Analysis of Fuel Burn-up Calculations of 3600 MWth Sodium cooled Fast Reactor Core

Fast spectrum reactors are essential for the future of nuclear energy. Therefore, there is a need continuous research and development design safety current fast reactors. The aim this work to analyze process fuel burnup in large scale (3600 MWth) Sodium cooled Reactor (SFR) core. This called European (ESFR). It proposed 7th Framework Programme within Euratom Framework. A new version (version 2.7) Monte Carlo neutron transport code (MCNPX) was used 3D model ESFR core evaluate number burnup-relevant characteristics. These include flux power distributions across as well reactivity changes transmutation during take into account composition burnup. Obtained results can serve up date evaluation allow detailed assessments performance inside