Comparison of methods for quantitative analysis of common cause failures - a case study
Description
The beta factor method traditionally used for quantitative analysis of common cause failures (CCFs), does not allow a distinction between different failure multiplicities. Consequently, application of such a simple model to systems characterized by high level of redundancy may lead to excessively conservative estimates of the system failure probability. In the present report several higher-order methods, namely Binomial Failure Rate (BFR) method, Multiple Dependent Failure Fraction (MDFF) method and Multiple Greek Letter (MGL) method are applied to the same set of data. THe MDFF method, originally developed for a system of three identical units, has been modified and extended to a four-channel system. The MGL method gives the best agreement with the results directly assessed from the data set. Generally, as expected, the higher-order methods provide more realistic estimates of system failure probabilities than traditional models using only one CCF-parameter
Additional details
Publishing Information
- Imprint Title
- International topical meeting on probabilistic safety methods and applications: proceedings. Volume 3. Sessions 17-23 and indexes
- Journal Page Range
- p. 183.1-183.10.
- Report number
- EPRI-NP--3912-SR-Vol.3
Conference
- Title
- International ANS/ENS topical meeting on probabilistic safety methods and applications.
- Dates
- 24 Feb - 1 Mar 1985.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19023413
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPARATIVE EVALUATIONS; FAILURES; MARKOV PROCESS; NUCLEAR POWER PLANTS; PROBABILITY; REACTOR COMPONENTS; REACTOR SAFETY; RISK ASSESSMENT; STATISTICAL MODELS; SYSTEM FAILURE ANALYSIS
- Descriptors DEC
- EVALUATION; MATHEMATICAL MODELS; NUCLEAR FACILITIES; POWER PLANTS; SAFETY; STOCHASTIC PROCESSES; SYSTEMS ANALYSIS; THERMAL POWER PLANTS