Accession Number : AD0768042

Title :   Additional Analysis of Neutron and Secondary Gamma Ray Transport in Concrete Using the SAM-CE Monte Carlo Code.

Descriptive Note : Final rept.,

Corporate Author : MATHEMATICAL APPLICATIONS GROUP INC ELMSFORD N Y

Personal Author(s) : Cohen,Martin O. ; Beer,Mendel

Report Date : SEP 1973

Pagination or Media Count : 43

Abstract : The SAM-CE Monte Carlo code has been used to analyze the time-dependent transport of neutrons and secondary gamma rays in a forty centimeter thick slab of concrete. Calculated counting rates and energy leakage spectra at a detector located behind the concrete slab, are compared with previous SAM-CE calculations involving older cross section sets. The results are also compared with similar experimental results obtained by Gulf Radiation Technology. (Author)

Descriptors :   (*SHIELDING, CONCRETE), (*NEUTRON TRANSPORT THEORY, *COMPUTER PROGRAMMING), (*GAMMA RAYS, TRANSPORT PROPERTIES), NEUTRON CROSS SECTIONS, GAMMA RAY CROSS SECTIONS, GRAPHICS

Subject Categories : Computer Programming and Software
      Nuclear Radiation Shield, Protection & Safety
      Nuclear Physics & Elementary Particle Physics

Distribution Statement : APPROVED FOR PUBLIC RELEASE