Published 1989 | Version v1
Book

On the treatment of dependence in making decisions about risk

Creators

  • 1. Pickard, Lowe and Garrick, Inc., Newport Beach, CA (USA)

Description

Much attention has been paid to the treatment of dependence in performing probabilistic risk assessments (PRA). For instance, causal dependencies (e.g., common cause failures, cascade failures, and intersystem dependencies) have been taken into account in PRAs beginning with the Reactor Safety Study (USNRC, 1975). In addition, beginning in the early 1980s, attention began to be paid to the issue of probabilistic dependence between the failure rates (Apostolakis and Kaplan, 1981) or seismic fragilities (Kaplan, 1985) of similar components, and the impact of such dependence on risk estimates. By now, it has been clearly demonstrated that failure to take either casual or probabilistic dependence into account in PRAs can lead to misleading results, typically underestimates of the true risk. However, there has been little attention to date on the effects of dependence in the area of decision making. The objectives of this paper are to illustrate the potential importance of dependence in making decisions about risks, and to present some ideas on how to communicate the effects of dependence to decision makers in a clear and easily comprehensible manner

Additional details

Publishing Information

Publisher
American Association for Structural Mechanics in Reactor Technology.
Imprint Place
Los Angeles, CA (USA)
ISBN
0-9623306-0-4
Imprint Title
Transactions of the 10th international conference on structual mechanics in reactor technology
Imprint Pagination
199 p.
Series
Volume P. Probabilistic safety assessment.
Journal Page Range
p. 63-68.

Conference

Title
10. international conference on Structural Mechanics in Reactor Technology (SMIRT).
Dates
14-18 Aug 1989.
Place
Anaheim, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
21068031
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FAILURE MODE ANALYSIS; MANAGEMENT; PLANNING; PROBABILISTIC ESTIMATION; REACTOR COMPONENTS; REACTOR SAFETY; RISK ASSESSMENT; SEISMIC EFFECTS; SPECIFICATIONS
Descriptors DEC
SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS

Optional Information

Secondary number(s)
CONF-890855--.