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Closed nuclear fuel cycle of thermal and fast reactors with fuel self-sufficiency

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dc.contributor.authorShmelev, A. N.
dc.contributor.authorApse, V. A.
dc.contributor.authorKulikov, E. G.
dc.contributor.authorKulikov, G. G.
dc.contributor.authorGlebov, V. B.
dc.contributor.authorГлебов, Василий Борисович
dc.contributor.authorКуликов, Евгений Геннадьевич
dc.contributor.authorКуликов, Геннадий Генрихович
dc.contributor.authorАпсэ, Владимир Александрович
dc.date.accessioned2025-11-24T11:59:45Z
dc.date.available2025-11-24T11:59:45Z
dc.date.issued2025
dc.description.abstractThe paper presents the results obtained in numerical evaluations of a possibility to reach self-sufficiency of fissile materials in the joint system of fast and thermal reactors. These studies considered the joint system consisting of thermal light-water reactors of VVER-type and fast lead-cooled reactors of BREST-type, which are operated within the frames of the closed (Th-U-Pu) fuel cycle. It was assumed that fast reactors (FR) of BREST-type used the mixed thorium-plutonium nitride fuel, while thermal reactors (TR) of VVER-type used the mixed oxide fuel of natural uranium and 233U. Uranium isotope 233U was produced in the Th-fraction of FR fuel for further introduction into the fresh composition of TR fuel, while plutonium was produced in the natural uranium fraction of TR fuel for further introduction into the fresh composition of FR fuel. The numerical studies resulted in the determination of the conditions necessary to provide fuel self-sufficiency in the joint TR-FR system. The following key findings of the research may be noted: – It is demonstrated the possibility to create the joint TR-FR system with inherent fuel self-sufficiency; – Involvement of thorium and 233U in the closed NFC of the joint TR-FR system can arrange an optimal regime for production and consumption of main FM; – Purposeful change of thermal power and introduction of natural uranium in the fuel composition of BREST-type FR made it possible to reach fuel self-sufficiency of the joint TR-FR system; – Application of radiogenic lead instead of natural lead allowed us to reduce necessary values of thermal power and content of natural uranium nitride in the fuel of BREST-type FR.
dc.description.urihttps://nucet.pensoft.net/article/127108/
dc.identifier.citationShmelev AN, Apse VA, Kulikov EG, Kulikov GG, Glebov VB (2025) Closed nuclear fuel cycle of thermal and fast reactors with fuel self-sufficiency. Nuclear Energy and Technology 11(1): 33–41. https://doi.org/10.3897/nucet.11.127108
dc.identifier.doi10.3897/nucet.11.127108
dc.identifier.urihttps://openrepository.mephi.ru/handle/123456789/39822
dc.publisherНИЯУ МИФИ
dc.subjectThermal VVER-type reactors
dc.subjectFuel self-sufficiency
dc.subjectFast BREST-type reactors
dc.titleClosed nuclear fuel cycle of thermal and fast reactors with fuel self-sufficiency
dc.title.alternativeНАУЧНЫЕ СТАТЬИ
dc.typeArticleru
dspace.entity.typePublication
journal.titleNuclear Energy and Technology (NUCET)
journalvolume.identifier.nameNuclear Energy and Technology (NUCET)
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