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The Application of Probabilistic Safety Assessment in the Preliminary Reactor Design Stage: Challenges and Insights

[+] Author Affiliations
Ibrahim A. Alrammah

University of Manchester, Manchester, UK

Paper No. ICONE22-31284, pp. V003T06A059; 6 pages
  • 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
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-4593-6
  • Copyright © 2014 by ASME


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.

Copyright © 2014 by ASME



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