Home / Publications / Journals / Nuclear Technology / Volume 76 / Number 2
Nuclear Technology / Volume 76 / Number 2 / February 1987 / Pages 229-240
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT87-A33877
Articles are hosted by Taylor and Francis Online.
An experimental study was carried out to quantitatively estimate the lateral drag changes due to flow structure alteration caused by the presence of wire-wrap 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.