Laminar natural convection heat transfer from vertical 7 × 7 rod bundle in liquid sodium was numerically analyzed to optimize the thermal–hydraulic design for the bundle geometry with equilateral square array (ESA). The unsteady laminar three-dimensional basic equations for natural convection heat transfer caused by a step heat flux were numerically solved until the solution reaches a steady-state. The code of the parabolic hyperbolic or elliptic numerical integration code series (PHOENICS) was used for the calculation considering the temperature dependence of thermophysical properties concerned. The 7 × 7 heated rods for diameter (D = 0.0076 m), length (L = 0.2 m) and L/D (=26.32) were used in this work. The surface heat fluxes for each cylinder, which was uniformly heated along the length, were equally given for a modified Rayleigh number, (Raf,L)ij and (Raf,L)Nx×Ny,S/D, ranging from 3.08 × 104 to 4.28 × 107 (q = 1 × 104∼7 × 106 W/m2) in liquid temperature (TL = 673.15 K). The values of ratio of the diagonal center-line distance between rods for bundle geometry to the rod diameter (S/D) for vertical 7 × 7 rod bundle were ranged from 1.8 to 6 on the bundle geometry with ESA. The spatial distribution of average Nusselt numbers for a vertical single cylinder of a rod bundle, (Nuav)ij, and average Nusselt numbers for a vertical rod bundle, (Nuav,B)Nx×Ny,S/D, were clarified. The average values of Nusselt number, (Nuav)ij and (Nuav,B)Nx×Ny,S/D, for the bundle geometry with various values of S/D were calculated to examine the effect of array size, bundle geometry, S/D, (Raf,L)ij and (Raf,L)Nx×Ny,S/D on heat transfer. The bundle geometry for the higher (Nuav,B)Nx×Ny,S/D value under the condition of S/D = constant was examined. The general correlations for natural convection heat transfer from a vertical Nx×Ny rod bundle with the ESA and equilateral triangle array (ETA), including the effects of array size, (Raf,L)Nx×Ny,S/D and S/D were derived. The correlations for vertical Nx×Ny rod bundles can describe the theoretical values of (Nuav,B)Nx×Ny,S/D for each bundle geometry in the wide analytical range of S/D (=1.8–6) and the modified Rayleigh number ((Raf,L)Nx×Ny,S/D = 3.08 × 104 to 4.28 × 107) within −9.49 to 10.6% differences.
Skip Nav Destination
Article navigation
April 2019
Research-Article
Laminar Natural Convection Heat Transfer From Vertical 7 × 7 Rod Bundles in Liquid Sodium
Koichi Hata,
Koichi Hata
Graduate School of Maritime Sciences,
Kobe University,
5-1-1, Fukae-minami,
Kobe, Hyogo 658-0022, Japan
e-mail: hatako1@people.kobe-u.ac.jp
Kobe University,
5-1-1, Fukae-minami,
Kobe, Hyogo 658-0022, Japan
e-mail: hatako1@people.kobe-u.ac.jp
Search for other works by this author on:
Katsuya Fukuda,
Katsuya Fukuda
Graduate School of Maritime Sciences,
Kobe University,
Kobe, Hyogo 658-0022, Japan
Kobe University,
5-1-1, Fukae-minami
,Kobe, Hyogo 658-0022, Japan
Search for other works by this author on:
Tohru Mizuuchi
Tohru Mizuuchi
Institute of Advanced Energy,
Kyoto University Gokasho,
Uji, Kyoto 611-0011, Japan
Kyoto University Gokasho,
Uji, Kyoto 611-0011, Japan
Search for other works by this author on:
Koichi Hata
Graduate School of Maritime Sciences,
Kobe University,
5-1-1, Fukae-minami,
Kobe, Hyogo 658-0022, Japan
e-mail: hatako1@people.kobe-u.ac.jp
Kobe University,
5-1-1, Fukae-minami,
Kobe, Hyogo 658-0022, Japan
e-mail: hatako1@people.kobe-u.ac.jp
Katsuya Fukuda
Graduate School of Maritime Sciences,
Kobe University,
Kobe, Hyogo 658-0022, Japan
Kobe University,
5-1-1, Fukae-minami
,Kobe, Hyogo 658-0022, Japan
Tohru Mizuuchi
Institute of Advanced Energy,
Kyoto University Gokasho,
Uji, Kyoto 611-0011, Japan
Kyoto University Gokasho,
Uji, Kyoto 611-0011, Japan
Manuscript received August 24, 2017; final manuscript received December 9, 2018; published online March 15, 2019. Editor: Igor Pioro.
ASME J of Nuclear Rad Sci. Apr 2019, 5(2): 021002 (15 pages)
Published Online: March 15, 2019
Article history
Received:
August 24, 2017
Revised:
December 9, 2018
Citation
Hata, K., Fukuda, K., and Mizuuchi, T. (March 15, 2019). "Laminar Natural Convection Heat Transfer From Vertical 7 × 7 Rod Bundles in Liquid Sodium." ASME. ASME J of Nuclear Rad Sci. April 2019; 5(2): 021002. https://doi.org/10.1115/1.4042356
Download citation file:
Get Email Alerts
Cited By
Estimation of Turbulent Mixing Factor and Study of Turbulent Flow Structures in Pressurized Water Reactor Sub Channel by Direct Numerical Simulation
ASME J of Nuclear Rad Sci (April 2025)
Heat Flux Correlations for Condensation From Steam and Air Mixtures on Vertical Flat Plates
ASME J of Nuclear Rad Sci (April 2025)
Radiation Monitoring for Volatilized Zinc Contamination Using Gamma-Ray Imaging and Spectroscopy
ASME J of Nuclear Rad Sci (April 2025)
Related Articles
Natural Convection Heat Transfer From Vertical 5 × 5 Rod Bundles in Liquid Sodium
J. Heat Transfer (March,2017)
A Natural Convection Model for the Rate of Salt Deposition From
Near-Supercritical, Aqueous Solutions
J. Heat Transfer (December,2003)
Sub-Channel Analysis of a Hexagonal Sub-Assembly: Influence of Blockage and Axial Power Distribution on Critical Heat Flux
J. Thermal Sci. Eng. Appl (December,2021)
On Gaseous Free-Convection Heat Transfer With Well-Defined Boundary Conditions
J. Heat Transfer (November,2000)
Related Chapters
Applications
Introduction to Finite Element, Boundary Element, and Meshless Methods: With Applications to Heat Transfer and Fluid Flow
Cooling of Steel Spherical Balls by Natural Convection and Radiation Heat Transfer in Unsteady State
Electromagnetic Waves and Heat Transfer: Sensitivites to Governing Variables in Everyday Life
Minimizing On-Site Septic System Drain Field Size by Combining Absorbic and Evaporative Disposal Methods
Site Characterization and Design of On-Site Septic Systems