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

Technical Report · Fri Jan 01 00:00:00 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. (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5663022
• Report Number(s): ORNL-5805; ON: DE82007737; TRN: 82-008556
• Country of Publication: United States
• Language: English

Related Subjects

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