Turbulence modeling of axial flow in a bare rod bundle

Journal Article · Wed Oct 31 23:00:00 EST 1979 · J. Heat Transfer; (United States)

DOI:https://doi.org/10.1115/1.3451048· OSTI ID:5664326

Bartzis, J G; Todreas, N E

Temperature distribution within the rod bundle of a nuclear reactor is of major importance in nuclear reactor design. However temperature information presupposes knowledge of the hydrodynamic behavior of the coolant which is the most difficult part of the problem due to the complexity of the turbulence phenomena. In the present work a two equation turbulence model (a strong candidate for analyzing actual three dimensional turbulent flows) has been used to predict fully developed flow of infinite bare rod bundles of various aspect ratios (P/D). The model has been modified to take into account anisotropic effects of eddy viscosity. Secondary flow calculations have been also performed although the model seems to be too rough to predict the secondary flow correctly. Heat transfer calculations have been performed to confirm the importance of anisotropic viscosity in temperature predictions. Experimental measurements of the distribution of axial velocity, turbulent axial velocity, turbulent kinetic energy and radial Reynolds stresses were performed in the developing and fully developed regions. A two channel Laser Doppler Anemometer working in the reference mode with forward scattering was used to perform the measurements in a simulated interior subchannel of a triangular rod array with P/D=1.124. Comparisons between the analytical results and the results of this experiment as well as other experimental data in rod bundle arrays available in the literature are presented. The predictions are in good agreement with the results for high Reynolds numbers.

• Research Organization: Department of Nuclear Engineering, Massachusetts Institute of Technology, Cambridge, MA 02139
• OSTI ID: 5664326
• Journal Information: J. Heat Transfer; (United States), Journal Name: J. Heat Transfer; (United States) Vol. 101:4; ISSN JHTRA
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220300* -- Nuclear Reactor Technology-- Fuel Elements
ANISOTROPY
BOUNDARY CONDITIONS
ENERGY TRANSFER
FLUID FLOW
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
FUEL ELEMENTS
FUEL RODS
HEAT TRANSFER
MATHEMATICAL MODELS
NUMERICAL SOLUTION
REACTOR COMPONENTS
REYNOLDS NUMBER
TEMPERATURE DISTRIBUTION
TURBULENCE
TURBULENT FLOW
VISCOSITY