Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core

<table class="table-group" id="tab7"><tr><td><table class="table"><tr><td class="thead-hr" colspan="2"><hr/></td></tr><tr class="thead"><td class="align_left">Number</td><td class="align_center"><i>k</i><sub>eff</sub> ± 95% CI</td></tr><tr><td class="thead-hr" colspan="2"><hr/></td></tr><tr><td class="align_left">1</td><td class="align_center">1.59693 ± 0.00126</td></tr><tr><td class="align_left">2</td><td class="align_center">1.59539 ± 0.00112</td></tr><tr><td class="align_left">3</td><td class="align_center">1.59164 ± 0.00119</td></tr><tr><td class="align_left">4</td><td class="align_center">1.58958 ± 0.00131</td></tr><tr><td class="align_left">5</td><td class="align_center">1.58662 ± 0.00134</td></tr><tr><td class="align_left">6</td><td class="align_center">1.59010 ± 0.00105</td></tr><tr><td class="align_left">7</td><td class="align_center">1.58651 ± 0.00117</td></tr><tr><td class="align_left">8</td><td class="align_center">1.58463 ± 0.00116</td></tr><tr class="table-tr"><td colspan="2"><hr class="tbody-hr"/></td></tr></table></td></tr></table>

<div>The <i>k</i><sub>eff</sub> results of each group.</div>

Science and Technology of Nuclear Installations

tab7

Table 7

Table 7: Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core 