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CCC-0127 MORSE.

MORSE, MultiGroup Neutron Transport and Gamma Transport for Complex Geometry Shields by Monte-Carlo
MORSE-E, Program MORSE with Uniform Source for Various Geometry

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1. NAME OR DESIGNATION OF PROGRAM:  MORSE.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
MORSE-H CCC-0127/05 Tested 26-JUL-1983
MORSE-E1 CCC-0127/06 Tested 18-OCT-1983

Machines used:

Package ID Orig. computer Test computer
CCC-0127/05 IBM 3081 IBM 3081
CCC-0127/06 IBM 3081 IBM 3081
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3. NATURE OF PHYSICAL PROBLEM SOLVED

The MORSE code is a multipurpose  neutron and gamma-ray transport Monte Carlo code. It has been 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, as well as specialized one-dimensional geometry descriptions, 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.
MORSE-E1 - This is a new analysis package written by ESIS at Ispra.  It can be used with the O5R geometry or with the combinatorial geometry as with any other geometry compatible with MORSE. It contains a flexible set of subprograms tailored to solve a variety of shielding problems. It provides uniform source distributions of several geometrical shapes, and calculates particle fluxes and reaction rates integrated over the volumes defined by the user. Currents of particles through surfaces may be calculated.
MORSE-H has been developed from MORSE-CG (CCC-0203) and MORSE-E. The special features of this version are:
1) Track-length (volume integrated flux) or next event (point flux)  estimates;
2) multiple source region specification;
3) flexible source direction options;
4) restartable in all classes of problems;
5) eigenvalue (keff) solution obtainable even if keff is significantly differenty from unity.
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4. 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 discrete ordinates codes may be used as input; either ANISN, DTF-4 or DOT cross section formats are acceptable.
Anisotropic scattering is treated for each group-to-group transfer by utilizing a generalized Gaussian quadrature technique.
The MORSE code is organized into functional modules with simplified  interfaces such that new modules may be incorporated with reasonable ease. The modules are (1) random walk, (2) cross section, (3) geometry, (4) analysis, and (5) diagnostic.
While the basic MORSE code assumes the analysis module is user-written, a general analysis package, SAMBO, has been developed. SAMBO handles most of the drudgery associated with the analysis of random walks and minimizes the amount of user-written coding. An arbitrary number of detectors, energy-dependent response functions,  energy bins, time bins, and angle bins are allowed. Analysis is divided for each detector as follows - uncollided and total response, fluence versus energy, time-dependent response, fluence versus time and energy, and fluence versus angle and energy. Each of these quantities is listed as output. The diagnostic module provides an easy means of printing out, in useful form, the information in the various labelled common and any part of blank common. This module is very useful to debug a problem and to gain further insight into the physics of the random walk.
MORSE-H uses in a weighted-tracking scheme a track-length as next- event event estimation of neutron and photon fluxes.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
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6. TYPICAL RUNNING TIME

The running time is wholly dependent on the complexity of the geometry, the number of "detectors" employed and accuracy desired. It may range from 30 seconds to 30 hours.
MORSE-H (CCC-0127/05): NEA-DB executed the included test case on IBM 3081 in 245 CPU seconds.
MORSE-E1 (CCC-0127/06): NEA-DB executed the included test case on IBM 3081 in 25 CPU seconds.
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7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM
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8. RELATED AND AUXILIARY PROGRAMS

SAMBO - collision analysis code.
PICTURE - geometry input diagnostic code.
MORSE was originally programmed for the CDC 1604 and was later modified and extended for the IBM 360. The original version was packaged (A, January 1970) but is not kept up-to-date by the originators.
See also advanced version MORSE-CG.
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9. STATUS
Package ID Status date Status
CCC-0127/05 26-JUL-1983 Tested at NEADB
CCC-0127/06 18-OCT-1983 Tested at NEADB
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10. REFERENCES

