Steady-State Thermal-Hydraulic Analysis of the LEU-Fueled Dalat Nuclear Research Reactor

<table class="table-group" id="tab2"><tr><td><table class="table"><tr><td class="thead-hr" colspan="2"><hr/></td></tr><tr class="thead"><td class="align_left">Hot channel factors</td><td class="align_center">Value</td></tr><tr><td class="thead-hr" colspan="2"><hr/></td></tr><tr><td class="align_left">Uncertainty in heat flux</td><td class="align_center">1.17</td></tr><tr><td class="align_left">Uncertainty in bulk coolant temperature rise</td><td class="align_center">1.34</td></tr><tr><td class="align_left">Uncertainty in film temperature rise</td><td class="align_center">1.21</td></tr><tr><td class="align_left">Uncertainty in power measurement</td><td class="align_center">1.05</td></tr><tr><td class="align_left">Uncertainty in flow measurement</td><td class="align_center">1.02</td></tr><tr><td class="align_left">Uncertainty in heat transfer coefficient</td><td class="align_center">1.15</td></tr><tr class="table-tr"><td colspan="2"><hr class="tbody-hr"/></td></tr></table></td></tr></table>

<div>Hot channel factors in thermal hydraulic analysis of the DNRR.</div>

Science and Technology of Nuclear Installations

tab2

Table 2

Table 2: Steady-State Thermal-Hydraulic Analysis of the LEU-Fueled Dalat Nuclear Research Reactor 