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PSR-0286 COMBINE-PC.

COMBINE-PC, MultiGroup Neutron Cross-Sections in B1 or B3 Approximation from ENDF/B-5

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1. NAME OR DESIGNATION OF PROGRAM:  COMBINE-PC.
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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
COMBINE-PC PSR-0286/01 Arrived 21-AUG-2001

Machines used:

Package ID Orig. computer Test computer
PSR-0286/01 IBM PC
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3. DESCRIPTION OF PROGRAM OR FUNCTION

COMBINE computes the neutron spectra and ENDF/B Version 5 based neutron multigroup constants suitable for use in diffusion and transport theory neutronics analysis. The equations solved for the energy-dependent fast and thermal neutron spectra are based on the B-1 or B-3 approximation to the Boltzmann transport equation.
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4. METHOD OF SOLUTION

The energy range is broken into 166 discrete points for the spectrum calculation. The resulting matrix of flux equations is then solved using standard numerical techniques to obtain the spectral weight function for generation of group-averaged constants. Resolved resonance shielding of the fine mesh cross section data is performed using a table lookup technique or the Nordheim method. The unresolved range is treated using a statistical averaging technique.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

This version can be  used for neutron energy range .001 eV to 16.9 MeV. The number of coalesced (broad) groups output to the cross section interface file  is limited to 99 or fewer, not 118 as indicated in the manual. COMBINE/PC will run on 32 or 60 or 64 bit computers.
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6. TYPICAL RUNNING TIME

Variable from a few minutes to 3 hours on IBM PC, depending on the number and type of resonance shielding calculation. On Cray, Apollo and CDC hardware, run times vary from a few seconds to a few minutes. At RSIC, the code was installed on an  IBM PC/XT with 640 K of main memory and 20 MB hard disk, running at  4.7 megahertz under DOS 3.3. Installation of the fast neutron library took about 1 hour; the resonance broadening table took about 1 hour and 10 minutes; the thermal library took about 2 hours. The following run times were noted:
C01.INP - 1 hour and 25 minutes
C09.INP - 2 hours and 25 minutes
C11.INP - 10 minutes
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
PSR-0286/01 21-AUG-2001 Masterfiled Arrived
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10. REFERENCES:
PSR-0286/01, included references:
- R.A. Grimesey, D.W. Nigg and R.L. Curtis
  COMBINE/PC - A Portable ENDF/B Version 5 Neutron Spectrum and
  Cross-Section Generation Program
  EGG-2589, Rev. 1 (February 1991)
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11. MACHINE REQUIREMENTS

IBM PC and compatibles with math co-processor, 640K of addressable memory and at least 20 MB of fixed storage.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
PSR-0286/01 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

