Published 1975 | Version v1
Book

Operational reliability of the safety system to detect abnormal heating of fuel assemblies in the Phenix reactor

  • 1. CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)

Description

In fast reactors, the surveillance of safety barriers requires a large number of temperature measurements, so that any anomalous heating of fuel assemblies can be detected very rapidly. The data can be handled within the time available only by means of computers. For dealing with overheating, the Phenix reactor has a safety system to which information is transmitted from the thermocouples on the fuel assemblies; the information passes through industrial mini-computers to a relay system which triggers the control rod drop if necessary. During normal operation the computers serving each safety circuit operate in pairs in a coincidence regime - in other words, the information from the two thermocouples on a fuel assembly must coincide, as must the information passed on by the two computers, if an emergency shut-down is to be triggered. In view of the importance of this safety system and the use of small computers for surveillance and initiation of safety measures, knowledge of the operational history of the system components is essential. Since a record has been kept of breakdowns affecting Phenix safety components, operational reliability estimates covering a period of over 18 months have been made for the components of the safety system for detection of anomalous heating of fuel assemblies. On the basis of these estimates it has been possible to verify the reliability and availability of the system in real operating conditions. The results of this study will be used in designing and constructing the corresponding safety system for the next French fast reactor, Super Phenix

Additional details

Additional titles

Original title (French)
Fiabilite operationnelle du poste de securite ''echauffement anormal d'assemblage'' sur le reacteur Phenix

Publishing Information

Publisher
IAEA.
Imprint Place
Vienna
ISBN
92-0-050075-7
Imprint Title
Reliability of nuclear power plants
Imprint Pagination
p. 277-292.
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
7233996
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CALCULATIONS; COMPUTERS; PHENIX REACTOR; REACTOR OPERATION; REACTOR PROTECTION SYSTEMS; RELIABILITY
Descriptors DEC
BREEDER REACTORS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; OPERATION; PLUTONIUM REACTORS; POWER REACTORS; REACTORS; SODIUM COOLED REACTORS

Optional Information

Secondary number(s)
IAEA-SM--195/7.