Accession Number : AD0711941

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

Corporate Author : OAK RIDGE NATIONAL LAB TENN

Personal Author(s) : Straker,E. A. ; Stevens,P. N. ; Irving,D. C. ; Cain,V. R.

Report Date : SEP 1970

Pagination or Media Count : 312

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)

Descriptors :   (*TRANSPORT PROPERTIES, MONTE CARLO METHOD), GAMMA RAYS, NEUTRON TRANSPORT THEORY, NUMERICAL METHODS AND PROCEDURES, SUBROUTINES, ALGORITHMS, SHIELDING, MATHEMATICAL MODELS, CRITICAL ASSEMBLIES, ANISOTROPY, SCATTERING, COMPUTER PROGRAMMING, INTEGRAL EQUATIONS

Subject Categories : Theoretical Mathematics
      Computer Programming and Software
      Fission Reactor Physics

Distribution Statement : APPROVED FOR PUBLIC RELEASE