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="tab5"><tr><td><table class="table"><tr><td class="thead-hr" colspan="3"><hr/></td></tr><tr class="thead"><td class="align_left">Basic event</td><td class="align_center">Components failure identification</td><td class="align_center">Probability</td></tr><tr><td class="thead-hr" colspan="3"><hr/></td></tr><tr><td class="align_left">1</td><td class="align_center">Flapper fails to open (stuck)</td><td class="align_center">1.440 × 10<sup>−5</sup></td></tr><tr><td class="align_left">2</td><td class="align_center">Wrong weight</td><td class="align_center">1.000 × 10<sup>−2</sup></td></tr><tr class="table-tr"><td colspan="3"><hr class="tbody-hr"/></td></tr></table></td></tr></table>

<div>System fault tree with top event “natural circulation heat removal failure.”</div>

Science and Technology of Nuclear Installations

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Table 5

Table 5: 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 5 | 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 