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) System fault tree with top event “reactor protection system failure” in LOCA. (b) System fault tree for “no signal” with top event “reactor protection system failure” in LOCA.</div>

Science and Technology of Nuclear Installations

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Figure 6

Figure 6: 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 6 | 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 