nucВестник НЯЦ РКNNC RK Bulletin1729-75161729-7885Национальный ядерный центр Республики Казахстан10.52676/1729-7885-2025-2-5-11nuc-875Research ArticleСтатьиТЕПЛОФИЗИЧЕСКИЙ АНАЛИЗ ТРАНСПОРТИРОВОЧНОГО КОНТЕЙНЕРА ДЛЯ ОТРАБОТАННОГО ЯДЕРНОГО ТОПЛИВА ПОСЛЕ КРАТКОВРЕМЕННОЙ ВЫДЕРЖКИ С ИСПОЛЬЗОВАНИЕМ МЕТОДОВ КОМПЬЮТЕРНОГО ИМИТАЦИОННОГО МОДЕЛИРОВАНИЯTHERMAL ANALYSIS FOR THE SPENT FUEL TRANSPORTATION PACKAGE AFTER SHORT-TERM COOLING BY USING COMPUTER SIMULATION MODELING METHODSЗарваД. Б.ZarvaD. B.

 Курчатов

Kurchatov

zarva@nnc.kzМукеневаС. А.MukenevaS. A.

Курчатов

Kurchatov

Mukeneva@nnc.kzТурЕ. С.TurYe. S.

Курчатов

Kurchatov

tur_es@mail.ruГулькинА. В.GulkinA. V.

Курчатов

Kurchatov

gulkin@nnc.kzВитюкВ. А.VityukV. A.

Курчатов

Kurchatov

vityuk@nnc.kzБатырбековЭ. Г.BatyrbekovE. G.

Курчатов

Kurchatov

АкаевА. С.AkayevA. S.

Курчатов

Kurchatov

akaev@nnc.kzРГП «Национальный ядерный центр Республики Казахстан»КазахстанRSE “National Nuclear Center of the Republic of Kazakhstan”KazakhstanФилиал «Институт атомной энергии» РГП НЯЦ РККазахстанBranch “Institute of Atomic Energy” RSE NNC RKKazakhstan20251407202502511Copyright © Зарва Д.Б., Мукенева С.А., Тур Е.С., Гулькин А.В., Витюк В.А., Батырбеков Э.Г., Акаев А.С., 20252025Зарва Д.Б., Мукенева С.А., Тур Е.С., Гулькин А.В., Витюк В.А., Батырбеков Э.Г., Акаев А.С.Zarva D.B., Mukeneva S.A., Tur Y.S., Gulkin A.V., Vityuk V.A., Batyrbekov E.G., 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/875

В работе представлены результаты исследований по обоснованию технической возможности применения контейнера для перемещения свежевыгруженного из реактора отработанного ядерного топлива. Выполнены расчеты по оценке уровня энерговыделения и радиационных характеристик отработанного ядерного топлива, которые в свою очередь послужили основанием для дальнейших теплофизических расчётов контейнера.

Предполагается, что с использованием контейнера становится возможным перевозка от 5 тепловыделяющих сборок реакторов большой мощности типа ABWR, AP1000 и ВВЭР-1000.

В результате работы обоснована техническая возможность применения транспортировочного контейнера для отработанных тепловыделяющих сборок после кратковременной выдержки с точки зрения протекающих в них теплофизических процессов, накладывающих определенные ограничения на конструкцию контейнера.

Данная работа является первой частью комплексных исследований, направленных на обоснование возможности перемещения отработавшего топлива после кратковременной выдержки и выработки требований к конструкции контейнера.

The paper presents the results of studies to substantiate the possibility of using a container for transfer of spent nuclear fuel after the short-term cooling. Spent nuclear fuel source-terms and energy release calculations, as well as thermal hydraulic calculations have been made to serve as the basis for further studies.

The proposed transport package is designed for transportation of recently discharged spent nuclear fuel with a high level of radioactivity. It is assumed that the use of this package allow transportation of up to 5 fuel assemblies from high-power reactors such as ABWR, AP1000, and VVER-1000.  

As a result of this study, the possibility of using a transport package for spent fuel assemblies after the short-term cooling is substantiated in terms of the thermal processes that occur within them. These processes impose specific restrictions on the container design.

This work is the first part of a comprehensive study aimed to substantiate the possibility of transporting spent fuel after the short-term cooling and develop requirements for the design of such transport packages. 

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