An experimental correlation of cross-flow pressure drop for triangular array wire-wrapped rod assemblies

Journal Article · Sun Feb 01 04:00:00 EST 1987 · Nucl. Technol.; (United States)

OSTI ID:5012263

Suh, K Y; Todreas, N E

An experimental study was carried out to quantitatively estimate the lateral drag changes due to flow structure alteration caused by the presence of wirewrap spacers in liquid-metal fast breeder reactor rod assemblies. Specially designed test rod bundles were constructed employing vertical straight wires attached at various angles around the rods relative to the cross-flow direction. These bundles simulate the cross-flow pressure drop within a control volume with axial mesh size less than one-twelfth of wire-wrap lead length. The variables examined were wire angular positions, Reynolds number, and rod arrangements. The transverse pressure drop data for triangular-array rod bundles with wires have been correlated throughout the laminar and turbulent flow regimes. The correlation is in the form of a correction parameter to be applied to the friction factor-Reynolds number relationship for the corresponding bare rod bundle.

• Research Organization: Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 77 Massachusetts Ave., Cambridge, MA (US)
• OSTI ID: 5012263
• Journal Information: Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 76:2; ISSN NUTYB
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
BREEDER REACTORS
DRAG
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
FLUID MECHANICS
FRICTION FACTOR
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
PRESSURE DROP
REACTORS
REYNOLDS NUMBER
ROD BUNDLES