Computer Programs

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES

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Program name | Package id | Status | Status date |
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MARMER | NEA-1307/01 | Tested | 24-JUN-1991 |

MARMER | NEA-1307/02 | Tested | 30-MAY-1994 |

Machines used:

Package ID | Orig. computer | Test computer |
---|---|---|

NEA-1307/01 | VAX under VMS | DEC VAX 8810 |

NEA-1307/02 | IBM PC | PC-80486 |

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3. DESCRIPTION OF PROGRAM OR FUNCTION

MARMER is a point-kernel shielding code which can be used to calculate the dose rate, energy absorption rate, energy flux or gamma-ray flux due to several sources at any point in a complex geometry. The geometry is described by the MARS geometry system which makes use of Combinatorial Geometry and an array repeating feature. Source spectra may be defined in several ways including an option to read a binary file containing nuclide concentrations, which has been calculated by ORIGEN-S. Therefore, MARMER makes use of a nuclide data library containing half life times, decay energies and gamma yields for over 1000 nuclides. To facilitate the use of ORIGEN-S, a preprocessor named PREORI is included for simple irradiation and decay problems. The spatial description of the source may be done in cartesian, cylindrical and spherical coordinates and the source strength as a function of the distance along the coordinate axes may be done in many different ways. Several sources with different spectra may be treated simultaneously. As many calculational points as needed may be defined.

MARMER is a point-kernel shielding code which can be used to calculate the dose rate, energy absorption rate, energy flux or gamma-ray flux due to several sources at any point in a complex geometry. The geometry is described by the MARS geometry system which makes use of Combinatorial Geometry and an array repeating feature. Source spectra may be defined in several ways including an option to read a binary file containing nuclide concentrations, which has been calculated by ORIGEN-S. Therefore, MARMER makes use of a nuclide data library containing half life times, decay energies and gamma yields for over 1000 nuclides. To facilitate the use of ORIGEN-S, a preprocessor named PREORI is included for simple irradiation and decay problems. The spatial description of the source may be done in cartesian, cylindrical and spherical coordinates and the source strength as a function of the distance along the coordinate axes may be done in many different ways. Several sources with different spectra may be treated simultaneously. As many calculational points as needed may be defined.

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4. METHOD OF SOLUTION

The source volume is divided into volume- elements and the source energy distribution is divided into energy groups. The unscattered gamma-ray flux is calculated by an exponential attenuation kernel, which is integrated over all source volume-elements and all energy group by use of a Monte Carlo integration method. The flux is then converted to the requested detector response by use of conversion factors, which are read from a binary file. Scattered gamma-rays are accounted for by buildup factors, which are tabulated in another binary file containing dose rate equivalent and energy absorption buildup factors. Buildup factors for each shield are calculated by interpolating for the effective atomic number of the shield. For multilayered shields the buildup factor of one shield or the methods of Kitazume or Broder may be used. Although all necessary data is read from binary files, attenuation coefficients, detector response functions and buildup factors may be given in the input too.

The source volume is divided into volume- elements and the source energy distribution is divided into energy groups. The unscattered gamma-ray flux is calculated by an exponential attenuation kernel, which is integrated over all source volume-elements and all energy group by use of a Monte Carlo integration method. The flux is then converted to the requested detector response by use of conversion factors, which are read from a binary file. Scattered gamma-rays are accounted for by buildup factors, which are tabulated in another binary file containing dose rate equivalent and energy absorption buildup factors. Buildup factors for each shield are calculated by interpolating for the effective atomic number of the shield. For multilayered shields the buildup factor of one shield or the methods of Kitazume or Broder may be used. Although all necessary data is read from binary files, attenuation coefficients, detector response functions and buildup factors may be given in the input too.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

MARMER can be subdivided into two parts: the MARS geometry system, where all geometric data is stored and handled, and the real shielding code, which is partly based on the MERCURE-IV shielding code. Both parts make use of flexible array dimensioning, so in principal there is no restriction on the complexity of the problem. There is, however, one exception: no more than 50 materials may be defined.

MARMER can be subdivided into two parts: the MARS geometry system, where all geometric data is stored and handled, and the real shielding code, which is partly based on the MERCURE-IV shielding code. Both parts make use of flexible array dimensioning, so in principal there is no restriction on the complexity of the problem. There is, however, one exception: no more than 50 materials may be defined.

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6. TYPICAL RUNNING TIME

CPU times for MARMER depend very much on the problem treated, especially on the complexity of the geometry, and can vary from a few seconds to tens of minutes per dose point on a

VAX 8350.

CPU times for MARMER depend very much on the problem treated, especially on the complexity of the geometry, and can vary from a few seconds to tens of minutes per dose point on a

VAX 8350.

