International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17)

Numerical simulation of hydraulics and heat transfer in the BREST-OD-300 LFR fuel assembly

26 Jun 2017, 13:00

20m

Room 6 (Yekaterinburg)

ORAL Track 6. Test Reactors, Experiments and Modeling and Simulations 6.1 CFD and 3D Modeling

Speaker

Dr Dmitry Fomichev (JSC NIKIET)

Description

This paper presents an analysis of hydraulic and heat transfer phenomena in a lead coolant flow in a fuel assembly (FA) of the BREST-OD-300 reactor core central subzone based on CFD simulations (RANS) using the STAR-CCM+ code. Based on the simulation results, coolant pressure, velocity and temperature fields, and the fuel cladding temperature distribution have been obtained. The FA design comprises a pin bundle (p/d = 1.38) with spacer grids, and the outer shroud has been eliminated. The influence of the FA design features on the hydraulic characteristics and the cladding temperature distribution has been shown. The CFD model was validated on experimental data on the hydraulic characteristics of a full-scale FA model. A good agreement has been shown between calculated and experimental data on the pressure drop both for the FA parts (head, pin bundle and tail) and for the FA as the whole.

Country/Int. Organization

Russia / JSC N.A. Dollezhal Research and Development Institute of Power Engineering (JSC "NIKIET")

Presentation materials

Material

paper548_fomichev_eng_final.docx