Monte Carlo simulations of the 1000 MWth SFR OECD/NEA benchmark with SERPENT code

The report presents the simulations of the medium size 1000 MWth Sodium-Cooled Fast Reactor (SFR) core with oxide and metallic fuel. The core design is based on the OECD/NEA “Benchmark for Neutronic Analysis of Sodium- cooled Fast Reactor Cores with Various Fuel Types and Core Sizes”. The full-core 3D model and simulations were prepared with SERPENT 2.1.28 Monte Carlo neutron transport computer code. Static k-eigenvalue criticality and isotopic depletion calculations were performed with ENDF\B-VII.0 and JEFF 3.1.1 nuclear data libraries. The Beginning of Equilibrium Cycle (BOEC) state, the core depletion process and End of Equilibrium Cycle (EOEC) state were simulated. The obtained results confirm that the prepared models are appropriate, as the majority of the obtained results is in agreement with the Benchmark data single standard deviation.The report presents the simulations of the medium size 1000 MWth Sodium-Cooled Fast Reactor (SFR) core with oxide and metallic fuel. The core design is based on the OECD/NEA “Benchmark for Neutronic Analysis of Sodium- cooled Fast Reactor Cores with Various Fuel Types and Core Sizes”. The full-core 3D model and simulations were prepared with SERPENT 2.1.28 Monte Carlo neutron transport computer code. Static k-eigenvalue criticality and isotopic depletion calculations were performed with ENDF\B-VII.0 and JEFF 3.1.1 nuclear data libraries. The Beginning of Equilibrium Cycle (BOEC) state, the core depletion process and End of Equilibrium Cycle (EOEC) state were simulated. The obtained results confirm that the prepared models are appropriate, as the majority of the obtained results is in agreement with the Benchmark data single standard deviation.