Sensitivity study of neutron transport through standard and rebar concrete

Conference · Fri Jan 01 00:00:00 EST 1982

OSTI ID:5185950

Bhuiyan, S I; Roussin, R W; Lucius, J L

An investigation is under way at ORNL to (1) develop a data base pertinent to the transport of neutrons through thick concrete shields, (2) use the data base in an energy group boundary selection and collapsing scheme, and (3) develop a simple methodology to access the data base to provide rapid solutions to practical shielding problems. This paper describes work carried out to fulfill objective (1), the work consisting of calculations of the transport of fission neutrons through 1- and 2-m-thick slabs of standard concrete and rebar (steel-reinforced) concrete, together with calculations of the sensitivities of the results to total, absorption, and elastic cross sections. The transport calculations were performed with the one-dimensional discrete ordinates code ANISN in both forward and adjoint modes. The DLC-41C/VITAMIN-C cross-section library (171 neutron, 36 gamma groups) was employed, with a P/sub 3/ cross-section expansion and an S/sub 16/ angular quadrature. In all cases the fission source was assumed to be distributed within the first 1-cm thickness of the slab and the detector was assumed to occupy the last 1-cm thickness of the slab. For the rebar concrete the slab constituents were homogenized, with the horizontal and vertical No. 11 reinforcing steel rods comprising 7.6 vol. % of the slab. The quantity calculated was the absorbed dose rate, and care was taken in the mesh interval selection and source description to ensure agreement between the forward and adjoint results to within 0.02%.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5185950
• Report Number(s): CONF-820609-43; ON: DE82017416; TRN: 82-017249
• Resource Relation: Conference: American Nuclear Society annual meeting, Los Angeles, CA, USA, 6 Jun 1982
• Country of Publication: United States
• Language: English

Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS
CONCRETES
NEUTRON TRANSPORT
FISSION NEUTRONS
TRANSMISSION
REINFORCED CONCRETE
ABSORPTION
COMPUTER CALCULATIONS
CROSS SECTIONS
DISCRETE ORDINATE METHOD
DOSE RATES
ELASTIC SCATTERING
SENSITIVITY ANALYSIS
SHIELDING
TOTAL CROSS SECTIONS
BARYONS
BUILDING MATERIALS
ELEMENTARY PARTICLES
FERMIONS
HADRONS
MATERIALS
NEUTRAL-PARTICLE TRANSPORT
NEUTRONS
NUCLEONS
RADIATION TRANSPORT
REINFORCED MATERIALS
SCATTERING
654002* - Radiation & Shielding Physics- Shielding Calculations & Experiments- (-1987)