Accession Number:

AD0748662

Title:

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:

1971-11-01

Pagination or Media Count:

106.0

Abstract:

SAM-CE is a Monte Carlo computer code designed to solve the neutron and gamma ray transport equations in complex three-dimensional geometries. In the study, the SAM-CE code was used to analyze the time-dependent transport of neutrons and secondary gamma rays in slabs of concrete. Calculationally determined counting rates and energy leakage spectra, at a detector located behind the concrete slabs, are 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