THE FRENCH FUEL ELEMENTS FOR THE SYSTEM NATURAL URANIUM-GRAPHITE-CARBON DIOXIDE

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

OSTI ID:4122622

Boussard, R; Jeanpierre, G

Results of studies carried out in France on fuel elements used in reactors of the type natural U-- CO/sub 2/--graphite are presented. The desire to increase the specific power extracted through the chandnels of this type of reactor led to research into the nature of the fuel itself andd of the canning material, as well as into the geometry of the fuel element. Each stage in the building program of the EDF power stations of this type (EDF 1, EDF 2, EDF 3, at the Chinon Center) was marked by the study of a different tuel element. The industrial policy of the C.E.A. for large-scale production is described. The termination of the studies is marked by in-pile resistandce tests, which are carried out both in experimental reactors of the EL 3 type at Saclay and in operational power reactors of the G 2/G 3 type at Marcoule. (auth)

• Research Organization: Originating Research Org. not identified
• NSA Number: NSA-18-004811
• OSTI ID: 4122622
• 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

BURNOUT
BURNUP
CANNING
CARBON DIOXIDE
CONFIGURATION
COOLANT LOOPS
EDF-1
EDF-2
EDF-3
EFFICIENCY
EL-3
ELECTRICITY
FABRICATION
FUEL ELEMENTS
FUELS
G2
G3
GAS COOLANT
GRAPHITE MODERATOR
HEAT TRANSFER
HIGH TEMPERATURE
IRRADIATION
MATERIALS TESTING
MEASURED VALUES
NATURAL URANIUM FUEL
NEUTRON FLUX
PLANNING
POWER PLANTS
PRODUCTION
RADIATION EFFECTS
REACTOR CORE
REACTOR SAFETY
REACTOR TECHNOLOGY
REACTORS
RESEARCH REACTORS
SURFACES