1. NAME AND TITLE
MARMER: A Flexible Point-Kernel Shielding Code System.
AUXILIARY ROUTINES
PICTURE: Two-dimensional Geometry Plotting Code.
PREORI: Pre-processor for ORIGEN-S Code. (Included in Vax package)
ORIGEN-S: Fission Products Inventory Code. (Included in Vax package)
BINBCD: Program To Convert BCD Data To Binary Form.
DATA LIBRARIES
MARBUP.BCD: Buildup Factors Based On ANSI 6.4.3. (Only in Vax version.)
MARGAM.BCD: Gamma Interaction Coefficients Based on JEF-1.1. (Only in Vax version.)
MARISO.BCD: Gamma Decay Data Based on JEF-1.1.
2. CONTRIBUTORS
Delft University of Technology, The Netherlands through the NEA Data Bank, Gif-sur-Yvette, France.
3. CODING LANGUAGE AND COMPUTER
FORTRAN 77; VAX 8350. (C00579D835000)
MSDOS6.2; F77L-EM/32 FORT 77. (C00579PC48600)
4. NATURE OF PROBLEM SOLVED
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 in the VAX version, 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.
5. 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 groups 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.
6. RESTRICTIONS OR LIMITATIONS
MARMER can be subdivided in 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 makes use of flexible array dimensioning, so in principle there is no restriction on the complexity of the problem. There is however one exception: no more than 50 materials may be defined.
The PC version is based on the 1990 VAX release. Although the PC version does NOT include ORIGEN-S and PREORI, it allows one to use ORIGEN-2 (PCH) output for specifying nuclide composition.
7. TYPICAL RUNNING TIME
CPU times for MARMER depend 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. The first sample problem took about 10 seconds; the second sample problem took 14 minutes and 49 seconds.
8. COMPUTER HARDWARE REQUIREMENTS
The code will run on the VAX family of computers and PC486.
9. COMPUTER SOFTWARE REQUIREMENTS
The code is written in FORTRAN 77. On the VAX 6000, the compiler used was VAX FORTRAN under the VAX/VMS operating system. On the PC version, the compiler used was Lahey F77L/EM/32 Version 5.11 to create the executables included in the package.
10. REFERENCES
a. Included in the package:
J. L. Kloosterman, "MARMER, A Flexible Point-Kernel Shielding Code, User's Manual," 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).
b. Background information:
J. T. West, and M. B. Emmett, "MARS: A Multiple Array System Using Combinatorial Geometry," NUREG/CR-200, Volume 3, Section M9, ORNL/NUREG/CSD-2/V3/R2.
O. W. Hermann, and R. M. Westfall, "ORIGEN-S: SCALE System Module to Calculate Fuel Depletion, Actinide Transmutation, Fission Product Buildup and Decay, and Associated Radiation Source Terms," NUREG/CR-200, Volume 2, Section F7, ORNL/NUREG/CSD-2/V2/R2.
C. Devillers, and C. Dupont, "MERCURE-IV, Un Programma de Monte-Carlo a Trois Dimensions Pour L'Integration de Noyaux Ponctuels d'Attenuation en Ligne Droite," note CEA-N-1276.
J. C. Ryman, "ORIGEN-S Data Libraries," NUREG/CR-200, Volume 3, Section M6, ORNL/NUREG/CSD-2/V3/R2.
M. B. Emmett, "PICTURE: A Printer Plot Package for Making 2-Dimensional Pictures of MARS Geometries," NUREG/CR-200, Volume 2, Section M13, ORNL/NUREG/CSD-2/V3/R2.
M. B. Emmett, L. M. Petrie, and J. T. West, "JUNEBUG-II: A Three-Dimensional Geometry Plotting Code," NUREG/CR-200, Volume 3, Section F12, ORNL/NUREG/CSD-2/V3/R2.
11. CONTENTS OF CODE PACKAGE
Included are the referenced documents in (10.a) and one DS/HD 3.5" diskette (1.44MB), containing the source codes, data libraries and other pertinent files. The PC version is transmitted on one DS/HD 3.5" (1.44MB) diskette in a self extracting compressed DOS file.
12. DATE OF ABSTRACT
January 1991, March 1999.
KEYWORDS: COMPLEX GEOMETRY; FISSION PRODUCT INVENTORY; FISSION PRODUCTS; GAMMA-RAY; ISOTOPE INVENTORY; MONTE CARLO; KERNEL; TWO-DIMENSIONS; MICROCOMPUTER