Science and Technology of Nuclear Installations

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 1

Description of basic events and probabilities for the reactor protection system (RPS).
Basic eventComponents failure identificationProbability
1Failure of all 8 rods2.280 × 10−6
2Failure of electromagnets to engage2.920 × 10−6
3NOR no electric power9.999 × 10−1
4Gate slow scram fails6.970 × 10−4
5Relay T3 stuck closed6.970 × 10−4
6Sensor fails to give a signal2.350 × 10−2
7Relay T1 fails to open6.970 × 10−4
8No electric power2.790 × 10−6
9Human error1.000 × 10−2
10Sensor T2 fails2.350 × 10−2
11Relay T2 fails6.970 × 10−4
12Sensor fails to give a signal2.350 × 10−2