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

<div>(a)Ssystem fault tree with the top event “no reactor pool isolation.” (b) System fault tree for “butterfly valve fails to close” with the top event “no reactor pool isolation”.</div>

Science and Technology of Nuclear Installations

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Figure 11

Figure 11: 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 

Figure 11 | 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 