
Accession Number : AD0711941
Title : THE MORSE CODE  A MULTIGROUP NEUTRON AND GAMMARAY 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 gammaray transport Monte Carlo code. Through the use of multigroup cross sections, the solution of neutron, gammaray, or coupled neutrongammaray problems may be obtained in either the forward or adjoint mode. Time dependence for both shielding and criticality problems is provided. General threedimensional geometry, as well as specialized onedimensional 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