THERMO-HYDRAULIC ANALYSIS OF FUEL ASSEMBLY OF NUCLEAR REACTOR VVER 440
22nd Symposium of AER on VVER Reactor Physics and Reactor Safety (2012, Průhonice, Czech Republic)
CFD CODES APPLICATION
Abstract
The paper deals with CFD modeling and simulation of coolant flow in fuel assembly of
nuclear reactor VVER 440. Geometry of fuel assembly and thermocouple housing with
channel in upper core supporting plate have been created in 3D CAD system, where detailed
geometry model was simplified. The discretization of geometry was realized in ANSYS
ICEM CFD software, where blocking strategy was used. ANSYS CFX was chosen as a main
CFD software tool, where all analyses were performed. Also the flow of coolant in central
tube as well as heat transfer across the wall of central tube were considered in the model.
Only steady-state analyses are performed. Generated thermal power in fuel rods is prescribed
individually for each rod with axial distribution of power. In analyses, there is investigated the
influence of volume flow for defined thermal power on fuel assembly output temperature.
Also the influence of thermal power and volume flow on pressure drop is investigated.
Different turbulent models and mesh densities are examined.