Science and Technology of Nuclear Installations / 2021 / Article / Tab 14 / 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 14 Uncertainty values for the fault trees.
Fault tree FREQ/Year Mean Median 95TH Minimum Maximum Std Dev CI 1.440 × 10−5 1.440 × 10−5 1.440 × 10−5 1.440 × 10−5 1.440 × 10−5 1.440 × 10−5 0.000 ECCS 1.024 × 10−2 1.024 × 10−2 1.024 × 10−2 1.024 × 10−2 1.024 × 10−2 1.024 × 10−2 0.000 NCHR 1.001 × 10−2 1.001 × 10−2 1.001 × 10−2 1.001 × 10−2 1.001 × 10−2 1.001 × 10−2 2.248 × 10−9 NEV (FB) 4.291 × 10−3 4.291 × 10−3 4.291 × 10−3 4.291 × 10−3 4.291 × 10−3 4.291 × 10−3 0.000 NEV (LOCA) 4.531 × 10−3 4.531 × 10−3 4.531 × 10−3 4.531 × 10−3 4.531 × 10−3 4.531 × 10−3 1.384 × 10−9 PHR 4.848 × 10−4 4.848 × 10−4 4.848 × 10−4 4.848 × 10−4 4.848 × 10−4 4.848 × 10−4 4.930 × 10−11 RPI 1.010 × 10−3 1.010 × 10−3 1.010 × 10−3 1.010 × 10−3 1.010 × 10−3 1.010 × 10−3 2.974 × 10−10 RPS (LOCA) 3.286 × 10−3 3.286 × 10−3 3.286 × 10−3 3.286 × 10−3 3.286 × 10−3 3.286 × 10−3 0.000
