Published March 1994 | Version v1
Report

A computer tool for systems configuration management based on PSA models and techniques

Creators

  • 1. Institute for Nuclear Research, Pitesti (Romania)

Description

In the frame of the IAEA coordinated research programme for expert systems development, in the Institute for Nuclear Research, a PSA based computer tool for systems configuration management is in progress. The system is designed to be integrated in the future ''living PSA'' system under development now. The design of the system is mainly based on the PSA model for Cernavoda NPP and the risk-based configuration management methods, taking into account the user requirements. The system will be developed taking into account the expert systems techniques, specific PSA methods (MCS and path-sets generation, etc.) and friendly user interface features. The work done up to now for the system mainly consist of the users requirements identification, development techniques choosing and top-level system design. (author). 4 refs, 1 fig

Part of:
Advances in reliability analysis and probabilistic safety assessment for nuclear power reactors

Additional details

Publishing Information

Imprint Title
Advances in reliability analysis and probabilistic safety assessment for nuclear power reactors
Imprint Pagination
264 p.
Journal Page Range
p. 259-261.
ISSN
1011-4289
Report number
IAEA-TECDOC--737

Conference

Title
Technical committee meeting on advances in reliability analysis and probabilistic safety assessment for nuclear power reactors.
Dates
7-11 Sep 1992.
Place
Budapest (Hungary).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
25037124
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CERNAVODA-1 REACTOR; CONFIGURATION; EXPERT SYSTEMS; PROBABILISTIC ESTIMATION; REACTOR SAFETY; RELIABILITY; SAFETY ANALYSIS
Descriptors DEC
CANDU TYPE REACTORS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; NATURAL URANIUM REACTORS; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SAFETY; THERMAL REACTORS

Optional Information