The code was written in Fortran 77 and uses Lahey F77L and PLINK86 overlay linker for the IBM PC version. A Fortran 77 compiler is required for the mainframe versions.
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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:   Idaho National Engineering Laboratory
                Idaho Falls, Idaho, USA
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16. MATERIAL AVAILABLE
PSR-0286/01
load module      mag tapeCOMIBINE.EXE COMBINE executable for IBM PC LODTP
load module      mag tapeSCOPE.EXE execut. for an iteractive input  LODTP
test-case data   mag tapeC01.INP input for a test-case (TRX Lattice)DATTP
test-case output mag tapeC01.OUT printed output file to C01.INP     OUTTP
test-case data   mag tapeC09.INP test-case input file               DATTP
test-case data   mag tapeA09.INP ANISN/PC input file                DATTP
test-case output mag tapeC09.OUT printed output file to C09.INP     OUTTP
test-case output mag tapeA09.OUT ANISN/PC print. output to A09.INP  OUTTP
test-case data   mag tapeC11.INP test-case input test-case          DATTP
test-case output mag tapeC11.OUT printed output file to C11.INP     OUTTP
error file       mag tapeF77.EER error message for Lahey FORTRAN    ERRTP
symb data lib    mag tapeFASTLIB.001 fast energy range master Lib.  LBSTP
symb data lib    mag tapeFASTLIB.002 fast energy range master Lib.  LBSTP
symb data lib    mag tapeFASTLIB.003 fast energy range master Lib.  LBSTP
symb data lib    mag tapeFASTLIB.004 fast energy range master Lib.  LBSTP
symb data lib    mag tapeFASTLIB.005 fast energy range master Lib.  LBSTP
test-case data   mag tapeFINST.BAT DOS batch file                   DATTP
load module      mag tapeBINPHRG.EXE executable program (IBM-PC)    LODTP
test-case data   mag tapeBINPHRG.INP input for BINPHRG.EXE          DATTP
symb data lib    mag tapeTABTABPC.CDS ASCII card-image file         LBSTP
test-case data   mag tapeRINST.BAT DOS batch file                   DATTP
load module      mag tapeBINTP12.EXE executable program (IBM-PC)    LODTP
test-case data   mag tapeBINTP12.INP input for BINTP12.EXE          DATTP
symb data lib    mag tapeTHRMLIB.001 thermal ener. range master Lib.LBSTP
symb data lib    mag tapeTHRMLIB.002 thermal ener. range master Lib.LBSTP
symb data lib    mag tapeTHRMLIB.003 thermal ener. range master Lib.LBSTP
symb data lib    mag tapeTHRMLIB.004 thermal ener. range master Lib.LBSTP
symb data lib    mag tapeTHRMLIB.005 thermal ener. range master Lib.LBSTP
symb data lib    mag tapeTHRMLIB.006 thermal ener. range master Lib.LBSTP
symb data lib    mag tapeTHRMLIB.007 thermal ener. range master Lib.LBSTP
symb data lib    mag tapeTHRMLIB.008 thermal ener. range master Lib.LBSTP
test-case data   mag tapeTINST.BAT DOS batch file                   DATTP
load module      mag tapeBININCI.EXE executable program (IBM-PC)    LODTP
test-case data   mag tapeBININCI.INP input for BININCI.EXE          DATTP
source program   mag tapeC000.FOR FORTRAN source code               SRCTP
source program   mag tapeC010.FOR FORTRAN source code               SRCTP
source program   mag tapeC100.FOR FORTRAN source code               SRCTP
source program   mag tapeC200.FOR FORTRAN source code               SRCTP
source program   mag tapeC210.FOR FORTRAN source code               SRCTP
source program   mag tapeC220.FOR FORTRAN source code               SRCTP
source program   mag tapeC230.FOR FORTRAN source code               SRCTP
source program   mag tapeC240.FOR FORTRAN source code               SRCTP
source program   mag tapeC250.FOR FORTRAN source code               SRCTP
source program   mag tapeC260.FOR FORTRAN source code               SRCTP
source program   mag tapeC270.FOR FORTRAN source code               SRCTP
source program   mag tapeC300.FOR FORTRAN source code               SRCTP
source program   mag tapeC310.FOR FORTRAN source code               SRCTP
source program   mag tapeC320.FOR FORTRAN source code               SRCTP
source program   mag tapeC330.FOR FORTRAN source code               SRCTP
source program   mag tapeC340.FOR FORTRAN source code               SRCTP
source program   mag tapeC400.FOR FORTRAN source code               SRCTP
source program   mag tapeC500.FOR FORTRAN source code               SRCTP
source program   mag tapeSCOPE.FOR source code for interactive inp. SRCTP
source program   mag tapeBINPHRG.FOR source fast spectrum Library   SRCTP
source program   mag tapeBINTP12.FOR source resonance tables        SRCTP
source program   mag tapeBININCI.FOR source thrm spectr. master Lib.SRCTP
report                   EGG-2589 Rev. 1 (February 1991)            REPPT
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17. CATEGORIES
  • B. Spectrum Calculations, Generation of Group Constants and Cell Problems

Keywords: ENDF/B, multigroup theory, neutron diffusion equation, neutron spectra, neutron transport equation.