Procházení Acta Polytechnica CTU Proceedings. 2020, vol. 28 dle data publikování

Zobrazují se záznamy 1-7 z 7

    • ANALYSIS OF FAST NEUTRON TRANSPORT IN CHLORIDE SALTS USING MONTE CARLO METHOD 

      Autor: Šťastný, Ondřej; Katovský, Karel; Král, Dušan; Krása, Antonín; Števanka, Kamil
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2020)
      The aim of this paper is to present results of fast neutron behavior analysis within the chloride salts environment using simulations based on Monte Carlo method (MCNP 6.2). Three non-fueled salts (NaCl, KCl, MgCl2) and ...

    • EXPERIMENTAL INVESTIGATION OF CRITICAL HEAT FLUX IN ANNULUS AT LOW PRESSURE AND LOW FLOW PARAMETERS 

      Autor: Vlček, Daniel; Suk, Ladislav; Števanka, Kamil; Petrosyan, Taron
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2020)
      Steady state flow boiling experiments were conducted on a technically smooth Inconel 625 tube with outer diameter 9.1 mm at inlet pressures 131, 220 and 323 kPa, inlet temperatures 62, 78 and 94 °C and approximately 400, ...

    • THERMAL ANALYSIS OF DRY STORAGE AND TRANSPORTATION CASKS CASTOR USING COBRA-SFS 

      Autor: Ševeček, Martin; Valach, Mojmír; Lee, Chih-Hao
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2020)
      State Office for Nuclear Safety is a regulator body in the Czech Republic handling also licensing of storage and transportation casks (SCs) of the spent nuclear fuel (SNF). One of the main concerns for the dry storage of ...

    • INVESTIGATION OF CRITICAL HEAT FLUX ON ABRADED INCONEL 625 TUBE 

      Autor: Suk, Ladislav; Števanka, Kamil; Petrosyan, Taron; Vlček, Daniel
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2020)
      Aim of this work was to study flow boiling in an annular channel at low pressure and low flow on a tube with modified surface roughness. The tube with the outer diameter of 9.14 mm and the heated length of 380 mm was made ...

    • METHODS OF XS DATA PREPARATION FOR GEOMETRY WITH FUEL DUMMY 

      Autor: Suk, Pavel
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2020)
      3D deterministic core calculation represents important category of the nuclear fuel cycle and safe Nuclear Power Plant operation. The appropriate solution was not published yet. Data preparation process for non-fuel elements ...

    • EXPERIMENTAL STUDY OF DAMAGED CR-COATED FUEL CLADDING IN POST-ACCIDENT CONDITIONS 

      Autor: Červenka, Petr; Krejčí, Jakub; Cvrček, Ladislav; Rozkošný, Vojtěch; Manoch, František; Rada, David; Kabátová, Jitka
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2020)
      To enhance the safety of nuclear power, the focus of researchers all around the world has recently mainly objected on the development of Accident Tolerant Fuels. Especially the Chromium coating of current Zirconium based ...

    • HIGH-TEMPERATURE OXIDATION OF CHROME-NICKEL ALLOY 

      Autor: Chalupová, Adéla; Steinbrück, Martin; Grosse, Mirco; Krejčí, Jakub; Ševeček, Martin
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2020)
      The investigations in this paper deal with the Cr-Ni alloy. The material has been recently proposed as a potential ATF concept, primarily due to its behaviour under high-temperature oxidation. A set of experiments to ...