. . . . . "Model of cooling fuel rod in the nuclear reactor" . . . "271791" . "P(GP101/09/P056), S" . . . "Polansk\u00FD, Ji\u0159\u00ED" . "RIV/49777513:23640/10:00503635" . . "Model of cooling fuel rod in the nuclear reactor" . "CFD; PIV. velocity flow field; temperature field; numerical simulation; annular vertical tube"@en . "2"^^ . . "23640" . "RIV/49777513:23640/10:00503635!RIV11-GA0-23640___" . . . "Model of cooling fuel rod in the nuclear reactor"@en . . "Model of cooling fuel rod in the nuclear reactor"@en . "The paper presents the erected experimental apparatus ?Model of fuel rod cooling inside a nuclear reactor?. The fuel rod model allows the general public to observe phenomena of fluid mechanics and thermomechanics. Safety and operational reasons usually prevent these phenomena from being observed in real-life equipment. The most interesting and important phenomena are ?boiling crisis? and related nonstationary heat transfer in multi-phase flow."@en . "The paper presents the erected experimental apparatus ?Model of fuel rod cooling inside a nuclear reactor?. The fuel rod model allows the general public to observe phenomena of fluid mechanics and thermomechanics. Safety and operational reasons usually prevent these phenomena from being observed in real-life equipment. The most interesting and important phenomena are ?boiling crisis? and related nonstationary heat transfer in multi-phase flow." . . . . . . "2"^^ . "[9410D77079D7]" . "L\u00E1vi\u010Dka, David" .