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

Personal Author(s):

• Straker,E. A.
• Stevens,P. N.
• Irving,D. C.
• Cain,V. R.

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

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