Published 1978 | Version v1
Book

Synthesis of experience data for risk assessment and design improvement of gas-cooled reactors

  • 1. General Atomic Co., San Diego, CA

Description

This paper illustrates the practical synthesis of previous component and system operating experience into the reliability parameters which are used in probabilistic risk evaluations of gas-cooled reactors (GCRs). Component and system reliability operating experience provides the basic input data for quantifying event tree and fault tree models that describe hypothesized reactor accident sequences. It is therefore necessary to collect and review the existing operating experience described in numerous accounts of power plant operations for both the development of detailed accident models and the quantification of their likelihood. It was found that the presently available operating experience includes enough information to provide both the qualitative and quantitative understanding necessary to evaluate the safety of the gas-cooled reactor designs

Additional details

Publishing Information

Publisher
American Nuclear Society, Inc.
Imprint Place
La Grange Park, IL
Imprint Title
Probabilistic analysis of nuclear reactor safety
Journal Page Range
p. VI.7.1-VI.7.12.

Conference

Title
Probabilistic analysis of nuclear reactor safety.
Dates
8 - 10 May 1978.
Place
Los Angeles, CA, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
10487495
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DATA; GAS COOLED REACTORS; REACTOR COMPONENTS; RISK ANALYSIS; STATISTICS; SYSTEM FAILURE ANALYSIS
Descriptors DEC
INFORMATION; MATHEMATICS; REACTORS; SYSTEMS ANALYSIS