Published 2004 | Version v1
Miscellaneous

Development of web-based reliability data base platform

  • 1. Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)

Description

Probabilistic safety assessment (PSA) is a systematic technique which estimates the degree of risk impacts to the public due to an accident scenario. Estimating the occurrence frequencies and consequences of potential scenarios requires a thorough analysis of the accident details and all fundamental parameters. The robustness of PSA to check weaknesses in a design and operation will allow a better informed and balanced decision to be reached. The fundamental parameters for PSA, such as the component failure rates, should be estimated under the condition of steady collection of the evidence throughout the operational period. However, since any single plant data does not sufficiently enough to provide an adequate PSA result, in actual, the whole operating data was commonly used to estimate the reliability parameters for the same type of components. The reliability data of any component type consists of two categories; the generic that is based on the operating experiences of whole plants, and the plant-specific that is based on the operation of a specific plant of interest. The generic data is highly essential for new or recently-built nuclear power plants (NPPs). Generally, the reliability data base may be categorized into the component reliability, initiating event frequencies, human performance, and so on. Among these data, the component reliability seems a key element because it has the most abundant population. Therefore, the component reliability data is essential for taking a part in the quantification of accident sequences because it becomes an input of various basic events which consists of the fault tree

Part of:
Proceedings of the KNS autumn meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the KNS autumn meeting
Imprint Pagination
1466 p.
Journal Page Range
p. 415-416

Conference

Title
2004 autumn meeting of the KNS
Dates
28-29 Oct 2004
Place
Yongpyong (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
36102354
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ACCIDENTS; DATA BASE MANAGEMENT; FAULT TREE ANALYSIS; PERFORMANCE; PROBABILISTIC ESTIMATION; RELIABILITY; RISK ASSESSMENT
Descriptors DEC
CALCULATION METHODS; MANAGEMENT; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS

Optional Information

Notes
3 refs, 2 figs