NEA-1307/01

NEA-DB executed the different modules of this package on a VAX 8810 computer. The following CPU times were required to run the specified test cases. BINBCD: 7.4s (buildup factor); 3.8s (gamma data); 23.9 s (nuclide data). MARMER: 5.2 s (case 1); 344 scase 2); PICTURE: 2.6 s (case 1); PREORI: 1.0 s (vase 1); ORIGENS: 9.7 s (case 1).

NEA-1307/02

The test case of MARMER executed at NEA-DB on a 66-MHz PC/80486 in 20.7 seconds of elapsed time. The execution of BINBCD.EXE to produce the binary version of the three libaries MARISO (nuclide data), MARBUP (buildup factor data), and MARGAM (gamma data) takes, respectively, 17.7, 8.2; and 3.0 seconds of elapsed time.[ top ]

7. UNUSUAL FEATURES OF THE PROGRAM

MARMER has several options not available in other point-kernel shielding codes: the possibility to use nuclide concentrations calculated by ORIGEN-S to define source spectra, the flexible energy structure by use of "fine" energy groups which can be collapsed to "broad" groups depending on the problem under consideration, anisotropic sources (cos**p or arbritrary defined by points), which can be used to calculate the unscattered component of thes treaming radiation through ducts and gaps.

MARMER has several options not available in other point-kernel shielding codes: the possibility to use nuclide concentrations calculated by ORIGEN-S to define source spectra, the flexible energy structure by use of "fine" energy groups which can be collapsed to "broad" groups depending on the problem under consideration, anisotropic sources (cos**p or arbritrary defined by points), which can be used to calculate the unscattered component of thes treaming radiation through ducts and gaps.

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8. RELATED AND AUXILIARY PROGRAMS

ORIGEN-S with six data libraries can be used to calculate nuclide concentrations, PREORI can be used as a preprocessor to ORIGEN-S, BINBCD is used to convert the three MARMER libraries from ASCII or BCD to binary form and vice-versa, the MARS geometry package is used to describe the geometry, PICTURE may be used to print two-dimensional slices of geometry and JUNEBUG may be used to plot three-dimensional pictures of geometry.

ORIGEN-S with six data libraries can be used to calculate nuclide concentrations, PREORI can be used as a preprocessor to ORIGEN-S, BINBCD is used to convert the three MARMER libraries from ASCII or BCD to binary form and vice-versa, the MARS geometry package is used to describe the geometry, PICTURE may be used to print two-dimensional slices of geometry and JUNEBUG may be used to plot three-dimensional pictures of geometry.

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Package ID | Status date | Status |
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NEA-1307/01 | 24-JUN-1991 | Tested at NEADB |

NEA-1307/02 | 30-MAY-1994 | Tested at NEADB |

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10. REFERENCES

- O.W. Hermann, R.M. Westfall

ORIGEN-S: SCALE System Module to Calculate Fuel Depletion,

Actinide Transmutation, Fission Product Buildup and Decay, and

Associated Radiation Source Termes

NUREG/CR-200 Volume 2, Section F7, ORNL/NUREG/CSD-2/V2/R2.

- J.C. Ryman

ORIGEN-S Data Libraries

NUREG/CR-200 Volume 3, Section M6, ORNL/NUREG/CSD-2/V3/R2.

- M.B. Emmett, L.M. Petrie, J.T. West

JUNEBUG-II: A Three-Dimensional Geometry Plotting Code

NUREG/CR-200 Volume 3, Section F12, ORNL/NUREG/CSD-2/V3/R2.

- J.L. Kloosterman:

On Gamma-ray Shielding and Neutron Streaming through Ducts

PhD Thesis, IRI, Technical University of Delft (1992).

- O.W. Hermann, R.M. Westfall

ORIGEN-S: SCALE System Module to Calculate Fuel Depletion,

Actinide Transmutation, Fission Product Buildup and Decay, and

Associated Radiation Source Termes

NUREG/CR-200 Volume 2, Section F7, ORNL/NUREG/CSD-2/V2/R2.

- J.C. Ryman

ORIGEN-S Data Libraries

NUREG/CR-200 Volume 3, Section M6, ORNL/NUREG/CSD-2/V3/R2.

- M.B. Emmett, L.M. Petrie, J.T. West

JUNEBUG-II: A Three-Dimensional Geometry Plotting Code

NUREG/CR-200 Volume 3, Section F12, ORNL/NUREG/CSD-2/V3/R2.

- J.L. Kloosterman:

On Gamma-ray Shielding and Neutron Streaming through Ducts

PhD Thesis, IRI, Technical University of Delft (1992).

NEA-1307/01, included references:

- J.L. Kloosterman:MARMER - A Flexible Point-Kernel Shielding Code, User Manual

Version 2.0

IRI-131-89-03/2 (June 1990).

