1. NAME AND TITLE

MORSE-SGC: A Super Grouped Cross Section Version of the MORSE Code System. We recommend C00474/ALLCP/02 MORSE-CGA or C00545/IRISC/01 SCALE 4.2.

AUXILIARY ROUTINE

LAVA: Cross Section Processor.

PICTURE: Geometry Debugging Code.

SCEPLOT: Distributed Source Update Code.

2. CONTRIBUTORS

Oak Ridge National Laboratory, Oak Ridge, Tennessee.

Sandia National Laboratories, Albuquerque, New Mexico.

3. CODING LANGUAGE AND COMPUTER

FORTRAN IV and Assembler language; IBM 360/370 (A) or CDC 7600 (B).

4. NATURE OF PROBLEM SOLVED

MORSE-SGC is a multipurpose neutron and gamma-ray transport Monte Carlo code system 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 may be obtained in either the forward or adjoint mode. Time dependence for both shielding and criticality problems is provided. General three-dimensional geometry may be used with an albedo option available at any material surface. Isotropic or anisotropic scattering up to a P16 expansion of the angular distribution is allowed. It will accept geometry descriptions either of the combinatorial geometry type or of the KENO (array) type. Core storage requirements for cross sections are reduced by using direct access storage when needed.

5. METHOD OF SOLUTION

Monte Carlo methods are used to solve the forward and the adjoint transport equations. Quantities of interest are then obtained by summing the contributions over all collisions, and frequently over most of phase space.

Standard multigroup cross sections such as those used in the PSR-63/AMPX-II code system may be used as input; CCC-82/ANISN cross section formats may be converted to the PSR-63/AMPX-II AMPX format using the LAVA code. Anisotropic scattering is treated for each group-to-group transfer by utilizing a generalized Gaussian quadrature technique.

6. RESTRICTIONS OR LIMITATIONS

None noted.

7. TYPICAL RUNNING TIME

No study has been made by RSIC of typical running times for MORSE-SGC.

8. COMPUTER HARDWARE REQUIREMENTS

MORSE-SGC is operable on the IBM 360/370 (A) or the CDC 7600 (B) computers.

9. COMPUTER SOFTWARE REQUIREMENTS

A FORTRAN IV compiler is required. All non-standard library routines which are needed by the code have been included in the package.

10. REFERENCES

M. B. Emmett, "The MORSE Monte Carlo Radiation Transport Code System," ORNL-4972 (February 1975).

S. K. Fraley, "Users Guide to MORSE-SGC," ORNL/CSD-7 (March 1976).

S. K. Fraley, "A User's Guide for LAVA, as issued with MORSE_SGC," ORNL/CSD-11 (June 1976).

Stephen A. Dupree and Ruth E. Lighthill, "Sandia National Laboratories CDC 7600 Version of MORSE-SGC," SAND80-1337 (February 1982).

11. CONTENTS OF CODE PACKAGE

Included are the referenced document and one (1.2MB) DOS diskette which contains the source codes and sample problem input and output.

12. DATE OF ABSTRACT

May 1976; updated January 1983, August 1985.

KEYWORDS: MONTE CARLO; NEUTRON; GAMMA-RAY; MULTIGROUP; ADJOINT; COMPLEX GEOMETRY