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