nucВестник НЯЦ РКNNC RK Bulletin1729-75161729-7885Национальный ядерный центр Республики Казахстан10.52676/1729-7885-2026-2-176-184nuc-1037Research ArticleСтатьиТЕХНОЛОГИИ ОБРАЩЕНИЯ С НАТРИЕМ ПРИ ВЫВОДЕ ИЗ ЭКСПЛУАТАЦИИ РЕАКТОРА НА БЫСТРЫХ НЕЙТРОНАХ: ОБЗОРSODIUM HANDLING TECHNOLOGIES FOR FAST REACTOR DECOMMISSIONING: A REVIEWТолеубековК. О.ToleubekovK. O.

Куанышбек Оразбекович Толеубеков 

Курчатов

10 Beibyt atom st., 180010 Kurchatov

toleubekov@nnc.kzМухамедовН. Е.MukhamedovN. E.

Нуржан Еролович Мухамедов 

Курчатов

10 Beibyt atom st., 180010 Kurchatov

mukhamedov@nnc.kzСураевA. С.SurayevA. S.

Артур Сергеевич Сураев 

Курчатов

10 Beibyt atom st., 180010 Kurchatov

suraev@nnc.kzДолжиковС. А.DolzhikovS. A.

Сергей Александрович Должиков

Курчатов

10 Beibyt atom st., 180010 Kurchatov

dolzhikov@nnc.kzФилиал «Институт атомной энергии» РГП НЯЦ РККазахстанInstitute of Atomic Energy NNC RKKazakhstan20260908202602176184Copyright © Толеубеков К.О., Мухамедов Н.Е., Сураев A.С., Должиков С.А., 20262026Толеубеков К.О., Мухамедов Н.Е., Сураев A.С., Должиков С.А.Toleubekov K.O., Mukhamedov N.E., Surayev A.S., Dolzhikov S.A.Данная работа распространяется под лицензией Creative Commons Attribution 4.0.This work is licensed under a Creative Commons Attribution 4.0 License.https://journals.nnc.kz/jour/article/view/1037

Реакторы на быстрых нейтронах с натриевым теплоносителем в настоящее время демонстрируют наибольшую технологическую готовность к промышленной эксплуатации и переходу к замкнутому ядерному топливному циклу. В то же время расширение парка атомных станций с быстрыми натриевыми реакторами в перспективе неизбежно приведёт к необходимости решения задач их вывода из эксплуатации. Одной из ключевых проблем данного этапа является использование натрия в качестве теплоносителя, что обусловлено его физико-химическими свойствами. Эти физико-химические особенности существенно усложняют процессы демонтажа и дезактивации оборудования реакторных установок. В связи с этим особую ценность представляет накопленный опыт обращения с натрием при выводе из эксплуатации опытно-демонстрационных быстрых натриевых реакторов. Таким образом, в настоящей статье представлен обзор современных и перспективных технологий обращения с натрием на этапе вывода из эксплуатации реакторов на быстрых нейтронах.

Sodium fast neutron reactors currently demonstrate the highest technological readiness for industrial operation and transition to a closed nuclear fuel cycle. At the same time, the expansion of the fleet of nuclear power plants with fast sodium reactors in the future will inevitably lead to the need to solve the problems of their decommissioning. One of the key challenges of this stage is the management of sodium as a coolant, which is due to its physicochemical properties. These physical and chemical features significantly complicate the processes of dismantling and decontamination of reactor plant equipment. In this regard, the accumulated experience in management of sodium during the decommissioning of experimental demonstration fast sodium reactors is of particular value. Thus, this article provides an overview of current and promising sodium management technologies at the stage of decommissioning sodium fast neutron reactors.

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The authors declare that there are no conflicts of interest present.