632d6567233f5 https://doi.org/10.1016/j.net.2022.11.020 http://elar.urfu.ru/handle/10995/130448 10.1016/j.net.2022.11.020 85144989584 000961804800001 |
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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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