CFD SIMULATION OF THERMAL PROCESSES IN VVER REACTORS. COMPARISON WITH THE EXPERIMENTAL DATA
24th Symposium of AER on VVER Reactor Physics and Reactor Safety (2014, Sochi, Russia)
Nuclear applications of computational fluid dynamics (CFD)
Abstract
CFD SIMULATION OF THERMAL PROCESSES IN VVER REACTORS. COMPARISON WITH THE EXPERIMENTAL DATA
Bikezin S.K., Oleksyuk D.A.
NRC “Kurchatov Institute”, Moscow, Russia
ABSTRACT
This presentation describes the computational work performed by CFD-code STAR- CCM + for VVER and comparing the results with experimental data obtained from the National Research Center “Kurchatov Institute” in recent years on various topics.
Intensification of heat and mass transfer. In NRC “Kurchatov Institute”, a large volume of experimental studies on the effectiveness of intensifiers grids of different types. Among the studied lattice models was developed at NRC “Kurchatov Institute”. The experimental results obtained can be used for verifying CFD-code. Conversely, using the CFD-code the optimization of the geometry of the grid-intensifier to reduce the coefficient of hydraulic resistance.
The estimated impact of structural changes in the head on the coolant mixing in the area from out of the bundle of fuel elements to the location of the thermocouple. In order to improve the strength characteristics of fuel assembly (FA) VVER-440 third generation was upgraded design of the head. To unify the design of the head bore planned to be make for second generation FA. Since 2003 in the NRC “Kurchatov Institute” work was carried out to study the mixing of coolant in the head RK VVER-440. Were performed as computational studies on CFD-codes, subchannel code SC-1 and experimental studies on a full-scale mixing model of second generation FA. Experimental studies have allowed a verification of computational models and calculations based on the correction functions to get the thermocouple for a number of NPPs.