SAMCEP: A Correlated Monte Carlo Neutron and Gamma Radiation Transport Code.
Abstract
SAMCEP is a system of U.S.A. - Standard FORTRAN programs for the solution by Monte Carlo of several correlated neutron and secondary gamma transport problems in complex three-dimensional geometries. Up to 10 correlated problems, involving perturbations of composition, neutron cross sections, angular or energy distributions, and/or source spectra, as well as perturbations of gamma production data, can be run simultaneously. Individual problem fluxes (region-, energy-, and time-dependent), as well as the flux differences between any or all pairs of problems, are available. In addition, fluxes can be obtained at point detectors, with a built-in biasing procedure to bound the estimates, the so-called bounded flux-at-a-point (BFAP) estimation procedure. SAMCEP retains essentially all the features of its predecessor code, SAM-CE, including the use of basic element data in the latest ENDF/B format.
Document Details
- Document Type
- Technical Report
- Publication Date
- Feb 01, 1977
- Accession Number
- ADA036469
Entities
People
- Henry Lichtenstein
- Herbert Steinberg
- Joan Brooks
Organizations
- Mathematical Applications Group