Analysis of the new GCFR upper and lower plenum flow-through shields

Conference · Sun Sep 14 00:00:00 EDT 1980

OSTI ID:5026699

Cramer, S N ^[1]; Reed, D A; Emmett, M B; Rouse, C A

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1. Oak Ridge National Lab., TN

Analysis of the proposed GCFR upper and lower plenum flow-through shields has been performed using both discrete ordinate (DOT) and Monte Carlo (MORSE) methods. Several shields having one change of direction in the coolant path (chevron) and two changes of direction (herringbone) were investigated. The shields were modeled as unit cells with periodic boundary conditions. From plenum fluence calculations and design constraints at the reactor vessel liner, it was determined that all the shield configurations analyzed should be adequate for the necessary radiation attenuation.

• Research Organization: Oak Ridge National Lab., TN (USA); Tennessee Univ., Knoxville (USA); Union Carbide Corp., Oak Ridge, TN (USA). Nuclear Div.; General Atomic Co., San Diego, CA (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5026699
• Report Number(s): CONF-800942-4; TRN: 80-017825
• Resource Relation: Conference: ANS topical meeting on 1980 advances in reactor physics and shielding, Sun Valley, ID, USA, 14 Sep 1980
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
GCFR REACTOR
SHIELDING
CONFIGURATION
NEUTRON FLUX
PRIMARY COOLANT CIRCUITS
REACTOR VESSELS
SPECIFICATIONS
BREEDER REACTORS
CONTAINERS
COOLING SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
GAS COOLED REACTORS
GCFR TYPE REACTORS
HELIUM COOLED REACTORS
RADIATION FLUX
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
210500* - Power Reactors
Breeding