Fuel assembly burnup calculations for VVER fuel assemblies with the MONTE CARLO code SERPENT

The Monte Carlo code SERPENT ( ) is tested and validated for different fuel configurations but not for VVER fuel assemblies with Gd fuel pins and enrichment profiling. The presentation outlines the results obtained during fuel assembly burnup calculations for VVER-440 and VVER-1000 reactor types with Gd fuel pins. The calculations follow the proposal of the benchmark for VVER-440 fuel assemblies specified by Mikolas at the 14 Symposium of AER in 2004. For fuel assemblies of VVER-1000 reactor types with Gd fuel pins a benchmark by the OECD/NEA was specified in 2002. A set of data for the further verification of the few group data preparation in the framework of the VVER-1000 reactor core burnup benchmark proposed at the 19 AER Symposium in 2009 is received and analysed. The results presented show sufficient agreement with the reference values.