nucВестник НЯЦ РКNNC RK Bulletin1729-75161729-7885Национальный ядерный центр Республики Казахстан10.52676/1729-7885-2025-2-57-63nuc-810Research ArticleСтатьиПРОЦЕСС ФРАГМЕНТАЦИИ МОДЕЛЬНОГО КОРИУМА ПРИ ВЗАИМОДЕЙСТВИИ С ТЕПЛОНОСИТЕЛЕМTHE PROCESS OF FRAGMENTATION OF MODEL CORIUM DURING INTERACTION WITH THE COOLANTБаклановВ. В.BaklanovV. V.

Курчатов

Kurchatov

baklanov@nnc.kzhttps://orcid.org/0000-0002-4054-7831БаклановаЮ. Ю.BaklanovaYu. Yu.

Курчатов

Kurchatov

basalai@nnc.kzКукушкинИ. М.KukushkinI. M.

Курчатов

Kurchatov

kukushkin@nnc.kzБукинаО. С.BukinaO. S.

Курчатов

Kurchatov

bukina@nnc.kzАкаевА. С.AkayevA. S.

Курчатов

Kurchatov

akaev@nnc.kzФилиал «Институт атомной энергии» РГП НЯЦ РККазахстанBranch “Institute of Atomic Energy” RSE NNC RKKazakhstan202514072025025763Copyright © Бакланов В.В., Бакланова Ю.Ю., Кукушкин И.М., Букина О.С., Акаев А.С., 20252025Бакланов В.В., Бакланова Ю.Ю., Кукушкин И.М., Букина О.С., Акаев А.С.Baklanov V.V., Baklanova Y.Y., Kukushkin I.M., Bukina O.S., Akayev A.S.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/810

В настоящей работе представлены результаты исследования гранулометрических параметров, элементного и фазового составов затвердевшего модельного расплава активной зоны ядерного реактора (кориума), полученного во внереакторных условиях. Внереакторные эксперименты проводятся на стенде «EAGLE» ИАЭ НЯЦ РК, который позволяет получить расплав шихты из компонентов активной зоны и реализовать его взаимодействие с теплоносителем. Для получения модельного кориума реактора на быстрых нейтронах был использована оксид алюминия (Al2O3), в качестве теплоносителя – натрий.

Результаты исследований выявили присутствие в фазовом составе затвердевшего имитатора трех модификаций окиси алюминия Al2O3. Основной является α-модификация (корунд), которая также является базовым компонентом исходной шихты. Появление и закономерное распределение других кристаллических модификаций окиси алюминия определенно является признаком, связанным с особенностями протекания процессов, возникающих при взаимодействии модельного кориума с теплоносителем. Подобные особенности могут оказаться характерными и распространяться на собственно расплав активной зоны реактора, но могут оказаться и специфичными для применяемого имитатора.

This paper presents the results of a study of the granulometric parameters, elemental and phase compositions of a solidified model melt of a nuclear reactor core (corium) obtained in out-of-pile conditions. The out-of-pile experiments are conducted in the EAGLE test-bench of the IAE NNC RK, which allows obtaining a melt of the burden from the components of the core and implementing its interaction with the coolant. To obtain the model corium of a fast neutron reactor, aluminum oxide (Al2O3) was used, and sodium was used as a coolant.

The results of the studies revealed the presence of three modifications of aluminum oxide Al2O3 in the phase composition of the solidified simulator. The main one is the α-modification (corundum), which is also the basic component of the initial burden. The appearance and regular distribution of other crystalline modifications of aluminum oxide is definitely a sign associated with the features of the processes occurring during the interaction between model corium and the coolant. Such features may be characteristic and extend to the actual melt of the reactor core, but may also be specific to the simulator used.

модельный кориумнатриевый теплоносительфрагментациярасплавэкспериментальное моделированиеmodel coriumsodium coolantfragmentationmeltexperimental modelingThis research is funded by the State Institution “Sci ence Committee of the Ministry of Science and Higher Education of the Republic of Kazakhstan” [IRN BR21882185 “Research in support of the establishment and safe operation of a nuclear power plant in the Republic of Kazakhstan”]ReferencesMatsuba K., Kato S., Kamiyama K., Akayev A., Baklanov V. Fragmentation and Cooling Behavior of a Simulated Molten Core Material Discharged into a Sodium Pool with Limited Depth and Volume // Proceedings of the 2021 28th International Conference on Nuclear Engineering. – 2021. – Vol. 3. – ICONE28-64500, V003T12A025. https://doi.org/10.1115/ICONE28-64500Matsuba K., Kato S., Kamiyama K., Akayev A., Baklanov V. 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The authors declare that there are no conflicts of interest present.