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PSR-0350 MC**2-2.

MC*2-2, Calculation of Fast Neutron Spectra and Multigroup Cross-Sections from ENDF/B Data

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1. NAME OR DESIGNATION OF PROGRAM:  MC**2-2.
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2. COMPUTERS
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
MC**2-2 PSR-0350/01 Arrived 19-DEC-2001

Machines used:

Package ID Orig. computer Test computer
PSR-0350/01 SUN W.S.,IBM RISC6000 WS
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3. DESCRIPTION OF PROGRAM OR FUNCTION

MC**2-2 solves the neutron slowing-down equations using basic neutron data derived from ENDF/B data files to determine fundamental mode spectra for use in generating multigroup neutron cross sections. The current edition includes the ability to treat all ENDF/B-V and -VI data representations. It accommodates high-order P scattering representations and provides numerous capabilities such as isotope mixing, delayed neutron processing, free-format input, and flexibility in output data selection.

This edition supersedes previous releases of the MC22 program and the earlier MC2 program. Improved physics algorithms and increased computational efficiency are incorporated.
Input data files required by MC2-2 may be generated from ENDF/B data by the code ETOE-2. The hyper-fine-group integral transport theory module of MC2-2, RABANL, is an improved version of the RABBLE/RABID codes. Many of the MC2-2 modules are used in the SDX code.
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4. METHODS

The extended transport P1, B1, consistent P1, and consistent B1 fundamental mode ultra-fine-group equations are solved using continuous slowing-down theory and multigroup methods. Fast and accurate resonance integral methods are used in the narrow resonance resolved and unresolved resonance treatments. A fundamental mode homogeneous unit cell calculation is performed using either a multigroup or a continuous slowing-down treatment. Multigroup neutron homogeneous cross sections are generated in an ISOTXS format for an arbitrary group structure. A hyper-fine-group integral transport slowing down calculation (RABANL) is available as an option. RABANL performs a homogeneous or heterogeneous (pin or slab) unit cell calculation over the resonance region (resolved and unresolved) and generates multigroup neutron cross sections in an ISOTXS format. Neutron cross sections are generated by RABANL for the homogeneous unit cell and for each heterogeneous region in the pin or slab unit cell calculation.

Extreme flexibility is provided in specifying the rigor of a calculation including a choice of four distinct slowing-down treatments: multigroup, improved and standard Greuling-Goertzel continuous slowing-down, and integral transport theory. All binary data transfers are localized in CCCC standard subroutines REED/RITE. Broad group cross-section files may be generated in the ARC System XS.ISO (Ref. 7) and CCCC ISOTXS (Ref. 9) formats.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The program uses variable dimensioning throughout so that computer storage requirements depend on a variety of problem parameters. Space requirements are approximately 2000 K bytes on RS6000 or SUN equipment depending on the complexity of the problem.
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6. TYPICAL RUNNING TIME

A 1740-group consistent P1 homogeneous twelve-isotope problem with 27 broad groups requires about 3.25 minutes of CPU time on the IBM RS/6000 and the SS20 SUN systems. On an IBM RS/6000 Model 270, the heterogeneous test case ran in 12 seconds; and the homogeneous test case ran in 40 seconds.
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7. UNUSUAL FEATURES
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8. RELATED OR AUXILIARY PROGRAMS

AUXILIARY DATA LIBRARIES:

The MC2-2 libraries consist of ten files, one ASCII file (ADELAY) and nine binary files (MCC2F1-MCC2F8, and THERM). The MC2-2 libraries contain 357 isotopes of version 5 ENDF/B data. All version 5 data that was distributed and had complete data (i.e. ENDF/B files 1 thru 5) have been processed and are in this library. The ENDF/B-VI derived data in the MC2-2 libraries are still being tested by the developers at ANL and will be released at a later date.
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9. STATUS
Package ID Status date Status
PSR-0350/01 19-DEC-2001 Masterfiled Arrived
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10. REFERENCES

- L. C. Just, H. Henryson, II, A. S. Kennedy, S. D. Sparck, B. J. Toppel, and P. M. Walker:
"The System Aspects and Interface Data Sets of the Argonne Reactor Computation (ARC) System," ANL-7711 (April 1971).

