CFD SIMULATION OF ROD BUNDLES
CNS 24th Nuclear Simulation Symposium - 2012 October 15-16


Presented at:
CNS 24th Nuclear Simulation Symposium
2012 October 15-16
Location:
Ottawa,Canada
Session Title:
Technical 7: Thermalhydraulics & Safety

Authors:
Krishna Podila (Atomic Energy of Canada Limited)
Joanne Bailey (Atomic Energy of Canada Limited)
Yanfei Rao (Atomic Energy of Canada Limited)
Matt Krause (Atomic Energy of Canada Limited)
  

Abstract

Atomic Energy of Canada (AECL) has initiated a program to develop Computational Fluid Dynamicscapability (CFD) to simulate single-phase and two-phase flow conditions in rod bundles.  This paper presents a comparative analysis of turbulence models available in commercial CFD programs for their use in nuclear thermalhydraulic applications.   The objective was accomplished using ANSYS FLUENT 6.3.26 for two geometries: a 5×5 bundle with split-type spacers and a 28-element bundle with appendages.   Apart from the  analysis of the two- and seven-equation models, superior predictive capabilities of  the  DES  (Detached Eddy Simulation)  and LES (Large Eddy Simulations) approaches were demonstrated for the 28-element uncrept CANDU fuel channel with appendages.

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