2:45 PM - 3:00 PM
[2C11] Development of Internal Flood Level 1 PRA Model for Light Water Reactor
Keywords:PRA, flood scenario, evet tree, fault tree, core damage frequency
Internal flood level 1 PRA methodologies were investigated for 4 loop PWR and ABWR. The results showed that the evaluation methodologies to estimate core damage frequencies were developed precisely and significant flood sources were secondary side pipes for 4 loop PWR and fire protection systems in the control building for ABWR.