- C. G. Stenberg and A. Lindeman:
"The ARC System Cross Section Generation Capabilities, ARC-MC2-2," ANL-7722 excerpt 571-576 (June 1973).
"Standard Interface Files and Procedures for Reactor Physics Codes, Version III," LA-5486-MS (February 1974).

- L. C. Leal, C. G. Stenberg, and B. R. Chandler:
"Completion of the Conversion of the MC2-2/SDX Codes from IBM to SUN (#3)," Argonne National Laboratory Internal Memorandum (May 27, 1993).

- C. G. Stenberg and H. Henryson, II:
"MC2-2 Information on IBM and CDC Implementation, Use of ENDF/B-V Library, and Added Capabilities," ANL/AP Memorandum (January 13, 1981).
PSR-0350/01, included references:
- H. Henryson, II, B.J. Toppel, and C.G. Stenberg
"MC2-2 : A Code to Calculate Fast Neutron Spectra and
Multigroup Cross Sections,"
ANL-8144 (June 1976)
- C.G. Stenberg and H.Henryson, II :
"MC2-2 Information on IBM and CDC Implementatio, Use of
ENDF/B-V Library, and Added Capabilities"
ANL/AP Memorandum (January 13, 1981)
- C.G. Stenberg and R.N. Hill,
"Addition to the MC2-2 Libraries and Updates to the MC2-2
Code on the RA Workstation (No.5)"
ANL Intra-laboratory Memo, file mcc2sdx5.pdf (Aug.10, 1993)
- C.G. Stenberg
"Auxiliary Cross Section Processing Codes Converted to the
Sun Workstation (No.6)"
ANL Intra-Laboratory Memo, file mcc2sdx6.pdf (Sept.1, 1993)
- C.G. Stenberg,
"ENDF/B-V Data of Li-6 in the MC2-2 Libraries (No.7),"
ANL Intra-Laboratory Memo, file mcc2sdx7.pdf (November 17, 1993)
- C.G. Stenberg and R.P. Jacqmin,
"Additions and Corrections to the MC2-2/RABANL/SDX Codes on the
RA Workstation (No.10),"
ANL Intra-Laboratory Memo, file mcc2sdx10.pdf (Aug.10, 1993)
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11. HARDWARE REQUIREMENTS

SUN and IBM RS/6000 versions of the MC2-2 code are distributed in this package together with the MC2-2 libraries processed through ETOE-2 using ENDF/B-V data. At least 2000 K of core memory are required.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
PSR-0350/01 FORTRAN-77, C-LANGUAGE
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13. SOFTWARE REQUIREMENTS

Fortran 77 and C compilers are required to build an executable. No special requirements are made on the operating system. This release has run under Solaris 2.5 and 2.6 (for SPARCStations) and AIX 3.2 and 4.3.3 on the IBM RS/6000. The standalone source code contains approximately 96,000 Fortran statements and 444 C statements. The code was tested at RSICC on a Sun Sparc UltraSparc 60 under Solaris 2.6 with F77 5.0 and C 5.0 and on an IBM RS/6000 Model 270 under xlf 7.1 with xlc 4.4.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by:
                Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.

Developed by:   Argonne National Laboratory,
                Argonne, Illinois, U.S.A.
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16. MATERIAL AVAILABLE
PSR-0350/01
350sun05.txt List of files
P350.pdf  Documentation in electronic form
P350tar1.gz compressed tar file
Readme.rsi  Readme file
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17. CATEGORIES
  • A. Cross Section and Resonance Integral Calculations

Keywords: ENDF/B, cross sections, multigroup, processing.