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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 2
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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 2
System fault tree with top event “containment isolation”.
Basic event
Components failure identification
Probability
1
Gates of the ventilation system fails
1.010 × 10
−4
2
Doors fail to remain closed
1.440 × 10
−5
3
Air pump # 1 fails to stop
3.240 × 10
−4
4
Air pump # 2 fails to stop
3.240 × 10
−4
5
Air pump # 1 fails to stop
3.240 × 10
−4