• 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 ...
    • MIXED CORE SUBCHANNEL MODEL FOR SUBCAL AND COUPLING WITH ANDREA 

      Autor: Caha, Vojtěch; Čížek, Jiří
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2018)
      This paper presents the results of an analysis of flow distribution in VVER-1000 mixed core consisting of fuel assemblies with non-identical spacing grids. The calculation was carried out using the modified subchannel code ...
    • POST CRITICAL HEAT TRANSFER AND FUEL CLADDING OXIDATION 

      Autor: Caha, Vojtěch; Krejčí, Jakub
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2016)
      The knowledge of heat transfer coefficient in the post critical heat flux region in nuclear reactor safety is very important. Although the nuclear reactors normally operate at conditions where critical heat flux (CHF) is ...