NEA-1562 MICROX-2.
MICROX-2, Group Constant Generator with Resonance Interference and Self-Shielding
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHODS, RESTRICTIONS, TYPICAL RUNNING TIME, FEATURES, RELATED OR AUXILIARY PROGRAMS, STATUS, REFERENCES, HARDWARE REQUIREMENTS, LANGUAGE, SOFTWARE REQUIREMENTS, OTHER RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES
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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 |
|---|---|---|---|
| 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.
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).
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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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.
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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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.
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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NEA-1562/02, included references:
- D. MathewsAn 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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| Package ID | Computer language |
|---|---|
| NEA-1562/02 | FORTRAN-90, FORTRAN-95 |
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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
Keywords: group constants, leakage, neutron cross sections, resonance absorption, self-shielding.