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

Дата
2025
Journal Title
Nuclear Energy and Technology (NUCET)
Journal ISSN
Volume Title
Nuclear Energy and Technology (NUCET)
Издатель
НИЯУ МИФИ
Организационные подразделения
Организационная единица
Институт ядерной физики и технологий
Цель ИЯФиТ и стратегия развития - создание и развитие научно-образовательного центра мирового уровня в области ядерной физики и технологий, радиационного материаловедения, физики элементарных частиц, астрофизики и космофизики.
Выпуск журнала
Выпуск журнала
Nuclear Energy and Technology (NUCET)
2025-11 - 1
Аннотация
The 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.
Описание
Ключевые слова
Thermal VVER-type reactors , Fuel self-sufficiency , Fast BREST-type reactors
Цитирование
Shmelev 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
Коллекции