The MORSE code is a multipurpose neutron and gamma-ray xransport 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 ir pxovided. General three-dimensional geometry, as well as specialized one-dimensional geometry descriptions, may be used with an albedo option av.ulable at any material surface. Standard multigroup cross sections such as those used in discrete ordinates codes may be used as input; either ANISN or DTP-IV cross-section formats are acceptable. Anisotropic scattering is treated for each groupto-group transfer by utilizing a generalized Gaussian quadrature technique. The modular form of the code with built-in analysis capability for all types of estimators makes it possible to solve a complete neutron-gammaray problem as one job and without the use of tapes. 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. viii

No abstract

No abstract

No abstract

No abstract