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Modeling of Hydrodynamic Processes at a Large Leak of Water into Sodium in the Fast Reactor Coolant Circuit

  • Perevoznikov, Sergey;Shvetsov, Yuriy;Kamayev, Aleksey;Pakhomov, Ilia;Borisov, Viacheslav;Pazin, Gennadiy;Mirzeabasov, Oleg;Korzun, Olga
    • Nuclear Engineering and Technology
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    • v.48 no.5
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    • pp.1162-1173
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    • 2016
  • 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.