3D neutronic analysis of VVER1000/V-320 using PARCS code

Due to the fact that Fukushima accident occurred, the European Commission decided to evaluate all European NPPs. The Research Centre Rez plans to simulate accident scenarios of NPP Temelin and NPP Dukovany in accordance with the stress tests conditions. While in a number of safety analysis of various accident scenarios is sufficient enough to use point kinetics, there are selected types of events in which is useful to model the 3D space behaviour of neutron kinetics. In particular control rod ejections, boron dilution scenarios, including transition between design basis and beyond design basis accidents. The main purpose of the presented work is to create a model of the active core of VVER1000/V320 reactor applicable for 3D modelling of neutron kinetics and its coupling with the thermo-hydraulic system codes, such as RELAP5/TRACE. Cross-section data was prepared with computation code SCALE 6.1.2/TRITON. PARCS 3.2 code uses homogenized cross-sections libraries to calculate core parameters of the PWR reactors.