Preliminary thermal analysis of the 300-MW(e) gas-cooled fast breeder reactor grid plate

Technical Report · Wed Jun 01 04:00:00 EDT 1977

DOI:https://doi.org/10.2172/7296068· OSTI ID:7296068

Jovanovic, V.

A preliminary thermal analysis of the 300-MW(e) gas-cooled fast breeder reactor (GCFR) grid plate was performed to predict the radial and axial grid plate temperature distributions and to provide input for thermal stress analysis. Gamma heating rates calculated by Oak Ridge National Laboratory were used. The maximum predicted temperatures for the GCFR grid plate are under 427/sup 0/C (800/sup 0/F); therefore, the requirements of Division 1 of Section III of the ASME Boiler and Pressure Vessel Code apply, and there is no need to use the more complex requirements of the high-temperature code case, No. 1592. The thermal stresses resulting from the temperature distributions are currently being evaluated. If these stresses prove to be excessive, several methods can be used to make the grid plate temperature distribution more uniform and, thus, reduce the thermal stresses.

• Research Organization: General Atomic Co., San Diego, Calif. (USA)
• DOE Contract Number: EY-76-C-03-0167-023
• OSTI ID: 7296068
• Report Number(s): GA-A-14457
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
BREEDER REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ASSEMBLIES
GAS COOLED REACTORS
GCFR REACTOR
GCFR TYPE REACTORS
HEATING
HELIUM COOLED REACTORS
MECHANICAL STRUCTURES
PLATES
RADIATION HEATING
REACTOR COMPONENTS
REACTOR INTERNALS
REACTORS
STRESSES
SUPPORTS
TEMPERATURE DISTRIBUTION
THERMAL STRESSES