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Science and Technology of Nuclear Installations
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Science and Technology of Nuclear Installations
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2021
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Article
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Tab 6
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Research Article
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 6
System fault tree with top event “emergency core cooling system failure.”
Basic event
Components failure identification
Probability
1
Hole in hose
1.200 × 10
−4
2
Operator fails to connect hose
1.000 × 10
−2
3
Water valves fail stuck closed
3.600 × 10
−6
4
No water in the tank
1.020 × 10
−4