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On numerical modelling of multiphase flows and heat transfer in nuclear fuel assemblies

Anglart H.

Prace Naukowe Politechniki Warszawskiej. Konferencje

2007

T. 1, z. 25

19-29

This paper presents the current methods used for the numerical modelling of multiphase flows and heat transfer in nuclear fuel assemblies. Special attention is devoted to the state-of-the-art Computational Fluid Dynamics (CFD) models and their application to prediction of velocity, temperature, pressure and turbulence intensity distributions in fuel assemblies with spacer grids. Such numerical methods require detailed experimental data for proper validation. In case of Boiling Water Reactor (BWR) applications one has to include the evaluation of phase distributions, since it affects the local moderator density, and thus the local reactivity in the fuel bundle. From a designer point of view the most interesting aspects include the evaluation of the influence of design details on the thermal and the nuclear performance of fuel assemblies.