Published 1982
| Version v1
Book
Fault tree analysis of a reactor protective system
- 1. Inst. fur Readtorentwicklung, Karlsruhe, Federal Republic of Germany
Description
The reactor protective system of a LMFBR for loss of primary flow has been analyzed. Due to the extremely large number of minimal cut sets of the fault tree, the system cannot be fully described by applying existing analytical methods. A special method based on boolean algebra with restricted variables has been developed and applied to the system. The method also accounts for statistical dependencies among components and for human failures
Additional details
Additional titles
- Augmented title (English)
- LMFBR
Publishing Information
- Publisher
- American Nuclear Society, Inc.
- Imprint Place
- La Grange Park, IL (USA)
- Imprint Title
- Probabilistic risk assessment
- Journal Page Range
- p. 1311-1320.
Conference
- Title
- ANS/ENS topical meeting on probabilistic risk assessment.
- Dates
- 20-24 Sep 1981.
- Place
- Port Chester, NY (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15027993
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALGEBRA; FAULT TREE ANALYSIS; LMFBR TYPE REACTORS; LOSS OF FLOW; REACTOR PROTECTION SYSTEMS; STATISTICS
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; MATHEMATICS; REACTOR ACCIDENTS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS