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" width="800px"><tr class="fig-image" id="a"><td><img alt="746467.fig.0012a" src="https://static.hindawi.com/articles/stni/volume-2012/746467/figures/746467.fig.0012a.jpg"/></td></tr><tr class="fig-caption"><td align="center"><table><tr><td><b>(a) </b>Overview of TRACE Model</td></tr></table></td></tr><tr class="fig-image" id="b"><td><img alt="746467.fig.0012b" src="https://static.hindawi.com/articles/stni/volume-2012/746467/figures/746467.fig.0012b.jpg"/></td></tr><tr class="fig-caption"><td align="center"><table><tr><td><b>(b) </b>Top-down view of test section</td></tr></table></td></tr></table>

Science and Technology of Nuclear Installations

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Figure 12

Figure 12: Analysis of Void Fraction Distribution and Departure from Nucleate Boiling in Single Subchannel and Bundle Geometries Using Subchannel, System, and Computational Fluid Dynamics Codes 

Figure 12 | Analysis of Void Fraction Distribution and Departure from Nucleate Boiling in Single Subchannel and Bundle Geometries Using Subchannel, System, and Computational Fluid Dynamics Codes 