Accession Number:

ADA036469

Title:

SAMCEP: A Correlated Monte Carlo Neutron and Gamma Radiation Transport Code.

Descriptive Note:

Final rept.,

Corporate Author:

MATHEMATICAL APPLICATIONS GROUP INC ELMSFORD N Y

Report Date:

1977-02-01

Pagination or Media Count:

209.0

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, andor 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 ENDFB format.

Subject Categories:

  • Computer Programming and Software
  • Fission Reactor Physics

Distribution Statement:

APPROVED FOR PUBLIC RELEASE