Ядерна фізика та енергетика Nuclear Physics and Atomic Energy   ISSN: 1818-331X (Print), 2074-0565 (Online)   Publisher: Institute for Nuclear Research of the National Academy of Sciences of Ukraine   Languages: Ukrainian, English   Periodicity: 4 times per year   Open access peer reviewed journal

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S. V. Alyokhina, V. N. Goloshchapov, A. O. Kostikov, Yu. M. Matsevity

Anatolii Pidhornyi Institute of Mechanical Engineering Problems of the National Academy of Sciences of Ukraine, Kharkiv, Ukraine

Abstract: The process of heat-and-mass transfer in the ventilated concrete container used for prolonged intermediate storage of sealed cask with spent fuel rods is investigated by computer modelling in conditions of exterior airflow leaking. The problem is considered in the three-dimensional coupled statement with account of natural and forced convection, and radiation heat transfer. The results of analysis for a stand-alone container for various external wind influences are given.

Keywords: spent nuclear fuel, dry storage, ventilated cask, coupled problem of heat exchange.

1. P. Poskas, V. Simonis, R. Makarevicius. Thermal analysis of casks for interim storage of spent nuclear fuel. Mechanics 2 (1999) 47.

2. B. Kühne, R. Gartz, A. Voßnacke. Die nächste CASTOR - Generation zur Entsorgunng der deutschen Kernkraftwerke. Jahrestagung Kerntechnik, 2003: Tagungsbericht, Berlin, 20 - 22 Mai, 2003. Dtsch. Atomforum, Kerntechn (Ges. Berlin: INFORUM, 2003) p. 221.

3. M. Mckinnon, R. Dodge, R. Schmitt. Testing and Cobra-sfs Analysis of the Vsc-17 Ventilated Concrete, Spent Fuel Storage Cask. International high level radioactive waste management (IHLRWM) conference: promoting understanding through education and communication (Las Vegas -USА, 12 - 16 Apr., 1992).

4. T. E. Michener, D. R. Rector, J. M. Cuta et al. COBRA-SFS: A Thermal-Hydraulic Analysis Code for Spent Fuel Storage and Transportation Casks. Documentation for Cycle 2 (Pacific Northwest Laboratory Richland, Washington, 1995) 346 p. https://doi.org/10.2172/124912

5. A. Y. Walavalkar, D. G. Schowalter. 3-D CFD Simulation of a ventilated concrete cask used for spent nuclear fuel storage (Tucson, WM’04 Conference, February 29 - March 4, 2004).

6. Кутателадзе С. С. Теплопередача и гидродинамическое сопротивление. Справ. пособие (Москва: Энергоатомиздат, 1990) 367 с.

7. Тепло- и массообмен. Теплотехнический эксперимент. Справочник. Под общей ред. В. А. Григорьева, В. М. Зорина (Москва: Энергоиздат, 1982) 512 с.

8. С. В. Алехина, В. Н. Голощапов, А. О. Костиков, Ю. М. Мацевитый. Решение сопряженной задачи тепломассообмена при исследовании теплового состояния вентилируемого бетонного контейнера с отработавшим ядерным топливом. Проблемы машиностроения 8 (Харьков, 2005) c. 12.

9. B. E. Launder, D. B. Spalding. The Numerical Computation of Turbulent Flow. Comp. Meth. Appl. Eng. 3 (1974) 269. https://doi.org/10.1016/0045-7825(74)90029-2

10. Бейнер К. С. Анализ безопасности ВКХ-ВВЭР 1000. Symposium within XV Int. Youth Nuclear Festival "DYSNAI" (Visaginas, 2002) p. 22.