Validation of the Serpent2 code for the VR-1 reactor core calculation

Abstract

The VR-1 reactor core safety characteristics calculations are performed by standardized MCNP code, however due to license requirements, it is desired to replace it by the Serpent2 code. In order to do that, Serpent2 calculation must be standardized by State office of nuclear safety. Comparison of Serpent2 and MCNP multiplication factors for several reactor cores is presented to demonstrate the capability and accuracy of Serpent2 results. In addition to this, Serpent2 calculation setup is tested and the impact of different nuclear data libraries is examined. The comparison of results from Serpent2 and standardized MCNP calculation proved that results are similar and therefore the Serpent2 code can be used for the VR-1 reactor core calculations, especially for criticality predictions.