Published 1993 | Version v1
Book

Application of database management software to probabilistic risk assessment calculations

Creators

  • 1. Sandia National Lab., Albuquerque, NM (United States)

Description

Probabilistic risk assessment (PRA) calculations require the management and processing of large amounts of information. This data normally falls into two general categories. For example, a commercial nuclear power plant PRA study makes use of plant blueprints and system schematics, formal plant safety analysis reports, incident reports, letters, memos, handwritten notes from plant visits, and even the analyst's ''engineering judgment''. This information must be documented and cross-referenced in order to properly execute and substantiate the models used in a PRA study. The first category is composed of raw data that is accumulated from equipment testing and operational experiences. These data describe the equipment, its service or testing conditions, its failure mode, and its performance history. The second category is composed of statistical distributions. These distributions can represent probabilities, frequencies, or values of important parameters that are not time-related. Probability and frequency distributions are often obtained by fitting raw data to an appropriate statistical distribution. Database management software is used to store both types of data so that it can be readily queried, manipulated, and archived. This paper provides an overview of the information models used for storing PRA data and illustrates the implementation of these models using examples from current PRA software packages

Part of:
Design analysis, robust methods, and stress classification

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers.
Imprint Place
New York, NY (United States)
ISBN
0-7918-0992-7
Imprint Title
Design analysis, robust methods, and stress classification
Imprint Pagination
341 p.
Journal Page Range
p. 225-228.

Conference

Title
1993 pressure vessels and piping conference.
Dates
25-29 Jul 1993.
Place
Denver, CO (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
25018817
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
MATHEMATICAL MODELS; NUCLEAR POWER PLANTS; PROBABILITY; RISK ASSESSMENT; SAFETY
Descriptors DEC
NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS

Optional Information

Secondary number(s)
CONF-930702--Vol.265.