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This paper provides information about the possibility to apply the FEMAXI-6 code for RBMK-1500 reactors. New thermal properties and correlations responsible for thermal analysis (thermal conductivity and heat capacity) according to RBMK-1500 specification were included into the FEMAXI-6 code. The RBMK-1500 fuel rod model using the adapted FEMAXI-6 code was developed and tested by employing uncertainty and sensitivity analysis. The processes in fuel rods during normal plant operation were modelled. The results received were compared with calculations performed by specialists from the Kurchatov Institute (designers of RBMK). The reasonable agreement of both calculation results shows that the adapted FEMAXI-6 code and the developed model are suitable for future analysis of processes in fuel rods of RBMK-1500 reactors. Also this work demonstrates what sensitivity and uncertainty analysis can be used for the model development.

Adaptation of the FEMAXI-6 code and RBMK fuel rods model testing employing the best estimate approach