Definition of conservative conditions for RIA analysis in the modernized RBMK reactor core

During the past decade a number of modifications were implemented in the Ignalina NPP reactors cores. A significant reactor core loading change allowed increasing the safety level of the plant. During previously performed safety analyses a question has arisen concerning conservatism of used initial boundary conditions for investigation. The impact of different axial fuel burn-up and power-density profiles in the reactor core on modelling results as well as estimation of conservative conditions for the analysis of reactivity initiated accidents in the modernized RBMK-1500 reactor core were analyzed. The results of the investigations are presented in this paper. Simulation results show that previously used initial boundary conditions for modelling of accidents are changing due to a change of composition and loading in the modernized RBMK reactor core. (orig.)