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
Descriptors:
Subject Categories:
- Computer Programming and Software
- Nuclear Radiation Shielding, Protection and Safety
- Nuclear Physics and Elementary Particle Physics