Physics design of the 300-MW(e) gas-cooled fast breeder reactor demonstration plant grid plate shielding

Technical Report · Wed Sep 01 04:00:00 EDT 1976

DOI:https://doi.org/10.2172/7331283· OSTI ID:7331283

Perkins, R. G.; Cerbone, R. J.

The grid plate for the 300-MW(e) gas-cooled fast breeder reactor demonstration plant provides the vital function of supporting the core and blanket assemblies. It is therefore essential that adequate shielding be provided to assure the structural integrity of the grid plate for the life of the plant. Results are presented for analyses leading to an optimum revised grid plate shielding design satisfying the conflicting requirements of shielding and helium flow. Discrete ordinate transport theory is used to estimate the maximum neutron flux and neutron spectrum in the grid plate, and calculational uncertainties are incorporated by applying a bias factor to the grid plate fluence. Damage function analysis is utilized to evaluate the lower-bound (95 percent confidence) fluence limit to attain the limiting grid plate material property level of 10 percent residual ductility based on total elongation.

• Research Organization: General Atomic Co., San Diego, CA (USA)
• OSTI ID: 7331283
• Report Number(s): GA-A-14124
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
BREEDER REACTORS
DESIGN
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
GAS COOLED REACTORS
GCFR REACTOR
GCFR TYPE REACTORS
HELIUM COOLED REACTORS
MECHANICAL STRUCTURES
NEUTRON FLUX
PLATES
RADIATION FLUX
REACTOR COMPONENTS
REACTOR CORES
REACTOR INTERNALS
REACTORS
SUPPORTS