Additional Analysis of Neutron and Secondary Gamma Ray Transport in Concrete Using the SAM-CE Monte Carlo Code.
MATHEMATICAL APPLICATIONS GROUP INC ELMSFORD N Y
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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
- Computer Programming and Software
- Nuclear Radiation Shielding, Protection and Safety
- Nuclear Physics and Elementary Particle Physics