Nuclear Engineering and Technology

  • 제48권5호
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  • Pages.1162-1173
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  • 2016
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Modeling of Hydrodynamic Processes at a Large Leak of Water into Sodium in the Fast Reactor Coolant Circuit

  • Perevoznikov, Sergey (Joint Stock Company State Scientific Centre of the Russian Federation - Institute for Physics and Power Engineering named after A.I. Leypunsky) ;
  • Shvetsov, Yuriy (Joint Stock Company State Scientific Centre of the Russian Federation - Institute for Physics and Power Engineering named after A.I. Leypunsky) ;
  • Kamayev, Aleksey (Joint Stock Company State Scientific Centre of the Russian Federation - Institute for Physics and Power Engineering named after A.I. Leypunsky) ;
  • Pakhomov, Ilia (Joint Stock Company State Scientific Centre of the Russian Federation - Institute for Physics and Power Engineering named after A.I. Leypunsky) ;
  • Borisov, Viacheslav (Joint Stock Company State Scientific Centre of the Russian Federation - Institute for Physics and Power Engineering named after A.I. Leypunsky) ;
  • Pazin, Gennadiy (Joint Stock Company State Scientific Centre of the Russian Federation - Institute for Physics and Power Engineering named after A.I. Leypunsky) ;
  • Mirzeabasov, Oleg (Joint Stock Company State Scientific Centre of the Russian Federation - Institute for Physics and Power Engineering named after A.I. Leypunsky) ;
  • Korzun, Olga (Joint Stock Company State Scientific Centre of the Russian Federation - Institute for Physics and Power Engineering named after A.I. Leypunsky)
  • 투고 : 2015.04.21
  • 심사 : 2016.04.27
  • 발행 : 2016.10.25
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초록

In this paper, we describe a physicomathematical model of the processes that occur in a sodium circuit with a variable flow cross-section in the case of a water leak into sodium. The application area for this technique includes the possibility of analyzing consequences of this leak as applied to sodium-water steam generators in fast neutron reactors. Hydrodynamic processes that occur in sodium circuits in the event of a water leak are described within the framework of a one-dimensional thermally nonequilibrium three-component gas-liquid flow model (sodium-hydrogen-sodium hydroxide). Consideration is given to the results of a mathematical modeling of experiments involving steam injection into the sodium loop of a circulation test facility. That was done by means of the computer code in which the proposed model had been implemented.

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참고문헌

  1. Y. Buksha, Fast Reactor Fuel Failures and Steam Generation Leaks: Transient and Accident Analysis Approaches, IAEA-TECDOC-908, October 1996.
  2. V.M. Poplavskiy, F.A. Kozlov, Bezopasnost' Parogeneratorov Natriy-voda (Sodium-water Steam Generators Safety), Energoatomizdat, Moscow, 1990.
  3. Y.W. Shin, R.A. Valentin, SWAAM Code development, Verification, and Application to Steam Generator Design, Proceedings of the specialists' meeting on steam generator failure and propagation experience, Aix-en Provence, France, September 26-28, 1990.
  4. F.A. Kozlov, E.K. Kuznetsov, G.P. Sergeev, L.G. Volchkov, Rabota parogeneratora s natriem i vodoy i vtorogo kontura pri malykh techakh vody v natriy (Operation of Sodium-water Steam Generator and the Secondary Circuit in Case of Small Water Leaks into Sodium), Works of Institute for Physics and Power Engineering, Atomizdat, Moscow, 1974.
  5. I.A. Kuznetsov, V.M. Poplavskiy, Bezopasnost' AES s reaktorami na bystrykh neytronakh (Safety of NPPS with Fast Reactors), IzdAT, Moscow, 2012.
  6. K.M. Magomedov, A.S. Kholodov, Setochnokharakteristichekie chislennye metody (Mesh-characteristic Numerical Methods), Nauka, Moscow, 1988.

피인용 문헌

  1. Spectroscopic, pressure and temperature measurements of the reactant mixing process in sodium-water reaction vol.364, pp.None, 2016, https://doi.org/10.1016/j.nucengdes.2020.110638