Kinetic parameters calculation of sodium-cooled fast reactor (SFR) MOX-1000 MWth using OpenMC code

Calculation of kinetic parameters of Sodium-cooled Fast Reactor (SFR) core design with 1000 MWth thermal power and Mix-Oxide (MOX) fuel has been determined. This study compares the SFR core kinetic parameters value using OpenMC against kinetic parameter value on the OECD/NEA "Benchmark for Neutronic Analysis of Sodium-cooled Fast Reactor Cores with Various Fuel Types and Core Sizes". Flux distribution and fission reactions rate distribution on SFR core has been calculated. Geometric design and kinetic parameters calculation were performed using OpenMC with nuclear data library ENDF/B-VII.1. Depletion will be carried out for 328.5 days assuming the reactor efficiency is 90% of full operating time, which is for 1 year. The calculation results show that the kinetic parameter values from OpenMC against benchmark in BOC and EOC conditions are still within the standard deviation of the benchmark. Flux distribution and fission reaction distribution value decreased from BOC to EOC state. This is due to the conversion ratio value of about ∼0.7 which means that the production of fissile material is lower than the consumption of fissile material. So it can be concluded that the correlation of the results obtained in calculations using OpenMC already has a good results. These results can be used as a validation of calculations using OpenMC and can be developed for variations in reactor design for further research on the SFR core.