A preliminary level-1 probabilistic safety assessment of the IRIS plant has been performed. The first focus is on five internal initiating events, such as primary system break (loss-of-coolant accident and steam generator tube rupture) and transients (secondary system line break and loss-of-off-site power). In this study, the event tree for each initiating event was developed and the fault tree analysis of the event tree headings was carried out. In particular, since one of the IRIS safety systems, the passive emergency heat removal system, is unique to the IRIS plant and its reliability is key to the core damage frequency evaluation, it received more extensive fault-tree development. Finally the dominant sequences that lead to severe accidents and the failures in the main and support systems are identified.
- Nuclear Engineering Division
Preliminary Probabilistic Safety Assessment of the IRIS Plant
- Views Icon Views
- Share Icon Share
- Search Site
Mizuno, YO, Ogura, K, Ninokata, H, & Conway, LE. "Preliminary Probabilistic Safety Assessment of the IRIS Plant." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 2. Arlington, Virginia, USA. April 14–18, 2002. pp. 517-523. ASME. https://doi.org/10.1115/ICONE10-22095
Download citation file: