This paper discusses some technical issues related to applying Probabilistic Safety Assessment (PSA) to a novel Nuclear Power Plant (NPP) design. These aspects include: initiating events, passive systems modeling, reliability and common-cause failure (CCF) data, modeling of novel design features, modeling of preventive maintenance and technical specifications, human reliability analysis (HRA), modeling of instrumentation and control (I&C), external hazards, PSA supporting studies and interpretation of PSA results for new plants.
- Nuclear Engineering Division
The Application of Probabilistic Safety Assessment in the Preliminary Reactor Design Stage: Challenges and Insights
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Alrammah, IA. "The Application of Probabilistic Safety Assessment in the Preliminary Reactor Design Stage: Challenges and Insights." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security. Prague, Czech Republic. July 7–11, 2014. V003T06A059. ASME. https://doi.org/10.1115/ICONE22-31284
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