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

<table class="table-group" id="tab3"><tr><td><table class="table"><tr><td class="thead-hr" colspan="2"><hr/></td></tr><tr class="thead"><td class="align_left">Nuclide</td><td class="align_center">Density (barn-cm)</td></tr><tr><td class="thead-hr" colspan="2"><hr/></td></tr><tr><td class="align_left">Al</td><td class="align_center">3.1633<i>e</i> − 2</td></tr><tr><td class="align_left">Si</td><td class="align_center">7.2719<i>e</i> − 3</td></tr><tr><td class="align_left"><sup>235</sup>U</td><td class="align_center">2.1763<i>e</i> − 3</td></tr><tr><td class="align_left"><sup>238</sup>U</td><td class="align_center">8.7315<i>e</i> − 3</td></tr><tr class="table-tr"><td colspan="2"><hr class="tbody-hr"/></td></tr></table></td></tr></table>

<div>Nuclide information for the fuel pellet.</div>

Science and Technology of Nuclear Installations

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Table 3

Table 3: Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core 