Experimental Channel for the Study of Heat Removal from the BR-1 Reactor; CHENAL EXPERIMENTAL POUR L'ETUDE DE L'EXTRACTION DE LA CHALEUR DU REACTEUR BR-1
To augment the thermal power and the neutron flux at the center of the BR-1 reactor, the use of natural uranium reds whose aluminum cladding would have fins was proposed. In order to study the performances of fuel elements fabricated with fins, an experimental channel was constructed in the reactor. A brief description is given of a previous channel with special emphasis on its defects which are to be remedied in the new facility. The experimental channel is a tube of graphite cornected to the inlet section by a rubber tube reenforced by a metallic spiral. The fabrication and assembling of the channel are described in detail. The controls used to assure the correct geometry, air tightness, and the temperatures of the air, claddings, and graphite are discussed. (J.S.R.)
- Research Organization:
- Brussels. Centre d'Etudes pour les Applications de l'Energie Nucleaire
- NSA Number:
- NSA-13-005915
- OSTI ID:
- 4291006
- Report Number(s):
- NP-7149
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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Related Subjects
ALUMINUM
BR-1
CANNING
CONFIGURATION
FABRICATION
FAILURES
FINS
FUEL ELEMENTS
GRAPHITE
IRRADIATION
MATERIALS TESTING
MECHANICAL STRUCTURES
MONITORING
NATURAL URANIUM FUEL
NEUTRON BEAMS
NEUTRON FLUX
PLANNING
REACTOR CORE
REACTORS
REMOTE CONTROL
RESEARCH REACTORS
RODS
RUBBER
SEALS
TEMPERATURE
TUBES
WATER MODERATOR