Experimental and Numerical Investigation of Temperature Distribution on Reactor Pressure Vessel Support under Operating Conditions

<table class="fixed-width table-group" id="tab3"><tr><td><table class="table"><colgroup><col style="width:11.88em"/><col style="width:25.72em"/></colgroup><tr><td class="thead-hr" colspan="2"><hr/></td></tr><tr class="thead"><td class="align_left">Boundary conditions</td><td class="align_center">Values</td></tr><tr><td class="thead-hr" colspan="2"><hr/></td></tr><tr><td class="align_left">Air inlet</td><td class="align_center">Velocity-Inlet (Velocity 3-9 m/s, temperature 25-40°C)</td></tr><tr><td class="align_left">Air outlet</td><td class="align_center">Pressure-Outlet</td></tr><tr><td class="align_left">Heating area</td><td class="align_center">Fixed temperature 287°C</td></tr><tr><td class="align_left">Support symmetry surface</td><td class="align_center">Symmetrical</td></tr><tr><td class="align_left">Support outside surface</td><td class="align_center">Heat convection (Natural convection in an infinite space [<a href="/journals/stni/2019/1217073/#B23" target="_blank">23</a>])</td></tr><tr class="table-tr"><td colspan="2"><hr class="tbody-hr"/></td></tr></table></td></tr></table>

<div>The boundary conditions of calculation model.</div>

Science and Technology of Nuclear Installations

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Table 3

Table 3: Experimental and Numerical Investigation of Temperature Distribution on Reactor Pressure Vessel Support under Operating Conditions 