Now showing items 1-2 of 2

    • Few group cross section representation based on sparse grid methods 

      Botes, Danniëll (North-West University, 2012)
      This thesis addresses the problem of representing few group, homogenised neutron cross sections as a function of state parameters (e.g. burn-up, fuel and moderator temperature, etc.) that describe the conditions in the ...
    • Global sensitivity analysis of reactor parameters 

      Adetula, Bolade Adewale (North-West University, 2011)
      Calculations of reactor parameters of interest (such as neutron multiplication factors, decay heat, reaction rates, etc.), are often based on models which are dependent on groupwise neutron cross sections. The uncertainties ...