• 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 ...
    • LATERAL COOLANT FLOW BETWEEN FUEL ASSEMBLIES IN MIXED CORES 

      Autor: Caha, Vojtech; Čížek, Jiří
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2018)
      This paper presents the results of an analysis of lateral coolant flow between adjacent fuel assemblies with non-identical spacing grids in a mixed core consisting of TVSA-T mod.1 and TVSA-T mod.2 fuel assemblies. The ...
    • COUPLED SIMULATION OF GAS COOLED FAST REACTOR FUEL ASSEMBLY WITH NESTLE CODE SYSTEM 

      Autor: Osusky, Filip; Cerba, Stefan; Luley, Jakub; Vrban, Branislav; Hascik, Jan
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2018)
      The paper is focused on coupled calculation of the Gas Cooled Fast Reactor. The proper modelling of coupled neutronics and thermal-hydraulics is the corner stone for future safety assessment of the control and emergency ...
    • IMITATING NEUTRON IRRADIATION DAMAGE USING A COMBINATION OF ION BEAMS 

      Autor: Šísl, Václav; Ševeček, Martin
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2018)
      There is a strong motivation for using ion beams to imitate neutron irradiation damage, mainly in order to reduce costs and time demands linked to neutron irradiation experiments. The long-term goal of the authors is to ...
    • NEUTRONIC ANALYSIS OF THE CANDIDATE MULTI-LAYER CLADDING MATERIALS WITH ENHANCED ACCIDENT TOLERANCE FOR WWER REACTORS 

      Autor: Novák, Ondřej; Ševeček, Martin
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2018)
      The paper summarizes preliminary results of neutronic analysis of candidate ATF cladding materials that are under development at the CTU in Prague. To evaluate basic neutronics-related characteristics the Serpent code was ...
    • ULTRA-LOW INTENSITY PROTON BEAMS FOR RADIATION RESPONSE RELATED EXPERIMENTS AT THE U-120M CYCLOTRON 

      Autor: Matlocha, Tomas; Krizek, Filip
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2018)
      The U-120M cyclotron at the Nuclear Physics Institute (NPI) of the Czech Academy of Sciences in Rez is used for radiation hardness tests of electronics for high-energy physics experiments. These tests are usually carried ...
    • UNCERTAINTY PROPAGATION FOR LWR BURNUP BENCHMARK USING SAMPLING BASED CODE SCALE/SAMPLER 

      Autor: Campolina, Daniel; Frybort, Jan
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2018)
      Sampling based method is adopted in many fields of engineering and it is currently used to propagate uncertainties from physical parameters and from nuclear data, to integral indicators of nuclear systems. The total ...
    • CALCULATION UNCERTAINTIES IN SPENT FUEL INVENTORY DETERMINATION 

      Autor: Czakoj, Tomas; Frybort, Jan; Lovecky, Martin
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2018)
      In the depletion calculation of the nuclear fuel, the uncertainty is of utmost importance, as it affects the uncertainty of the subsequent calculation, when the calculated composition is used. The calculations are even ...
    • ŠIMÁNĚ 2017 

      Autor: Foreword, Editorial,
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2018)
      Nuclear science and technology have a long history within the Czechoslovakia. Even though the Czech Republic and Slovakia have been separated since 1993, wide cooperation on different levels including education and research ...