- J.L. Kloosterman:

MARMER - A Flexible Point-Kernel Shielding Code, Appendices

Ch. Devillers and C. Dupont:

MERCURE-4 - Un Programme de Monte Carlo a Trois Dimensions pour

l'Integration de Noyaux Ponctuels d'Attenuation en Ligne Droite

Note CEA-N-1726

J.T. West and M.B. Emmett:

MARS - A Multiple Array System Using Combinatorial Geometry

NUREG/CR-0200 V. 3, Section M9 ORNL/NUREG/CSD-2/V3/R2 (October

1981) Revised (December 1984).

M.B. Emmett:

PICTURE - A Printer Plot Package for Making 2-D Pictures of MARS

Geometries

NUREG/CR-0200 V. 3, Section M13 ORNL/NUREG/CSD-2/V3/R2 (December

1984).

IRI-131-89-03/2 (June 1990).

- J.L. Kloosterman:

Gamma Benchmark Calculations on the TN12 Spent Fuel Shipping Cask

IRI-131-89-11 (November 1989).

NEA-1307/02, included references:

- J.L. Kloosterman:MARMER - A Flexible Point-Kernel Shielding Code, User Manual

Version 2.0

IRI-131-89-03/2 (June 1990).

- J.L. Kloosterman:

MARMER - A Flexible Point-Kernel Shielding Code, Appendices

Ch. Devillers and C. Dupont:

MERCURE-4 - Un Programme de Monte Carlo a Trois Dimensions pour

l'Integration de Noyaux Ponctuels d'Attenuation en Ligne Droite

Note CEA-N-1726

J.T. West and M.B. Emmett:

MARS - A Multiple Array System Using Combinatorial Geometry

NUREG/CR-0200 V. 3, Section M9 ORNL/NUREG/CSD-2/V3/R2 (October

1981) Revised (December 1984).

M.B. Emmett:

PICTURE - A Printer Plot Package for Making 2-D Pictures of MARS

Geometries

NUREG/CR-0200 V. 3, Section M13 ORNL/NUREG/CSD-2/V3/R2 (December

1984).

IRI-131-89-03/2 (June 1990).

- J.L. Kloosterman:

Gamma Benchmark Calculations on the TN12 Spent Fuel Shipping Cask

IRI-131-89-11 (November 1989).

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11. MACHINE REQUIREMENTS

MARMER runs on VAX computers, but is probably runs on every 32 bits computer without problems.

NEA 1307/02: NEA-DB implemented the program on a PC DELL 466/L (processor 80486, 66 MHz, 16 MB of RAM).The file sizes of the executables are: 1170 Kbytes (MARMER.EXE); 562 Kbytes (BINBCD.EXE); 243 Kbytes (ORMARM.EXE); 352 KBytes (PICTURE.EXE). The file sizes of the BCD versions of the libraries included in this package are: 576 Kbytes (MARISO); 192 Kbytes (MARBUP); 104 Kbytes (MARGAM);

MARMER runs on VAX computers, but is probably runs on every 32 bits computer without problems.

NEA 1307/02: NEA-DB implemented the program on a PC DELL 466/L (processor 80486, 66 MHz, 16 MB of RAM).The file sizes of the executables are: 1170 Kbytes (MARMER.EXE); 562 Kbytes (BINBCD.EXE); 243 Kbytes (ORMARM.EXE); 352 KBytes (PICTURE.EXE). The file sizes of the BCD versions of the libraries included in this package are: 576 Kbytes (MARISO); 192 Kbytes (MARBUP); 104 Kbytes (MARGAM);

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Package ID | Computer language |
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NEA-1307/01 | FORTRAN-77 |

NEA-1307/02 | FORTRAN-77 |

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NEA-1307/01

VMS 5.3 (VAX 8810).NEA 1307/02: The programs were implemented under MS-DOS 6.2. The source codes were compiled with the Lahey F77L-EM/32 Version 5.11 Fortran-77 compiler.

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NEA-1307/01

File name | File description | Records |
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NEA1307_01.001 | This information file | 151 |

