nucВестник НЯЦ РКNNC RK Bulletin1729-75161729-7885Национальный ядерный центр Республики Казахстан10.52676/1729-7885-2025-2-12-21nuc-885Research ArticleСтатьиНЕЙТРОННО-ФИЗИЧЕСКИЕ РАСЧЁТЫ В ОБОСНОВАНИЕ ТЕХНИЧЕСКОЙ ВОЗМОЖНОСТИ ПРИМЕНЕНИЯ ТРАНСПОРТИРОВОЧНОГО КОНТЕЙНЕРА ДЛЯ ОТРАБОТАННОГО ЯДЕРНОГО ТОПЛИВА ПОСЛЕ КРАТКОВРЕМЕННОЙ ВЫДЕРЖКИ С ИСПОЛЬЗОВАНИЕМ МЕТОДОВ КОМПЬЮТЕРНОГО ИМИТАЦИОННОГО МОДЕЛИРОВАНИЯRADIATION AND NUCLEAR SAFETY ANALYSIS FOR THE SPENT FUEL TRANSPORTATION PACKAGE AFTER THE SHORT-TERM COOLING BY USING COMPUTER SIMULATION MODELING METHODSЗарваД. Б.ZarvaD. B.

Курчатов 

Kurchatov

zarva@nnc.kzТурЕ. С.TurYe. S.

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Kurchatov

tur_es@mail.ruМукеневаС. А.MukenevaS. A.

Курчатов 

Kurchatov

mukeneva@nnc.kzГулькинА. В.GulkinA. V.

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Kurchatov

gulkin@nnc.kzБатырбековЭ. Г.BatyrbekovE. G.

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Kurchatov

batyrbekov@nnc.kzВитюкВ. А.VityukV. A.

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Kurchatov

vityuk@nnc.kzРГП «Национальный ядерный центр Республики Казахстан»КазахстанRSE “National Nuclear Center of the Republic of Kazakhstan”Kazakhstan202514072025021221Copyright © Зарва Д.Б., Тур Е.С., Мукенева С.А., Гулькин А.В., Батырбеков Э.Г., Витюк В.А., 20252025Зарва Д.Б., Тур Е.С., Мукенева С.А., Гулькин А.В., Батырбеков Э.Г., Витюк В.А.Zarva D.B., Tur Y.S., Mukeneva S.A., Gulkin A.V., Batyrbekov E.G., Vityuk V.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/885

Данная работа является завершающим этапом двухстадийных комплексных исследований, направленных на обоснование возможности перемещения ОЯТ после кратковременной выдержки и выработку требований к конструкции ТУК.

В работе представлены результаты исследований по обоснованию технической возможности применения транспортировочного контейнера для транспортировки отработанного ядерного топлива после кратковременной выдержки. Выполнены расчеты защиты от радиоактивного излучения, обоснована ядерная безопасность, изучены соответствующие сопровождающие нейтронно-физические процессы. В результате проведенных работ обоснована техническая возможность применения транспортировочного контейнера для отработанного ядерного топлива, предложен наиболее приемлемый вариант контейнера для отработанного ядерного топлива с газовым заполнением или с жидкостным заполнением поглотителя в корзине с конструкцией из материалов: железобетон + диоксид урана и чугун + диоксид урана.

Для достижения поставленной цели в работе использовались методы компьютерного имитационного моделирования, проводились расчеты в обоснование радиационной защиты и ядерной безопасности в нормальных и аварийных условиях эксплуатации, изучались нейтронно-физические процессы, сопровождающие ТУК с ОЯТ. В работе рассмотрены несколько вариантов материалов для радиационной защиты, в зависимости от их толщины и наполняемости контейнера ОТВС.

The paper presents the results of studies to substantiate the possibility of using a transport container for the spent nuclear fuel after short-term cooling. Calculations for radiation protection have been completed, nuclear safety has been justified, and the relevant accompanying neutron-physical processes have been studied. As a result, technical feasibility of using a transport container for spent nuclear fuel has been substantiated. The most acceptable option of a container for spent nuclear fuel is to be made of iron-concrete + uranium dioxide and cast iron + uranium dioxide with gas filling or with liquid filling of the absorber in a basket.

To achieve the set goal, methods of computer simulation modeling were used, calculations were conducted to justify radiation protection and nuclear safety under normal and emergency operating conditions, and neutron-physical processes accompanying spent nuclear fuel were studied. The work examined several options for materials for radiation protection, depending on their thickness and the fill of the spent nuclear fuel container.

