Today, probabilistic risk assessments (PRAs) at multi-unit nuclear power plants consider risk from each unit separately and do not formally consider combination events between the units. To gain an accurate view of a multi-unit site’s risk profile, the core damage frequency for the site, rather than the unit, should be considered. There are many types of events that could create a dependency between multiple units from a risk perspective. In order to effectively account for these risks in a multi-unit PRA, six main dependence classifications have been created: initiating events, shared connections, identical components, proximity dependencies, human dependencies, and organizational dependencies. This paper discusses these six classifications that could create dependence between multiple units. As a validation of the classification, this paper will also discuss multi-unit events that have occurred.
Skip Nav Destination
2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference
July 30–August 3, 2012
Anaheim, California, USA
Conference Sponsors:
- Nuclear Engineering Division
- Power Division
ISBN:
978-0-7918-4495-3
PROCEEDINGS PAPER
Initial Classification of Events to Consider in a Multi-Unit PRA
Suzanne Schroer,
Suzanne Schroer
University of Maryland, College Park, MD
Search for other works by this author on:
Mohammad Modarres
Mohammad Modarres
University of Maryland, College Park, MD
Search for other works by this author on:
Suzanne Schroer
University of Maryland, College Park, MD
Mohammad Modarres
University of Maryland, College Park, MD
Paper No:
ICONE20-POWER2012-54131, pp. 295-300; 6 pages
Published Online:
October 30, 2013
Citation
Schroer, S, & Modarres, M. "Initial Classification of Events to Consider in a Multi-Unit PRA." Proceedings of the 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference. Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance. Anaheim, California, USA. July 30–August 3, 2012. pp. 295-300. ASME. https://doi.org/10.1115/ICONE20-POWER2012-54131
Download citation file:
17
Views
Related Proceedings Papers
Related Articles
Moving Beyond Nondestructive Examination to Proactive Management of Materials Degradation
J. Pressure Vessel Technol (February,2012)
An Experimental Study of Assessment of Weld Quality on Fatigue Reliability Analysis of a Nuclear Pressure Vessel
J. Pressure Vessel Technol (November,1993)
Venturing to the Far Reaches
Mechanical Engineering (September,2005)
Related Chapters
Introduction
Risk Importance Measures in the Design and Operation of Nuclear Power Plants
QRAS Approach to Phased Mission Analysis (PSAM-0444)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
A Simplified Expert Elicitation Guideline (PSAM-0089)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)