Accession Number : AD0771091

Title :   The SAMCEP Code with Bounded Flux at a Point Estimation.

Descriptive Note : Final rept.,


Personal Author(s) : Lichtenstein,Henry ; Steinberg,Herbert

Report Date : JUN 1973

Pagination or Media Count : 190

Abstract : SAMCEP is a system of U.S.A.-Standard FORTRAN programs for the solution by Monte Carlo of several correlated neutron transport problems in complex three-dimensional geometries. Up to 10 correlated problems, involving up to 100 perturbations, of composition, neutron cross sections, angular or energy distributions, and/or source spectra, can be run simultaneously. Individual problem fluxes or doses (region-, energy-, and (on option) time-dependent), as well as the differences between those of 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 (BEAP) estimation procedure. SAMCEP retains essentially all the features of its predecessor code, SAM-CE, including the use of basic neutron data in the latest ENDF/B format. (Modified author abstract)

Descriptors :   *Neutron transport theory, *Computer programming, Neutron flux, Monte Carlo method, Sampling, Computations, FORTRAN

Subject Categories : Computer Programming and Software
      Fission Reactor Physics

Distribution Statement : APPROVED FOR PUBLIC RELEASE