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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 4
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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 4
System fault tree with the top event “no emergency ventilation.”
Basic event
Components failure identification
Probability
1
No signal
8.300 × 10
−4
2
Human error
1.000 × 10
−2
3
Filters fail
3.440 × 10
−4
4
Air pump
F
failed
2.270 × 10
−3
5
Two valves (h) fail to open
1.680 × 10
−3
6
Loss of normal offsite power
1.000 × 10
−4
7
AC generator fails
2.790 × 10
−3
8
Diesel motor fails
8.200 × 10
−3
9
Switches fail stuck
3.200 × 10
−2