کوروش قیصری

In this thesis, the fuel burnup of the Bushehr reactor core at minimum and maximum power, in its second stage of fuel loading, has been simulated. At first the geometry of the core has been simulated by the MCNPX2.6 code. The core material temperatures, which are dependent on reactor powerو have been implemented in the NJOY code. In this respect, all the cross-sections have been calculated. The fuel burnup has been calculated versus workday (2, 60, 135 and 292 days) for different fuel assemblies.