On the calculation of flow and heat transfer characteristics for CANDU-type 19-rod fuel bundles

Journal Article · Sat Aug 01 04:00:00 EDT 1987 · Journal of Heat Transfer (Transactions of the ASME (American Society of Mechanical Engineers), Series C); (United States)

DOI:https://doi.org/10.1115/1.3248129· OSTI ID:6243300

Yueh, Yuhshan; Chieng, Chingchang ^[1]

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1. National Tsing Hua Univ., Hsinchu (Taiwan)

A numerical study is reported of flow and heat transfer in a CANDU-type 19 rod fuel bundle. The flow domain of interest includes combinations of triangular, square, and peripheral subchannels. The basic equations of momentum and energy are solved with the standard k-{epsilon} model of turbulence. Isotropic turbulent viscosity is assumed and no secondary flow is considered for this steady-state, fully developed flow. Detailed velocity and temperature distributions with wall shear stress and Nusselt number distributions are obtained for turbulent flow of Re = 4.35 {times} 10{sup 4}, 10{sup 5}, 2 {times} 10{sup 5}, and for laminar flow of Re {approximately} 2,400. Friction factor and heat transfer coefficients of various subchannels inside the full bundle are compared with those of infinite rod arrays of triangular or square arrangements. The calculated velocity contours of peripheral subchannel agreed reasonably with measured data.

• OSTI ID: 6243300
• Journal Information: Journal of Heat Transfer (Transactions of the ASME (American Society of Mechanical Engineers), Series C); (United States), Journal Name: Journal of Heat Transfer (Transactions of the ASME (American Society of Mechanical Engineers), Series C); (United States) Vol. 109:3; ISSN 0022-1481; ISSN JHTRA
• Country of Publication: United States
• Language: English

Related Subjects

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42 ENGINEERING
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CANDU TYPE REACTORS
ENERGY TRANSFER
FLUID FLOW
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
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HEAVY WATER MODERATED REACTORS
NUMERICAL SOLUTION
PRESSURE TUBE REACTORS
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TEMPERATURE DISTRIBUTION
THERMAL REACTORS
VELOCITY