NEA1307_01.002 | Information for MARMER, BINBCD, PICTURE | 33 |

NEA1307_01.003 | Information for ORIGENS, PREORI | 25 |

NEA1307_01.004 | BINBCD Command file to compile and link | 3 |

NEA1307_01.005 | BINBCD Command file for execution | 34 |

NEA1307_01.006 | BINBCD FORTRAN source | 413 |

NEA1307_01.007 | MARBUP Biuldup factor library | 2490 |

NEA1307_01.008 | MARGAM Gamma data library | 1602 |

NEA1307_01.009 | MARISO Nuclide data library | 11547 |

NEA1307_01.010 | MARMER Command file to compile and link | 5 |

NEA1307_01.011 | MARMER FORTRAN source | 6010 |

NEA1307_01.012 | MARMER Command file for execution | 7 |

NEA1307_01.013 | MARMER Sample problem 1 | 63 |

NEA1307_01.014 | MARMER Sample problem 1 output | 577 |

NEA1307_01.015 | MARMER Sample problem 2 | 815 |

NEA1307_01.016 | MARMER Sample problem 2 output | 4922 |

NEA1307_01.017 | MARSMC FORTRAN source | 3987 |

NEA1307_01.018 | MARSUB FORTRAN source | 1080 |

NEA1307_01.019 | PREORI Command file to compile and link | 4 |

NEA1307_01.020 | PREORI FORTRAN source | 212 |

NEA1307_01.021 | PREORI Command file for execution | 15 |

NEA1307_01.022 | PREORI Sample problem | 10 |

NEA1307_01.023 | PREORI Sample problem output | 38 |

NEA1307_01.024 | PICTURE Command file to compile and link | 5 |

NEA1307_01.025 | PICTURE FORTRAN source | 299 |

NEA1307_01.026 | PICTURE Command file for execution | 4 |

NEA1307_01.027 | PICTURE Sample problem | 59 |

NEA1307_01.028 | PICTURE Sample problem output | 313 |

NEA1307_01.029 | ORIGENS Command file to compile and link | 4 |

NEA1307_01.030 | ORIGENS FORTRAN source | 10186 |

NEA1307_01.031 | ORIGENSMAIN FORTRAN source | 748 |

NEA1307_01.032 | ORIGENS Command file for execution | 11 |

NEA1307_01.033 | ORIGENS Sample problem | 38 |

NEA1307_01.034 | ORIGENS Sample problem output | 1358 |

NEA1307_01.035 | ORIGENS Sample problem output (by NEADB) | 694 |

NEA1307_01.036 | PHOACT Photon actinide library | 292 |

NEA1307_01.037 | PHOLITE Photon light element library | 653 |

NEA1307_01.038 | PHOFISP Photon fission product library | 547 |

NEA1307_01.039 | ACTINIDE Actinide library | 505 |

NEA1307_01.040 | SMALLITE Light element library | 1265 |

NEA1307_01.041 | SMALFISP Fission product library | 505 |

NEA-1307/02

File name | File description | Records |
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NEA1307_02.001 | MARMER Information File | 354 |

NEA1307_02.002 | MARMER Source code file # 1 | 6039 |

NEA1307_02.003 | MARMER Source code file # 2 | 3990 |

NEA1307_02.004 | MARMER Source code file # 3 | 1080 |

NEA1307_02.005 | Source code file of program BINBCD | 431 |

NEA1307_02.006 | Source code file of program ORMARM | 26 |

NEA1307_02.007 | Source code file of program PICTURE | 304 |

NEA1307_02.008 | Batch file to create the exec. MARMER.EXE | 23 |

NEA1307_02.009 | Batch file to create the exec. BINBCD.EXE | 15 |

NEA1307_02.010 | Batch file to create the exec. ORMARM.EXE | 15 |

NEA1307_02.011 | Batch file to create the exec. PICTURE.EXE | 23 |

NEA1307_02.012 | Batch file to create the exec. BINBCD.EXE | 22 |

NEA1307_02.013 | Aux. file to create binary library MARBUP | 2 |

NEA1307_02.014 | Aux. file to create binary library MARGAM | 2 |

NEA1307_02.015 | Aux. file to create binary library MARISO | 2 |

NEA1307_02.016 | Executable file of program MARMER | 0 |

NEA1307_02.017 | Executable file of program ORMARM | 0 |

NEA1307_02.018 | Executable file of program BINBCD | 0 |

NEA1307_02.019 | Executable file of program PICTURE | 0 |

NEA1307_02.020 | MARBUP - Library of buildup factor data | 2490 |

NEA1307_02.021 | MARGAM - Library of gamma data | 1602 |

NEA1307_02.022 | MARISO - Library of nuclide data | 8061 |

NEA1307_02.023 | Binary version of library MARBUP.LIB | 0 |

NEA1307_02.024 | Binary version of library MARGAM.LIB | 0 |

NEA1307_02.025 | Binary version of library MARISO.LIB | 0 |

NEA1307_02.026 | Sample ORIGEN output vector | 245 |

NEA1307_02.027 | Nuclide binary data file | 0 |

NEA1307_02.028 | Sample input data file for MARMER | 63 |

NEA1307_02.029 | Sample output data file (MARMER results) | 577 |

NEA1307_02.030 | DOS file-names | 29 |

Keywords: Monte Carlo method, absorption, buildup, dose rates, gamma radiation, point kernels, shielding.