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NEA-1562 MICROX-2.

MICROX-2, Group Constant Generator with Resonance Interference and Self-Shielding

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1. NAME OR DESIGNATION OF PROGRAM:  MICROX-2
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2. COMPUTERS
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Program name Package id Status Status date
MICROX-2 NEA-1562/02 Tested 24-MAY-2004

Machines used:

Package ID Orig. computer Test computer
NEA-1562/02 IBM PC,Linux-based PC Linux-based PC,PC Windows
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3. DESCRIPTION OF PROGRAM OR FUNCTION

The MICROX-2 code prepares broad group neutron cross sections for use in diffusion- and/or transport-theory codes from an input library of fine group and pointwise cross sections. The MICROX-2 code can explicitly account for overlap and  interference effects between resonances in both the
resonance and thermal neutron  energy ranges and allows the simultaneous treatment of leakage and resonance self-shielding in doubly heterogeneous lattice cells.
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4. METHODS

  The neutron weighting spectrum is obtained by solving the B1 neutron balance equations at about 10000 energies in a one- dimensional (planar, spherical or cylindrical), two-region unit cell. The regions are coupled by collision probabilities based upon spatially flat neutron emission. Energy dependent Dancoff factors and bucklings correct the one-dimensional cell calculations for multi- dimensional lattice effects. A critical buckling search option is also included. The inner region may include two different types of fuel particles (grains).
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
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6. TYPICAL RUNNING TIME

Many  of the parameterized dimensions  were changed to  odd numbers to minimize memory access time on CRAY computers. - The vectorization is quite successful. For example, Ed. 13 running times with and with-out vectorisation for the TRX-1 CSEWG benchmark using 193 group JEF-1 data are given. The  cft77 version 3.1 FORTRAN compiler on the ETHZ  CRAY-X/MP28  computer was used. An average 0.385 megawords was used.
On PC it took a few seconds.
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7. UNUSUAL FEATURES
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8. RELATED OR AUXILIARY PROGRAMS

The package contains the MICROR NJOY compatible module. It is a reformatting module that produces cross-sections library files for the MICROX-2 and MICROBURN postprocessor codes. Using the data on the pointwise and groupwise NJOY tapes, MICROR produces the tapes containing basic nuclear data, FDTAPE, GAR and GGTAPE used by two-region spectrum codes MICROX and MICROX-2 and by two-region spectrum burn-up code MICROBURN.
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9. STATUS
Package ID Status date Status
NEA-1562/02 24-MAY-2004 Tested at NEADB
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10. REFERENCES
NEA-1562/02, included references:
- D. Mathews
An Improved Version of the MICROX-2 Code"
PSI Bericht Nr. 97-11 (November 1997)
- D. Mathews
Appendices B to E of PSI-Report No. 97-11 "An Improved Version of the MICROX-2
TM-41-97-17 (November 1997)
- D.R. Mathews, J. Stepanek, S Pelloni, C.E. Higgs
The NJOY Nuclear Data Processing System: The MICROR Module
EIR-Beiricht Nr. 539 (December 1984)
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11. HARDWARE REQUIREMENTS

  The PSI version of the MICROX-2 code operates on the CRAY J90 and CRAY-Y/MP computers using the UNICOS 9 operating system and the f90 FORTRAN compiler, as well as on an IBM PC with the Lahey LF90 FORTRAN compiler.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-1562/02 FORTRAN-90, FORTRAN-95
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13. SOFTWARE REQUIREMENTS:  MICROX-2 runs under UNICOS and DOS operating systems
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHORS

                D. Mathews
                Paul Scherrer Institut
                CH - 5232 Villigen PSI
                SWITZERLAND
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16. MATERIAL AVAILABLE
NEA-1562/02
README.TXT  Installation instructions
/data/gendfc/ DOS procedure and data files
/data/libraries/ Data files
/data/pendfc/ DOS procedure and data files
/doc/ PDF documentation
/outputs/micror/ Test outputs
/outputs/microx2/ Test outputs
/runs/ linux scripts and DOS procedures
/source/ Makefile (linux only) and MICROR and MICROX-2 Fortran sources
readme.now  Information file
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17. CATEGORIES
  • B. Spectrum Calculations, Generation of Group Constants and Cell Problems

Keywords: group constants, leakage, neutron cross sections, resonance absorption, self-shielding.