Calculation and Analysis of the Source Term of the Reactor Core Based on Multivariate Analysis of Variance

<table class="table-group" id="tab1"><tr><td><table class="table"><tr><td class="thead-hr" colspan="2"><hr/></td></tr><tr class="thead"><td class="align_left">Name</td><td class="align_center">Number</td></tr><tr><td class="thead-hr" colspan="2"><hr/></td></tr><tr><td class="align_left">Number of fuel assembly</td><td class="align_center">157</td></tr><tr><td class="align_left">Arrangement of fuel rods</td><td class="align_center">17 × 17</td></tr><tr><td class="align_left">Number of fuel rods per assembly</td><td class="align_center">264</td></tr><tr><td class="align_left">Fuel rod spacing (cm)</td><td class="align_center">1.3</td></tr><tr><td class="align_left">Cross-sectional size (m)</td><td class="align_center">0.214 × 0.214</td></tr><tr><td class="align_left">Core fuel loading (kg)</td><td class="align_center">96084</td></tr><tr><td class="align_left">Number of guide tubes in each assembly</td><td class="align_center">24</td></tr><tr><td class="align_left">Guide tube material</td><td class="align_center">ZIRLO<sup>TM</sup></td></tr><tr><td class="align_left" rowspan="2">Central measuring tube size(cm)</td><td class="align_center">Internal diameter (1.12)</td></tr><tr><td class="align_center">External diameter (1.22)</td></tr><tr class="table-tr"><td colspan="2"><hr class="tbody-hr"/></td></tr></table></td></tr></table>

<div>Basic parameters of AP1000 fuel assembly.</div>

Science and Technology of Nuclear Installations

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Table 1

Table 1: Calculation and Analysis of the Source Term of the Reactor Core Based on Multivariate Analysis of Variance 