Nuclear Design Tool Development For Thermal And Fast Reactors

Migration Mode Method for Reactor Calculations

  • Feasibility Study for MMM application for thermal reactor calculation – UOx and MOX fuel
  • Feasibility Study for MMM application to gas cooled reactor calculation
  • Code development for cross-sections library preparation based on MMM (for Cell and Core Codes coupling)

Implementation of a neutron diffusion computer code based on MMM method

design_tool2

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