Published February 1985 | Version v1
Report

Comparison of methods for quantitative analysis of common cause failures - a case study

  • 1. Aktiebolaget Asea-Atom, Vaesteras, Sweden

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