THE DEVELOPMENT IN FRANCE OF THE REACTOR SYSTEM NATURAL URANIUM-GRAPHITE- CO$sub 2$. EXPERIENCE ACQUIRED. FUTURE PROSPECTS

Journal Article · Tue Oct 01 04:00:00 EDT 1963 · Bull. Inform. Sci. Tech. (Paris)

OSTI ID:4122637

Horowitz, J; Roux, J P

The uranium-- graphite-- CO/sub 2/ reactors constitute the basis of the French electro-nuclear power station program. The reactors EDF 1, EDF 2, and EDF 3 at Chinon follow up the plutonium piles G 2 and G 3 at Marcoule, and these together represent the major part of the 850 Mw of electricity which was planned for 1965 by the third equipment program. G 2 and G 3 have been supplying electricity to the French national grid since 1959 and 1960 respectively. EDF 1 underwent 1963 preliminary tests in early 1963 prior to power operation; it is plandned that EDF 2 will come into service at the end of 1964 and EDF 3 during 1965. A review of the development of this reactor system In the light of experience acquired on this type of reactor is presented. The progress achieved in the laboratories on the various technical aspects, neutronic, thermal, mechanical, and metallurgical, and the development prospects resulting from them are discussed. The experience acquired from the construction of the various reactors and the technical and economical conclusions resulting from it are described. The operational experience of the Marcoule reactors and of the first trials of the EDF 1 reactor, are reviewed. An attempt was made to define the prospects of this type of reactor in the French program, by distinguishing between the technical practicability and the economic feasibility. (auth)

• Research Organization: Originating Research Org. not identified
• NSA Number: NSA-18-004810
• OSTI ID: 4122637
• Journal Information: Bull. Inform. Sci. Tech. (Paris), Journal Name: Bull. Inform. Sci. Tech. (Paris) Vol. Vol: No. 76
• Country of Publication: Country unknown/Code not available
• Language: French

Related Subjects

CARBON DIOXIDE
CONFIGURATION
COOLANT LOOPS
ECONOMICS
EDF-1
EDF-2
EDF-3
EFFICIENCY
ELECTRICITY
FABRICATION
FUELS
G2
G3
GAS COOLANT
GRAPHITE MODERATOR
HEAT TRANSFER
MATERIALS TESTING
MECHANICAL STRUCTURES
METALLURGY
NATURAL URANIUM FUEL
NEUTRON FLUX
OPERATION
PERFORMANCE
PLANNING
PLUTONIUM
POWER PLANTS
PRODUCTION
REACTIVITY
REACTOR CORE
REACTOR TECHNOLOGY
REACTORS
STARTUP
URANIUM