Prohlížení České vysoké učení technické v Praze dle autora "331ebfce-120e-4c86-9caf-867c7c894bb4"

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    • EXPERIMENTAL INVESTIGATION OF CRITICAL HEAT FLUX IN ANNULUS AT LOW PRESSURE AND LOW FLOW PARAMETERS 

      Autor: Vlček, Daniel; Suk, Ladislav; Števanka, Kamil; Petrosyan, Taron
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2020)
      Steady state flow boiling experiments were conducted on a technically smooth Inconel 625 tube with outer diameter 9.1 mm at inlet pressures 131, 220 and 323 kPa, inlet temperatures 62, 78 and 94 °C and approximately 400, ...

    • HEAT TRANSFER MODELLING OF TWO-PHASE FLOW IN ISOLATED CHANNEL 

      Autor: Vlček, Daniel; Caha, Vojtěch; Ševeček, Martin
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2018)
      This paper deals with Post-CHF (critical heat flux) heat transfer with the focus on different regimes of film boiling. The new thermal-hydraulic code TUBE 2.0 is presented. This code uses the equation of energy conservation ...

    • INVESTIGATION OF CRITICAL HEAT FLUX ON ABRADED INCONEL 625 TUBE 

      Autor: Suk, Ladislav; Števanka, Kamil; Petrosyan, Taron; Vlček, Daniel
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2020)
      Aim of this work was to study flow boiling in an annular channel at low pressure and low flow on a tube with modified surface roughness. The tube with the outer diameter of 9.14 mm and the heated length of 380 mm was made ...

    • RESIDUAL HEAT POWER REMOVAL FROM SPENT NUCLEAR FUEL DURING DRY AND WET STORAGE 

      Autor: Vlček, Daniel
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2018)
      This project deals with the thermal analyses of the wet and dry storages of the spent nuclear fuel. The dry spent fuel storage sub-channel code COBRA-SFS has been used in order to calculate the temperature field. In this ...