
Accession Number : AD0748662
Title : Analysis of Neutron and Secondary Gamma Ray Transport in Concrete Using the SAMCE Monte Carlo Code.
Descriptive Note : Final rept.,
Corporate Author : MATHEMATICAL APPLICATIONS GROUP INC ELMSFORD N Y
Personal Author(s) : Cohen,Martin O.
Report Date : NOV 1971
Pagination or Media Count : 106
Abstract : SAMCE is a Monte Carlo computer code designed to solve the neutron and gamma ray transport equations in complex threedimensional geometries. In the study, the SAMCE code was used to analyze the timedependent 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 : (*SHIELDING, *CONCRETE), (*NEUTRON TRANSPORT THEORY, COMPUTER PROGRAMS), (*GAMMA RAYS, SHIELDING), NEUTRON SPECTRUM, GAMMA RAY SPECTRA, GRAPHICS, COMPUTER PROGRAMMING, MONTE CARLO METHOD
Subject Categories : Computer Programming and Software
Nuclear Radiation Shield, Protection & Safety
Nuclear Physics & Elementary Particle Physics
Distribution Statement : APPROVED FOR PUBLIC RELEASE