Final analysis of the GCFR radial blanket and shield integral experiment

Technical Report · Wed Apr 01 00:00:00 EST 1981

DOI:https://doi.org/10.2172/6562511· OSTI ID:6562511

Ingersoll, D T; Williams, L R

An integral experiment has been performed for verification of radiation transport methods and nuclear data used in the design of the radial shield for the proposed gas-cooled fast breeder reactor demonstration plant. The experiment was conducted at the ORNL Tower Shielding Facility and consisted of integral and spectral measurements of the neutron and gamma-ray flux transmitted through slabs of materials which modeled a GCFR-type radial blanket and radial shield. Both UO/sub 2/ and ThO/sub 2/ blankets were investigated as well as several shield designs comprising stainless steel, graphite, and boronated graphite.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6562511
• Report Number(s): ORNL-5756; TRN: 81-006654
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
GCFR REACTOR
SHIELDING
GAMMA RADIATION
GRAPHITE
NEUTRON FLUX
SPECIFICATIONS
STAINLESS STEELS
THORIUM OXIDES
URANIUM DIOXIDE
ACTINIDE COMPOUNDS
ALLOYS
BREEDER REACTORS
CARBON
CHALCOGENIDES
CHROMIUM ALLOYS
CORROSION RESISTANT ALLOYS
ELECTROMAGNETIC RADIATION
ELEMENTS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
GAS COOLED REACTORS
GCFR TYPE REACTORS
HELIUM COOLED REACTORS
IONIZING RADIATIONS
IRON ALLOYS
IRON BASE ALLOYS
NONMETALS
OXIDES
OXYGEN COMPOUNDS
RADIATION FLUX
RADIATIONS
REACTORS
STEELS
THORIUM COMPOUNDS
URANIUM COMPOUNDS
URANIUM OXIDES
210500* - Power Reactors
Breeding