Published 1975 | Version v1
Book

Application of reliability analysis methods to the Rapsodie reactor

Creators

  • 1. CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-les-Durance (France)

Description

A study has been made of the variation in the failure rate as a function of the total operating time of the Rapsodie fast reactor, for operation at 24 MW(th) from May 1967 to February 1970 and for operation at 37 MW(th) subsequently (Fortissimo version). In both cases, classical bathtub curves were obtained - without the rise characteristic of wear and tear. The failure rates for both Rapsodie and Fortissimo are very close to 4.3x10-3, giving a mean time between failures of 230 hours. On the other hand, the duration of teething troubles is considerably greater in the case of Rapsodie than in that of Fortissimo. These results relate only to incidents which occurred during reactor operation and which entailed a variation in power. For the classification of incidents, a degree of acuteness is assigned to failures of different componetns on the basis of a dimensionless number, A, defined for that purpose

Additional details

Additional titles

Original title (French)
Application des methodes d'analyse de la fiabilite au cas du reacteur Rapsodie

Publishing Information

Publisher
IAEA.
Imprint Place
Vienna
ISBN
92-0-050075-7
Imprint Title
Reliability of nuclear power plants
Imprint Pagination
p. 441-455.
Series
Proceedings series.

Conference

Title
Symposium on the reliability of nuclear power plants.
Dates
14 Apr 1975.
Place
Innsbruck, Austria.

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
7242693
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FAILURE MODE ANALYSIS; FAILURES; PROBABILITY; RAPSODIE REACTOR; REACTOR OPERATION; RELIABILITY
Descriptors DEC
BREEDER REACTORS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; OPERATION; PLUTONIUM REACTORS; REACTORS; RESEARCH AND TEST REACTORS; SODIUM COOLED REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; TEST REACTORS

Optional Information

Secondary number(s)
IAEA-SM--195/4.