Investigations for edge region of a fuel assembly

VVER-1200 NPP (Nuclear Power Plant) is a 3+ generation Russian designed PWR (Pressurized Water Reactor). This type of NPPs will be built to increase the capacity of Paks NPP. In our paper the impact of the mixing vane of VVER-1200 spacers on the flow is examined. Distribution of velocity, temperature field and cross-flows are evaluated. For these investigations detailed calculation models have been developed with the ANSYS CFX code. A mesh sensitivity analysis is performed using three meshes of different resolutions. The impacts of the spacer orientations and arrangements on the mixing between two fuel assemblies are analyzed.