**1. NAME AND TITLE**

MORSE-E: Special Purpose Monte Carlo Multigroup Neutron and Gamma-Ray Transport
Code System. We recommend C00474/ALLCP/02 MORSE-CGA.

**AUXILIARY ROUTINES**

Random Number Generator.

Alternative Random Number Generator.

Cylindrical Geometry Routine.

Slab Geometry Routine.

Spherical Geometry Routine.

General Geometry Routine.

MORSE was originally programmed at the Oak Ridge National Laboratory for the CDC 1604
(CCC-127, 1970) and was later modified and extended for the IBM 360. The original version
incorporated the CCC-017/05R geometry routines. The MAGI (Mathematical Applications Group,
Inc.) combinatorial geometry routines are currently used in the Oak Ridge National Laboratory
(ORNL) version, CCC-203/MORSE-CG. In these codes, certain routines must be written for a
specific problem. MORSE-E, based on the ORNL work, seeks to facilitate practical use of the
MORSE codes. It is also available from NEA CPL as Abstract C-127.

**2. CONTRIBUTOR**

The CCR EURATOM European Shielding Information Service (ESIS) through OECD Nuclear
Energy Agency's Computer Programme Library (NEA CPL), Ispra, Italy.

**3. CODING LANGUAGE AND COMPUTER**

FORTRAN IV; IBM 360/370.

**4. NATURE OF PROBLEM SOLVED**

MORSE is a neutron and gamma-ray transport Monte Carlo code. MORSE-E enlarges
application and use of the MORSE code system by easing the job of adapting the code to a
particular problem. It calculates practical fluxes and reaction rates averaged over the volume of the
zones requested by the user. The corresponding standard deviation is also computed. It may
consider isotropic sources uniformly distributed over a volume. The geometry of the source can be
parallelepiped, sphere, or cylinder. MORSE-E handles ``normal'' media (for which cross section
is specified) and ``special'' media (cross section set need not be specified, e.g., internal voids,
external voids, albedo media).

**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 in PSR-063/AMPX format such as those used in several
discrete ordinates codes may be used as input. 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-E.

**8. COMPUTER HARDWARE REQUIREMENTS**

MORSE-E is operable on the IBM 360/370 computers.

**9. COMPUTER SOFTWARE REQUIREMENTS**

A FORTRAN IV compiler is required.

**10. REFERENCES**

C. Ponti, R. Van Heuscen, "MORSE-E, A New Version of the MORSE Code ESIS," EUR1512e (1974).

E. A. Straker, P. N. Stevens, D. C. Irving, and V. R. Cain, "The MORSE CodeA
Multigroup Neutron and Gamma-Ray Monte Carlo Transport Code," ORNL-4585 (September
1970).

**11. CONTENTS OF CODE PACKAGE**

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

**12. DATE OF ABSTRACT**

August 1975; revised January 1983.

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