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    • POST CRITICAL HEAT TRANSFER AND FUEL CLADDING OXIDATION 

      Author: 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 ...