PRESTRESSED CONCRETE VESSELS IN THE FRENCH POWER REACTOR PROGRAM (in French)
Journal Article
·
· Bull. Inform. Sci. Tech. (Paris)
OSTI ID:4124443
The application of prestressed concrete to the reactors G 2 andd G 3 at Marcoule and to the reactor EDF 3 under construction at Chinon is discussed. The construction of the reactor vessels for G 2 andd G 3 begand in 1958; the reactors have been operating under power since 1959 and 1960 respectively. The problems that arose during the construction of the reactor vessel, and the philosophy of the observations made during operation, which tend to show the safety of this equipment are discussed. The construction of the vessel for EDF 3 was begun at Chinon in the second half of 1961. The reasons for the choice of this vessel, the results of the calculations and trials carried out on a model, and the problems posed by the construction are listed. Various studies were carried out on the possibilities of units made of prestressed concrete for reactors. It appears that it is possible, if so desired, to increase the operating pressure and also to increase notably the size, thus making it possible to consider solutions of the integrated type. (auth)
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-18-004812
- OSTI ID:
- 4124443
- 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
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Related Subjects
CARBON DIOXIDE
CONCRETES
CONFIGURATION
COOLANT LOOPS
EDF-3
EFFICIENCY
EQUATIONS
FABRICATION
G2
G3
GAS COOLANT
GRAPHITE MODERATOR
MATERIALS TESTING
MOCKUP
NATURAL URANIUM FUEL
PERFORMANCE
PLANNING
POWER PLANTS
PRESSURE
PRESSURE VESSELS
REACTOR CORE
REACTOR SAFETY
REACTOR TECHNOLOGY
REACTORS
STRESSES
THERMAL STRESSES
VOLUME
CONCRETES
CONFIGURATION
COOLANT LOOPS
EDF-3
EFFICIENCY
EQUATIONS
FABRICATION
G2
G3
GAS COOLANT
GRAPHITE MODERATOR
MATERIALS TESTING
MOCKUP
NATURAL URANIUM FUEL
PERFORMANCE
PLANNING
POWER PLANTS
PRESSURE
PRESSURE VESSELS
REACTOR CORE
REACTOR SAFETY
REACTOR TECHNOLOGY
REACTORS
STRESSES
THERMAL STRESSES
VOLUME