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):

Report Date:

1973-09-01

Pagination or Media Count:

43.0

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

Subject Categories:

  • Computer Programming and Software
  • Nuclear Radiation Shielding, Protection and Safety
  • Nuclear Physics and Elementary Particle Physics

Distribution Statement:

APPROVED FOR PUBLIC RELEASE