Analysis and Estimation of Core Damage Frequency of Flow Blockage and Loss of Coolant Accident: A Case Study of a 10 MW Water-Water Research Reactor-PSA Level 1

<table class="table-group" id="tab10"><tr><td><table class="table"><tr><td class="thead-hr" colspan="3"><hr/></td></tr><tr class="thead"><td class="align_left">Event tree</td><td class="align_center">Frequency of releases (SAPHIRE 7.0)</td><td class="align_center">Sequences</td></tr><tr><td class="thead-hr" colspan="3"><hr/></td></tr><tr><td class="align_left">ET1</td><td class="align_center">2.979 × 10<sup>−6</sup></td><td class="align_center">#9</td></tr><tr><td class="align_left">ET1</td><td class="align_center">2.562 × 10<sup>−5</sup></td><td class="align_center">#10</td></tr><tr><td class="align_left">ET1</td><td class="align_center">3.449 × 10<sup>−7</sup></td><td class="align_center">#11</td></tr><tr><td class="align_left">TOTAL</td><td class="align_center">2.894 × 10<sup>−5</sup></td><td class="align_center"> </td></tr><tr class="table-tr"><td colspan="3"><hr class="tbody-hr"/></td></tr></table></td></tr></table>

<div>Frequencies contributing most to core damage (30%).</div>

Science and Technology of Nuclear Installations

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Table 10

Table 10: Analysis and Estimation of Core Damage Frequency of Flow Blockage and Loss of Coolant Accident: A Case Study of a 10 MW Water-Water Research Reactor-PSA Level 1 

Table 10 | Analysis and Estimation of Core Damage Frequency of Flow Blockage and Loss of Coolant Accident: A Case Study of a 10 MW Water-Water Research Reactor-PSA Level 1 