Accession Number:

AD0711941

Title:

THE MORSE CODE - A MULTIGROUP NEUTRON AND GAMMA-RAY MONTE CARLO TRANSPORT CODE,

Descriptive Note:

Corporate Author:

OAK RIDGE NATIONAL LAB TENN

Report Date:

1970-09-01

Pagination or Media Count:

312.0

Abstract:

The MORSE code is a multipurpose neutron and gamma-ray transport Monte Carlo code. Through the use of multigroup cross sections, the solution of neutron, gamma-ray, or coupled neutron-gamma-ray problems may be obtained in either the forward or adjoint mode. Time dependence for both shielding and criticality problems is provided. General three-dimensional geometry, as well as specialized one-dimensional geometry descriptions, may be used with an albedo option available at any material surface. A detailed discussion of the relationship between forward and adjoint flux and collision densities, as well as a detailed description of the treatment of the angle of scattering, is given in the appendices. Logical flow charts for each subroutine add to the understanding of the code. Author

Subject Categories:

  • Theoretical Mathematics
  • Computer Programming and Software
  • Fission Reactor Physics

Distribution Statement:

APPROVED FOR PUBLIC RELEASE