Review of ORNL-TSF shielding experiments for the gas-cooled Fast Breeder Reactor Program

Technical Report · Fri Jan 01 04:00:00 EST 1982

DOI:https://doi.org/10.2172/5663022· OSTI ID:5663022

Abbott, L S; Ingersoll, D T; Muckenthaler, F J; Slater, C O

During the period between 1975 and 1980 a series of experiments was performed at the ORNL Tower Shielding Facility in support of the shield design for a 300-MW(e) Gas Cooled Fast Breeder Demonstration Plant. This report reviews the experiments and calculations, which included studies of: (1) neutron streaming in the helium coolant passageways in the GCFR core; (2) the effectiveness of the shield designed to protect the reactor grid plate from radiation damage; (3) the adequacy of the radial shield in protecting the PCRV (prestressed concrete reactor vessel) from radiation damage; (4) neutron streaming between abutting sections of the radial shield; and (5) the effectiveness of the exit shield in reducing the neutron fluxes in the upper plenum region of the reactor.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5663022
• Report Number(s): ORNL-5805; ON: DE82007737
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
654002 -- Radiation & Shielding Physics-- Shielding Calculations & Experiments-- (-1987)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BREEDER REACTORS
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
GAS COOLED REACTORS
GCFR REACTOR
GCFR TYPE REACTORS
HELIUM COOLED REACTORS
NEUTRON FLUX
RADIATION FLUX
RADIATION STREAMING
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
RESEARCH REACTORS
SHIELDING
SPECIFICATIONS
TANK TYPE REACTORS
TEST FACILITIES
TEST REACTORS
TSR-1 REACTOR
TSR-2 REACTOR
WATER COOLED REACTORS
WATER MODERATED REACTORS