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.