Acta Polytechnica CTU Proceedings. 2023, vol. 44

 

Zobrazují se záznamy 1-5 z 5

    • Evaluation of ATLHAMC12 subchannel code for total loss of flow scenario 

      Autor: Křeček, Tomáš; Foral, Štěpán
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2023)
      The ALTHAMC12 subchannel code is a new subchannel code developed by the ALVEL company. The code is intended for DNBR safety analyses of the Czech nuclear power plants. In order to validate the code, a code to code comparison ...

    • Effect of heat-treatment on material properties of L-DED printed austenistic alloy 08CH18N10T for nuclear reactor applications 

      Autor: Jedlan, Štěpán; Ševeček, Martin; Prantl, Antonín; Hodek, Josef; Podaný, Pavel; Brázda, Michal
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2023)
      This paper deals with the evaluation of material properties of the additively manufactured austenistic alloy 08CH18N10T, which is widely used in the Czech Republic nuclear power plants Temelín and Dukovany and other VVER ...

    • Simulation of the compression test of the Zr1Nb fuel cladding ring 

      Autor: Smolík , Vojtěch; Endrychová, Alžběta; Krejčí, Jakub
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2023)
      Fuel cladding is a first protective barrier against the loss of fission products that must withstand extreme conditions, from normal operation to final and interim dry storage. This hostile environment results in mechanical ...

    • Neutronic analysis of a heat-pipe cooled reactor 

      Autor: Sabol, Josef; Frýbort, Jan
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2023)
      Heat-pipe cooled reactors belong to the group of nuclear reactors using heat pipes filled with liquid metals (such as sodium or potassium) to cool the core. Due to the passive heat removal system, there is no need to use ...

    • Thermomechanical calculation within the HERA programme 

      Autor: Kinkorová, Tereza
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2023)
      HERA (High Burnup Experiments in Reactivity Initiated Accident) is one of the programmes which should replace closed Halden reactor. As the name implies HERA is focused on the tests simulated RIA (Reactivity Initiated ...