INVESTIGATIONS OF FLUID FLOW WITHIN A 37-ELEMENT CANDU FUEL BUNDLE IN A NORMAL AND A DEFORMED PRESSURE TUBE
13th International Conference on CANDU Fuel - 2016 Aug. 15-18


Presented at:
13th International Conference on CANDU Fuel
2016 Aug. 15-18
Location:
Kingston, ON Canada
Session Title:
Session 9: Modelling & Computer Code Development - Aging and Deformation

Authors:
M. Piro (Canadian Nuclear Laboratories)
F. Wassermann (Darmstadt University)
M. Bruschewski (Darmstadt University)
D. Freudenhammer (Darmstadt University)
S. Grundmann (University of Rostock)
J. Kim (Los Alamos National Laboratory)
M. Christon (Altair Engineering)
M. Berndt (Los Alamos National Laboratory)
C. Azih (Canadian Nuclear Laboratories)
C. Tropea (Darmstadt University)
  

Abstract

The current work presents investigations of two scenarios involving fluid flow through a 37-element CANDU nuclear fuel bundle residing within either a normal or a deformed pressure tube simulating end-of-life diametral creep. Computational Fluid Dynamic simulations were performed for both scenarios with the HYDRA-TH code, which captured turbulent behaviour using implicit large eddy simulation. Numerical predictions compared well to concurrent experimental measurements based on Magnetic Resonance Velocimetry. Together, numerical and experimental results provided greater understanding of the evolution of geometry-induced inter-subchannel mixing and the effects of obstructive debris on the local flow field, as well as quantification of changes in flow distribution as a result of flow bypass. These capabilities are not possible with conventional experimental techniques or thermal-hydraulic codes. The overall goal of this work is to continue developing experimental and computational capabilities for further investigations that reliably support nuclear reactor performance and safety.

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