IGCAR results of BN-600 full MOX core benchmark calculations

During the third RCM of IAEA-CRP on Updated Codes and Methods to Reduce the Calculational Uncertainties of LMFR Reactivity Effects, it was decided to analyse a full MOX core benchmark of BN-600. Specifications of this benchmark was supplied by IPPE and IAEA. The benchmark consisted of a three zone MOX core of BN-600 with a Na plenum above core, an internal breeding zone and no radial blanket. The IGCAR calculations were done using 26 group ABBN type nuclear data set. Only homogeneous model of the core was analysed by diffusion theory. Three-dimensional calculations were done by the 3DB code with 6 meshes per fuel assembly. Criticality worth distribution was calculated by perturbation theory. Delayed neutrons are derived from the INDC-NDS-107. Power distribution was calculated assuming that 200 MeV is released at the point fission and zero neutron capture energy release