• COATED CLADDING BEHAVIOR DURING HIGH-TEMPERATURE TRANSIENTS 

      Autor: Chalupová, Adéla; Krejčí, Jakub; Cvrček, Ladislav; Ševeček, Martin; Rozkošný, Vojtěch; Přibyl, Antonín; Halodová, Patricie; Gávelová, Petra
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2019)
      The concept of accident-tolerant fuels has been proposed and widely investigated over the past decade. The contribution is focused on one of the near-term approaches - the modification of the surface of existing Zr-alloy ...
    • Degradation of Cr-coated cladding under the simulated Loss-of-Coolant Accident phenomena 

      Autor: Červenka, Petr; Krejčí, Jakub; Cvrček, Ladislav; Manoch, František; Chalupová, Adéla; Halodová, Patricie; Gávelová, Petra
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2022)
      The present study focuses on the evaluation of the mechanical properties degradation of Cr-coated Zr-alloy fuel cladding. The main objective of the work is to find a suitable methodology to evaluate the mechanical properties ...
    • NANOINDENTATION OF HYDROGEN ENRICHED Zr-1Nb ZIRCONIUM ALLOY NUCLEAR FUEL CLADDINGS 

      Autor: Libera, Ondřej; Halodová, Patricie; Gávelová, Petra; Krejčí, Jakub
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2020)
      Zirconium alloys are being commonly used as a material of choice for nuclear fuel claddings in water cooled nuclear reactors for decades due to their good corrosion resistance and low neutron absorption. However, the ...