ядерное топливоядерный топливный циклядерная безопасностьконтейнер для отработанного ядерного топливаядерный реакторnuclear fuel cyclenuclear safetyspent fuelcontainernuclear reactorThis work was financially supported by the Scientific Committee of the Ministry of Science and Higher Education of the Republic of Kazakhstan (Grant No. BR21882185)This work was financially supported by the Scientific Committee of the Ministry of Science and Higher Education of the Republic of Kazakhstan (Grant No. BR21882185).ReferencesConceptual View of the Implementation of the Nuclear Energy Program in the Republic of Kazakhstan / Batyrbekov E., Vityuk V., Zarva D., Sharipov M. // Energies. – 2024. – Vol. 17. – No. 22. – P. 5788.Conceptual View of the Implementation of the Nuclear Energy Program in the Republic of Kazakhstan / Batyrbekov E., Vityuk V., Zarva D., Sharipov M. // Energies. – 2024. – Vol. 17. – No. 22. – P. 5788.Connolly, K.J., Pope, R.B. A Historical Review of the Safe Transport of Spent Nuclear Fuel. – US Department of Energy. FCRD-NFST-2016-000474. – August 31, 2016.Connolly, K.J., Pope, R.B. A Historical Review of the Safe Transport of Spent Nuclear Fuel. – US Department of Energy. FCRD-NFST-2016-000474. – August 31, 2016.D. Aquaro, N. Zaccari, M. Di Prinzio, G. Forasassi Numerical and experimental analysis of the impact of a nuclear spent fuel cask // Nuclear Engineering and Design. –2010. – Vol. 240, Issue 4.– P. 706–712.D. Aquaro, N. Zaccari, M. Di Prinzio, G. Forasassi Numerical and experimental analysis of the impact of a nuclear spent fuel cask // Nuclear Engineering and Design. –2010. – Vol. 240, Issue 4.– P. 706–712.Belal Almomani, Yoon-Suk Chang Failure probability assessment of SNF cladding transverse tearing under a hypothetical transportation accident // Nuclear Engineering and Design. –2021. – Vol. 379.Belal Almomani, Yoon-Suk Chang Failure probability assessment of SNF cladding transverse tearing under a hypothetical transportation accident // Nuclear Engineering and Design. –2021. – Vol. 379.Rules for the Safe Transport of Radioactive Materials. 2018 Edition No. SSR-6 (Rev. 1), IAEA.Rules for the Safe Transport of Radioactive Materials. 2018 Edition No. SSR-6 (Rev. 1), IAEA.“Rules for the Transportation of Nuclear Materials, Radioactive Substances, and Radioactive Waste” Approved by the Order of the Minister of Energy of the Republic of Kazakhstan dated May 28, 2021, No. 183.“Rules for the Transportation of Nuclear Materials, Radioactive Substances, and Radioactive Waste” Approved by the Order of the Minister of Energy of the Republic of Kazakhstan dated May 28, 2021, No. 183.American Society of Mechanical Engineers, ASME BPVC Section III – Rules for Construction of Nuclear Facility Components – Division 1. In Subsection NB: Class Components, 2010.American Society of Mechanical Engineers, ASME BPVC Section III – Rules for Construction of Nuclear Facility Components – Division 1. In Subsection NB: Class Components, 2010.American Society of Mechanical Engineers, ASME BPVC Section III – Rules for Construction of Nuclear Facility Components – Appendices, 2015.American Society of Mechanical Engineers, ASME BPVC Section III – Rules for Construction of Nuclear Facility Components – Appendices, 2015.Safety Rules for the Storage and Transportation of Nuclear Fuel at Nuclear Power Facilities. PnAE G-14-029-91.Safety Rules for the Storage and Transportation of Nuclear Fuel at Nuclear Power Facilities. PnAE G-14-029-91.General Provisions for Ensuring the Safety of Nuclear Fuel Cycle Facilities (GPB OYATs). NP-0162000, Moscow, 2000.General Provisions for Ensuring the Safety of Nuclear Fuel Cycle Facilities (GPB OYATs). NP-0162000, Moscow, 2000.Nuclear Safety Rules for the Transportation of Spent Nuclear Fuel. PBYA-06-08-77, 1978.Nuclear Safety Rules for the Transportation of Spent Nuclear Fuel. PBYA-06-08-77, 1978.J. B. Lambert, “Events During the Postulated Drop Accident with BN-350 Cask”, Argonne National Laboratory Intra-Laboratory Memo to R. W. Schaefer, December 3, 1998.J. B. Lambert, “Events During the Postulated Drop Accident with BN-350 Cask”, Argonne National Laboratory Intra-Laboratory Memo to R. W. Schaefer, December 3, 1998.

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