Dispersed Two-Phase Flow Modelling for Nuclear Safety in the NEPTUNE_CFD Code

<table class="table-group" id="tab8"><tr><td><table class="table"><tr><td class="thead-hr" colspan="2"><hr/></td></tr><tr class="thead"><td class="align_left">Test case</td><td class="align_center">ASU</td></tr><tr><td class="thead-hr" colspan="2"><hr/></td></tr><tr><td class="align_left">Inlet mass flow rate (kg·m<sup>−2</sup>s<sup>−1</sup>)</td><td class="align_center">784</td></tr><tr><td class="align_left">Inlet temperature (°C)</td><td class="align_center">50.2</td></tr><tr><td class="align_left">Wall heat flux (W·m<sup>−2</sup>)</td><td class="align_center">95000</td></tr><tr><td class="align_left">Pressure (Pa)</td><td class="align_center">269000</td></tr><tr class="table-tr"><td colspan="2"><hr class="tbody-hr"/></td></tr></table></td></tr></table>

Experimental conditions retained for the ASU experiment.

Science and Technology of Nuclear Installations

tab8

Table 8

Table 8: Dispersed Two-Phase Flow Modelling for Nuclear Safety in the NEPTUNE_CFD Code 