1. NAME AND TITLE
MORSE-B: General Purpose Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. We recommend C00474/ALLCP/02 MORSE-CGA.
MORSE-B is a revised version of the Monte Carlo code MORSE.
MORSE-CG: General Purpose Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code with Combinatorial Geometry.
University of Birmingham, Birmingham, England.
3. CODING LANGUAGE AND COMPUTER
Fortran IV, Assembler language; IBM 370/3033.
4. NATURE OF PROBLEM SOLVED
The original MORSE code was a multipurpose neutron and gamma-ray transport Monte Carlo code. It was designed as a tool for solving most shielding problems. Through the use of multigroup cross sections, the solution of neutron, gamma-ray, or coupled neutron-gamma-ray problems could be obtained in either the forward or adjoint mode. Time dependence for both shielding and criticality problems is provided. General three-dimensional geometry could be used with an albedo option available at any material surface. Isotropic or anisotropic scattering up to a P16 expansion of the angular distribution was allowed.
MORSE-CG incorporated the Mathematical Applications, Inc. (MAGI) combinatorial geometry routines.
MORSE-B modifies the Monte Carlo neutron and photon transport computer code MORSE-CG by adding routines which allow various flexible options.
5. METHOD OF SOLUTION
MORSE-B provides options for flux scoring, source region specification, and response rate calculations. These can be done in a more flexible way than in MORSE-CG.
6. RESTRICTIONS OR LIMITATIONS
7. TYPICAL RUNNING TIME
The sample problem executed in 1 minute 48 seconds on the IBM 370/3033.
8. COMPUTER HARDWARE REQUIREMENTS
The code is designed to operate on the IBM 370/3033 computers. It requires 732 K of storage.
9. COMPUTER SOFTWARE REQUIREMENTS
Fortran H and Assembler compilers with override regions are required.
a. included in documentation:
N. P. Taylor, "MORSE-B A Revised Version of the Monte Carlo Code MORSE."
b. background information:
M. B. Emmett, "Collision Site Plotting Routines and Collision Density Estimates for MORSE," Informal Notes (September 1978).
J. W. Kinch, "MORSE Routines for the UNIVAC 1108," (June 1975).
M. B. Emmett, "The MORSE Monte Carlo Radiation Transport Code System," ORNL-4972 (February 1975).
M. B. Emmett, C. E. Burgart, and T. J. Hoffman, "DOMINO, A General Purpose Code for Coupling Discrete Ordinates and Monte Carlo Radiation Transport Calculations," ORNL-4853 (July 1973).
University of Wisconsin, "Three-Dimensional Neutronics for a Fusion Reactor Non-Mobile Gas-Cooled Solid Blanket," UWFDM-92 (1975).
E. A. Straker and M. B. Emmett, "Collision Site Plotting Routines and Collision Density Fluence Estimates for the Monte Carlo Code," ORNL-TM-3585 (October 1971).
M. B. Emmett, "DOMINO-II, A General Purpose Code for Coupling DOT-IV Discrete Ordinates and Monte Carlo Radiation Transport Calculations," ORNL/TM-7771 (May 1981).
11. CONTENTS OF CODE PACKAGE
Included are the referenced documents and one (1.2MB) DOS diskette which contains the source codes and sample problem input and output.
12. DATE OF ABSTRACT
February 1982, updated August 1991.
KEYWORDS: MONTE CARLO; NEUTRON; GAMMA-RAY; MULTIGROUP; COMPLEX GEOMETRY; COMBINATORIAL GEOMETRY; ADJOINT