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

<table class="table-group" id="tab5"><tr><td><table class="table"><tr><td class="thead-hr" colspan="2"><hr/></td></tr><tr class="thead"><td class="align_left">Temperature (K)</td><td class="align_center">ID extension</td></tr><tr><td class="thead-hr" colspan="2"><hr/></td></tr><tr><td class="align_left">293</td><td class="align_center">00.32t</td></tr><tr><td class="align_left">323</td><td class="align_center">01.32t</td></tr><tr><td class="align_left">373</td><td class="align_center">02.32t</td></tr><tr><td class="align_left">423</td><td class="align_center">03.32t</td></tr><tr class="table-tr"><td colspan="2"><hr class="tbody-hr"/></td></tr></table></td></tr></table>

<div>The variations of neutron scattering cross-sections with temperature in coolant.</div>

Science and Technology of Nuclear Installations

tab5

Table 5

Table 5: Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core 