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 · J. Heat Transfer; (United States)

DOI:https://doi.org/10.1115/1.3248129· OSTI ID:6300244

Yueh, Yuh-Shan; Chieng, Ching-Chang

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 trangular, 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 x 10/sup 4/, 10/sup 5/, 2 x 10/sup 5/, and for laminar flow of Re--2400. Friction factor and heat transfer ceofficients 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.

• Research Organization: National Tsing Hua University, Hsinchu, Taiwan 300, Republic of China
• OSTI ID: 6300244
• Journal Information: J. Heat Transfer; (United States), Journal Name: J. Heat Transfer; (United States) Vol. 109:3; ISSN JHTRA
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210400* -- Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
BOUNDARY CONDITIONS
CANDU TYPE REACTORS
ENERGY TRANSFER
HEAT FLOW
HEAT TRANSFER
HEAVY WATER MODERATED REACTORS
NUSSELT NUMBER
PRESSURE TUBE REACTORS
REACTORS
REYNOLDS NUMBER
ROD BUNDLES
TEMPERATURE DISTRIBUTION
THERMAL REACTORS
TURBULENCE