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From Lesseps 1300 to the application of computerized PSAs to operational safety; De Lesseps 1300 a l`application des EPS informatisees a la surete operationnelle

Abstract

The LESSEPS project was conducted in the framework of the Probabilistic Safety Assessment of the PALUEL power plant (PSA 1300), from 1986 to 1989. It has led to the creation of LESSEPS 1300, a fully computerized knowledge base on the PALUEL power plant, including methods, reliability models and programs. From the experience gained, we can draw two main conclusions: -this computerized and detailed knowledge base on a nuclear plant is a powerful tool to perform sensitivity studies, when functional assumptions or reliability data are changed. -to be used correctly, either by people who didn`t participate in its creation or for purposes for which it was not initially developed such an important knowledge base should have two essential characteristics: a great user-friendliness of the tools, and a great transparency, as regards the assumptions. Therefore, part of the `post-PSA 1300 study program` is devoted to: (1) the development of a workstation for reliability engineers, (2) an important methodological work to determine the validity range of the different methods used. (3) a validation program of these tools and of the methodological approach in the framework of practical studies.
Publication Date:
Jun 01, 1991
Product Type:
Technical Report
Report Number:
EDF-92-NB-00031
Reference Number:
SCA: 210200; PA: AIX-24:030223; SN: 93000955863
Resource Relation:
Other Information: PBD: Jun 1991
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; PALUEL-1 REACTOR; SAFETY; KNOWLEDGE BASE; PROBABILISTIC ESTIMATION; COMPUTER CODES; FAULT TREE ANALYSIS; PALUEL-2 REACTOR; PALUEL-3 REACTOR; PALUEL-4 REACTOR; 210200; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED
OSTI ID:
10132153
Research Organizations:
Electricite de France (EDF), 92 - Clamart (France)
Country of Origin:
France
Language:
French
Other Identifying Numbers:
Other: ON: DE93619439; TRN: FR9301096030223
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
FRN
Size:
[25] p.
Announcement Date:
Jul 04, 2005

Citation Formats

Ancelin, C, and Dubreuil Chambardel, A. From Lesseps 1300 to the application of computerized PSAs to operational safety; De Lesseps 1300 a l`application des EPS informatisees a la surete operationnelle. France: N. p., 1991. Web.
Ancelin, C, & Dubreuil Chambardel, A. From Lesseps 1300 to the application of computerized PSAs to operational safety; De Lesseps 1300 a l`application des EPS informatisees a la surete operationnelle. France.
Ancelin, C, and Dubreuil Chambardel, A. 1991. "From Lesseps 1300 to the application of computerized PSAs to operational safety; De Lesseps 1300 a l`application des EPS informatisees a la surete operationnelle." France.
@misc{etde_10132153,
title = {From Lesseps 1300 to the application of computerized PSAs to operational safety; De Lesseps 1300 a l`application des EPS informatisees a la surete operationnelle}
author = {Ancelin, C, and Dubreuil Chambardel, A}
abstractNote = {The LESSEPS project was conducted in the framework of the Probabilistic Safety Assessment of the PALUEL power plant (PSA 1300), from 1986 to 1989. It has led to the creation of LESSEPS 1300, a fully computerized knowledge base on the PALUEL power plant, including methods, reliability models and programs. From the experience gained, we can draw two main conclusions: -this computerized and detailed knowledge base on a nuclear plant is a powerful tool to perform sensitivity studies, when functional assumptions or reliability data are changed. -to be used correctly, either by people who didn`t participate in its creation or for purposes for which it was not initially developed such an important knowledge base should have two essential characteristics: a great user-friendliness of the tools, and a great transparency, as regards the assumptions. Therefore, part of the `post-PSA 1300 study program` is devoted to: (1) the development of a workstation for reliability engineers, (2) an important methodological work to determine the validity range of the different methods used. (3) a validation program of these tools and of the methodological approach in the framework of practical studies.}
place = {France}
year = {1991}
month = {Jun}
}