Title: An Overview of Main Impact on PRA Tasks in Order to Model Ageing Effects
Other Contributors: SERBANESCU DAN
Citation: Proceedings of EC Enlargement and Integration Workshop on Use of Probabilistic Safety Assessment (PSA) for Evaluation of Impact of Ageing Effects on the Safety of Nuclear Power Plants
Publisher: EC-JRC-IE
Publication Year: 2006
JRC N°: JRC34810
URI: http://publications.jrc.ec.europa.eu/repository/handle/JRC34810
Type: Articles in periodicals and books
Abstract: This presentation discusses the implications on the individual tasks when performing a Probabilistic Safety/Risk Assessment (PSA/PRA) in order to model ageing effects. The discussion deals with the following aspects: 1) PRA/PSA data issues: - Initiating events (updating of Initiating Events (IE) frequencies and definitions) - Active components (choice of reliability models and parameters estimation) - Passive components (physical reliability models development) - Common Cause Failures (CCF) (parameters, intersystem failures) 2) PRA/PSA Tasks: - PRA/PSA main assumptions and inputs from the deterministic analyses and operation - List of Initiating Events and evaluation of their frequencies - Event Trees construction and definition of Success Criteria for the Fault Tree Analysis - Fault Tree Analysis - Integration of Fault Trees into Event Trees - Sensitivity and Uncertainty Analysis for PRA level 1 - Containment Event Trees - Implementation of changes into the model to consider external/area events - PRA level 3 and risk calculations - Introducing changes for other modes of operation and all radioactive sources - Sensitivity / uncertainty analysis for PRA - Review of results and preparation for their use into the decision making process, design optimization and other applications.
JRC Directorate:Energy, Transport and Climate

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