UNC-SAM, A FORTRAN MONTE CARLO SYSTEM FOR THE EVALUATION OF NEUTRON OR GAMMA-RAY TRANSPORT IN THREE-DIMENSIONAL GEOMETRY

Abstract

A code system (called UNC-SAM) which evaluates the transport of neutrons or gamma rays using Monte Carlo methods in complex three-dimensional geometry, has been written in FORTRAN for the Control Data Corporation 1604-A computer. The code will calculate fluxes, flux dependent functionals such as doses, and their stantard deviations in geometry comprised of rectangular parallelepipeds which, in turn, may contain spheres, cylinders, parallelepipeds, or wedges. In order to increase the efficiency of the Monte Carlo transport game, UNC-SAM uses an importance sampling technique. In addition, in the particular case of evaluating neutron fluxes in small volume detectors, a scoring by analytical estimation referred to as flux at a point is employed.

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Document Details

Document Type
Technical Report
Publication Date
Aug 31, 1964
Accession Number
AD0605458

Entities

People

  • B. Eisenman
  • B. Eisenmann
  • F. R. Nakache

Tags

Communities of Interest

  • Air Platforms
  • Energy and Power Technologies

DTIC Thesaurus Topics

  • Charged Particles
  • Computers
  • Corporations
  • Detectors
  • Distribution Functions
  • Elastic Scattering
  • Energy Levels
  • Gamma Rays
  • Geometry
  • Health Services
  • Inelastic Scattering
  • Military Research
  • Neutron Flux
  • Scattering
  • Scattering Cross Sections
  • Standards
  • Three Dimensional

Fields of Study

  • Physics

Readers

  • Combustion Dynamics and Shock Wave Physics.
  • Computer Science.
  • Solar Physics