Analysis of Void Fraction Distribution and Departure from Nucleate Boiling in Single Subchannel and Bundle Geometries Using Subchannel, System, and Computational Fluid Dynamics Codes

<table class="table-group" id="tab5"><tr><td><table class="table"><tr><td class="thead-hr" colspan="2"><hr/></td></tr><tr class="thead"><td align="left">Spacer type</td><td align="center">Loss Coefficient</td></tr><tr><td class="thead-hr" colspan="2"><hr/></td></tr><tr><td align="left">Simple spacer (SS)</td><td align="center">0.4</td></tr><tr><td align="left">Nonmixing vanes spacer (NMV)</td><td align="center">0.7</td></tr><tr><td align="left">Mixing vanes spacer (MV)</td><td align="center">1.0</td></tr><tr class="table-tr"><td colspan="2"><hr class="tbody-hr"/></td></tr></table></td></tr></table>

Bundle average spacer pressure loss coefficients [<a href="/journals/stni/2012/746467/#B2">2</a>].

Science and Technology of Nuclear Installations

tab5

Table 5

Table 5: Analysis of Void Fraction Distribution and Departure from Nucleate Boiling in Single Subchannel and Bundle Geometries Using Subchannel, System, and Computational Fluid Dynamics Codes 

Table 5 | Analysis of Void Fraction Distribution and Departure from Nucleate Boiling in Single Subchannel and Bundle Geometries Using Subchannel, System, and Computational Fluid Dynamics Codes 