Prohlížení Časopisy dle autora "4e899167-c10f-4fc6-87eb-b1dcd0f8c886"

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    • 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 ...

    • Proposal of point-wise power reconstruction for IRT-4M fuel assemblies in coupled Monte-Carlo calculations 

      Autor: Jíška, Pavel; Frýbort, Jan
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2022)
      Current efforts to develop high-fidelity multi-physics tools for research reactors with IRT-4M fuel leads to the involvement of Monte-Carlo transport and subchannel thermo-hydraulic codes in the process of safety assessment. ...

    • SCALE AND SERPENT TWO-GROUP CROSS-SECTION DATA GENERATION 

      Autor: Novák, Ondřej; Frýbort, Jan; Sklenka, Lubomír; Rataj, Jan; Chvála, Ondřej
      (České vysoké učení technické v PrazeCzech Technical University in Prague, 2018)
      In this work, VVER fuel assembly is calculated using two different codes - Serpent and SCALE. Multiplication factor and several two-group macroscopic parameters including scattering cross-section, fission cross-section, ...