- V.R. Cain:
  'SAMBO, A Collision Analysis Package for Monte Carlo Doses'
  ORNL-TM-3203 (September 1970).
- D.C. Irving and G.W. Morrison:
  'PICTURE, An Aid in Debugging Geom Input Data'
  ORNL-TM-2892 (May 1970).
- D.C. Irving:
'The Adjoint Boltzmann Equation and its Simulation by Monte Carlo'    ORNL-TM-2879 (May 1970).
- C. Ponti and R. Van Heusden:
  'MORSE-E, A New Version of the MORSE Code'
  EUR.5212 (1974).
CCC-0127/05, included references:
- E.A. Straker, P.N. Stevens, D.C. Irving, V.R. Cain:
  The MORSE Code - A Multigroup Neutron and Gamma-Ray Monte Carlo
  Transport Code
  ORNL-4585 (September 1970)
- N.P. Taylor and J. Needham:
  MORSE-H: A Revised Version of the Monte Carlo Code MORSE.
  Revision of AERE-R 10432  (October 1982)
- J. Needham:
  Letter (28 January 1983)
CCC-0127/06, included references:
- E.A. Straker, P.N. Stevens, D.C. Irving, V.R. Cain:
  The MORSE Code - A Multigroup Neutron and Gamma-Ray Monte Carlo
  Transport Code
  ORNL-4585 (September 1970)
- C. Ponti and R. Van Heusden:
  MORSE-E1 - Source and Analysis Routines to be used with the
  MORSE Code.  JRC - Ispra  (November 1982)
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11. MACHINE REQUIREMENTS

Absolute minimum core requirement is 240 kbytes, but a typical problem will require at least 700 kbytes.
MORSE-H (CCC-0127/05): To execute the test case on IBM 3081, main storage requirements are 704K bytes.
MORSE-E1 (CCC-0127/06): To execute the test case on IBM 3081, main storage requirements are 316K bytes.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
CCC-0127/05 FORTRAN+ASSEMBLER
CCC-0127/06 FORTRAN+ASSEMBLER
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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  MVS-SP (IBM 3081).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHOR

Oak Ridge National Laboratory
Oak Ridge
Tennessee, U.S.A.

EURATOM CCR
Ispra, Italy

AERE Harwell
Oxfordshire
United Kingdom
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16. MATERIAL AVAILABLE
CCC-0127/05
File name File description Records
CCC0127_05.001 MORSE-H INFORMATION FILE 79
CCC0127_05.002 MORSE-H MAIN PROGRAM (FORTRAN-4) 27
CCC0127_05.003 RANDOM WALK MODULE (FORTRAN-4) 3115
CCC0127_05.004 CROSS SECTION MODULE (FORTRAN-4) 2384
CCC0127_05.005 GEOMETRY MODULE (FORTRAN-4) 1490
CCC0127_05.006 SOURCE MODULE (FORTRAN-4) 436
CCC0127_05.007 POINT-DETECTOR SCORING MODULE (FORTRAN-4) 848
CCC0127_05.008 TRACK-LENGTH SCORING MODULE (FORTRAN-4) 461
CCC0127_05.009 MORSE-H SOURCE (ASSEMBLER) 1375
CCC0127_05.010 RANDOM NUMBER ROUTINES (FORTRAN-4) 157
CCC0127_05.011 HELP ROUTINES 393
CCC0127_05.012 MORSE-H JCL 91
CCC0127_05.013 MORSE-H INPUT DATA FOR TEST CASE 70
CCC0127_05.014 CROSS SECTION LIBRARY (BINARY) 7
CCC0127_05.015 MORSE-H PRINTED OUTPUT OF TEST CASE 1931
CCC0127_05.016 TEXT OF USER MANUAL 55
CCC-0127/06
File name File description Records
CCC0127_06.003 MORSE-E1 INFORMATION FILE 74
CCC0127_06.004 MORSE-E1 MAIN PROGRAM (FORTRAN-4) 41
CCC0127_06.005 MORSE ORIGINAL PROGRAM (FORTRAN-4) 3946
CCC0127_06.006 MORSE-E1 SUBROUTINES (FORTRAN-4) 745
CCC0127_06.007 CYLINDRICAL GEOMETRY PACKAGE (FORTRAN-4) 440
CCC0127_06.008 RANDOM NUMBER GENER. & AUX. ROUTINES (ASM) 1463
CCC0127_06.009 ALTERNATIVE RANDOM NO. GENERATOR (FORTRAN4) 157
CCC0127_06.010 SLAB GEOMETRY PACKAGE (FORTRAN-4) 258
CCC0127_06.011 SPHERICAL GEOMETRY PACKAGE (FORTRAN-4) 182
CCC0127_06.012 GENERAL GEOMETRY PACKAGE (FORTRAN-4) 1152
CCC0127_06.013 MORSE-E1 JCL 26
CCC0127_06.014 MORSE-E1 INPUT DATA FOR TEST CASE 185
CCC0127_06.015 MORSE-E1 PRINTED OUTPUT OF TEST CASE 498
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17. CATEGORIES
  • C. Static Design Studies
  • J. Gamma Heating and Shield Design

Keywords: Monte Carlo method, angular distribution, anisotropic scattering, criticality, cross sections, gamma radiation, multigroup, neutron transport theory, one-dimensional, shielding, three-dimensional, time dependence.