CALCULATIONS OF FISSION-PRODUCT GAMMA-RAY DOSES IN SINGLE-COMPARTMENT ABOVE GROUND CONCRETE STRUCTURES,
Abstract
Parametric data describing Structure Protection Coefficients for fission-product gamma-rays have been generated for use in analysis of the shielding effectiveness of above-ground concrete structures against the initial nuclear radiation produced by the detonation of a nuclear weapon. Energy and angle distributions of the fission-product gamma-ray fluence incident on the roof and walls of rectangular structures were calculated for an over-pressure range of 100 psi. These data were used as source input data to an S sub n code for machine calculations of the penetration of fission-product gamma-rays through concrete slabs of various thickness. The penetration calculations used an S sub 16 angle quadrature and a P sub 12 expansion of the Klein-Nishina differential scattering cross section. The angular distributions of the emergent gamma-ray absorbed dose current for each slab orientation as a function of slab thickness were input to a machine procedure that was used to calculate fission-product gamma-ray absorbed doses at receivers placed 3 ft. above the structure floor and at various positions within the structure for structures with square floor areas. Structure Protection Coefficients (absorbed dose at receiver per unit free-field absorbed dose) were computed for receivers positioned within concrete structures with an inside height of 10 ft. and with length and widths of the structures varying between 10 and 50 ft. for wall thickness of 6 to 60 inches. (Author)
Document Details
- Document Type
- Technical Report
- Publication Date
- Jun 09, 1968
- Accession Number
- AD0675053
Entities
People
- L. Glenn Mooney
- Michael B. Wells