Generalized Monte Carlo Program for Neutrons-GMCM-9

Abstract

GMCM-9 is a FORTRAN coded three-dimensional, multiregion, multienergy group, neutronic radom walk solution for reactor and shielding problems. Estimates are provided on the neutron flux within various zones of the configuration, the leakage at outer boundaries, and the criticality of reactor configurations. Answers are also obtained on the number of neutrons emerging from elastic scattering, inelastic scattering, and fission for the various materials. The program takes time into account, and may be used to obtain the above answers for successive time periods to investigate the time-dependent nature of a particular reactor configuration.

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Document Details

Document Type
Technical Report
Publication Date
Jul 15, 1962
Accession Number
AD0410523

Entities

People

  • M. Kniedler
  • T. Jordan

Organizations

  • Glenn L. Martin Company

Tags

Communities of Interest

  • C4I

DTIC Thesaurus Topics

  • Elastic Scattering
  • Government Procurement
  • Governments
  • Inelastic Scattering
  • Materials
  • Neutron Flux
  • Plastic Explosives
  • Procurement
  • Scattering
  • Three Dimensional

Fields of Study

  • Physics

Readers

  • Computational Modeling and Simulation
  • Solar Physics