Studies of turbulent coolant mixing flows in the new generation reactors

Abstract

Due to studying of the flow parameters in the downcomer the bottom plenum of the nuclear reactor can be carried out with the help of CFD programs, the work is devoted to experimental researches in the field of pressurized water reactor with the purpose of creation of benchmarks for verification of domestic codes of computational hydrodynamics. Such data must have high spatial resolution, high resolution and high accuracy of the measurements. It makes necessary to apply complex experimental methodologies, measurement instrumentation and careful adjustment of experimental methodology. So a brief description of the experimental stand and its research methodology is given. A spatial conductometric measuring system that allows to study the processes of turbulent mixing of flows in the complex geometry of the nuclear reactor is presented. The description of experimental research and their results are presented. Conclusions are drawn about the prospects of using spatial conductometry as a vortex-resolving measurement method.

CFD Modeling of Heat Exchanger with Small Bent Radius Coils Using Porous Media Model

“…R.E. Alekseev (Nizhny Novgorod, Russia), an experimental thermophysical facility FT-40 [2,3] was created to study the processes of mixing non-isothermal flows of water coolant in models of equipment for nuclear power plants. This research facility is universal and multifunctional, which causes periodic changes in both its operating modes and the design of working sections, as well as the requirements for accuracy in maintaining the specified thermophysical parameters of the working environment.…”