Computer Programs

MORSE-E, Program MORSE with Uniform Source for Various Geometry

NAME OR DESIGNATION OF PROGRAM, COMPUTER, NATURE OF PHYSICAL PROBLEM SOLVED, METHOD OF SOLUTION, RESTRICTIONS, TYPICAL RUNNING TIME, FEATURES, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED, OTHER RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES

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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.

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.

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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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.

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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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.

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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Package ID | Status date | Status |
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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).

- 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.

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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Package ID | Computer language |
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CCC-0127/05 | FORTRAN+ASSEMBLER |

CCC-0127/06 | FORTRAN+ASSEMBLER |

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CCC-0127/05

File name | File description | Records |
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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 |
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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 |

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