Presentation of common cause failures in fault tree structure of Krsko PSA : an historical overview
Creators
- 1. Nuclear Power Plant Krsko, Krsko (Slovenia)
- 2. Faculty of Electrical Engineering and Computing, Zagreb (Croatia)
Description
Failure of multiple components due to a common cause represents one of the most important issues in evaluation of system reliability or unavailability. The frequency of such events has relatively low expectancy, when compared to random failures, which affect individual components. However, in many cases the consequence is a direct loss of safety system or mitigative safety function. For this reason, the modeling of a common cause failure (CCF) and its presentation in fault tree structure is of the uttermost importance in probabilistic safety analyses (PSA). During the past decade, PSA model of Krsko NPP has undergone many small changes and a couple of major ones in fulfilling its basic purpose, which was serving as a tool for providing an appropriate information on the risk associated with actual plant design and operation. All changes to Krsko PSA model were undertaken in order to make it a better tool and / or to make it represent the plant in more accurate manner. The paper provides an overview of changes in CCF modeling in the fault tree structure from the initial PSA model development till present. (author)
Files
36115780.pdf
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Additional details
Publishing Information
- Publisher
- Nuclear Society of Slovenia
- Imprint Place
- Ljubljana (Slovenia)
- ISBN
- 961-6207-21-0
- Imprint Title
- Proceedings of the International Conference Nuclear Energy for New Europe 2003
- Imprint Pagination
- 827 p.
- Journal Page Range
- [8 p.]
- Report number
- INIS-SI--05-001
Conference
- Title
- International Conference Nuclear Energy for New Europe 2003
- Dates
- 8-11 Sep 2003
- Place
- Portoroz (Slovenia)
INIS
- Country of Publication
- Slovenia
- Country of Input or Organization
- Slovenia
- INIS RN
- 36115780
- Subject category
- S99: GENERAL AND MISCELLANEOUS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CALCULATIONS; DIAGRAMS; FAILURES; FAULT TREE ANALYSIS; HISTORICAL ASPECTS; KRSKO REACTOR; OPTIMIZATION; RISK ASSESSMENT; SAFETY ANALYSIS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; INFORMATION; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 refs., 3 figs. Imprint:665 refs., 126 tabs., 520 figs.