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IAEA0849 GROUPIE2010.

GROUPIE2010, Bondarenko Self-Shielded Cross Sections from ENDF/B

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1. NAME OR DESIGNATION OF PROGRAM:  GROUPIE2010.
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2. COMPUTERS
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Program name Package id Status Status date
GROUPIE2010 IAEA0849/16 Tested 30-AUG-2011

Machines used:

Package ID Orig. computer Test computer
IAEA0849/16 Many Computers Linux-based PC,PC Windows
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3. DESCRIPTION OF PROBLEM OR FUNCTION

GROUPIE reads evaluated data in ENDF/B format and uses these to calculate unshielded group averaged  cross sections, Bondarenko self-shielded cross sections, and multiband parameters. The program allows the user to specify arbitrary energy groups and an arbitrary energy-dependent neutron spectrum (weighting function).
IAEA0849/16
This version include the updates up to April 2010.
The 2010 ENDF/B Pre-processing codes process nuclear data formatted in any version of the ENDF formats; ENDF/B-I through ENDF/B-VII evaluations. These codes can be used on virtually any computer: everything from large mainframe computers, to workstations, to IBM-PC (Windows or Linux) and MAC (OSX).
MODIFICATIONS FROM PREVIOUS VERSIONS:
-------------------------------------
Groupie VERS. 2010-1 (Apr. 2010):
- Increased weighting spectrum to 30,000 from 3,000 energy points.
- Added output to plot/compare shielded and unshielded cross sections.
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4. METHOD OF SOLUTION

All integrals are performed analytically; in no case is iteration or any approximate form of integration used. GROUPIE reads either the 0 deg. Kelvin cross sections or the Doppler broadened cross sections to calculate the self-shielded cross sections and multiband parameters for 25 values of the "background"  cross sections (representing the combined effects of all other isotopes and of leakage).
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

GROUPIE requires that the energy-dependent neutron spectrum and all cross sections be given in tabular form, with linear interpolation between tabulated values. There is no limit to the size of the table used to describe  the spectrum, so the spectrum may be described in as much detail as  required. - If only unshielded averages are calculated, the program  can handle up to 3000 groups. If self-shielded averages and/or multiband parameters are calculated, the program can handle up to 175 groups. These limits can easily be extended. - The program only  uses the ENDF/B BCD card-image format and can handle data in any version of the ENDF/B format (I to VI) It is assumed that the data is correctly coded in the ENDF/B format. No error checking is performed. Non-processed data is simply copied. - All file 3 cross sections must be linearly interpolable in energy and cross section.  GROUPIE terminates execution if it finds that the file 3 cross sections are not linearly interpolable.
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6. TYPICAL RUNNING TIME:  A few seconds.
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7. UNUSUAL FEATURES OF THE PROGRAM

Current weighting and next higher  flux moment weighting are available. - The code can be used as a simple and very economical means of obtaining multigroup cross sections for applications where only multigroup cross sections are required, e.g. dosimetry.
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8. RELATED AND AUXILIARY PROGRAMS

The following programs are all part of the PREPRO2010 package.  
ACTIVATE: is designed to create file 10 activation cross sections by
          combining file 3 cross sections and file 9 multipliers
COMPLOT: Compares ENDF/B formatted data from two separate input
         files. Results are in graphical form.  
CONVERT: Automatically converts a FORTRAN program for use on
         any one of a variety of: (1) computers; (2) compilers:
         (3) precisions; (4) installations; (5) standard or
         non-standard file names.  
DICTIN:  Creates a reaction index for each material.  
EVALPLOT:Plots data in the ENDF/B format.  
FIXUP:   Reads evaluated data in the ENDF/B format; performs
         corrections and outputs the results in the ENDF/B format.  
GROUPIE: calculates unshielded group averaged cross sections,  
         Bondarenko self-shielded group averaged cross sections,
         and multiband parameters from data in the ENDF/B format.  
LEGEND:  Calculates linearly interpolable tabulated angular  
         distributions starting from data in the ENDF/B format.  
LINEAR:  Converts cross sections in the ENDF/B format (File 3,
         23, and 27) to linearly interpolable form (in energy  
         and cross section) and outputs the result in the ENDF/B
         format.  
MERGER:  Selectively retrieves data by MAT/MF/MT or ZA/MF/MT from
         up to 10 ENDF/B data tapes and merges the data into a
         single MAT/MF/MT ordered output file.  
MIXER:   Calculates the energy dependent cross sections for a
         composite mixture.  
RECENT:  Reconstructs energy-dependent cross sections from a
         combination of resonance parameters and tabulated  
         background cross sections in the ENDF/B format.  
RELABEL: relabels a ENDF/B preprocessing program so that  
         statement labels are in increasing order in increments of
         10 within each routine.  
SIGMA-1: Doppler broadens evaluated cross sections in the
         linear-linear interpolation form of the ENDF/B format.
SIXPAK:  Checks all double-differential ENDF/B-VI format data (MF=6)
         and outputs equivalent uncorrelated data (MF=4, 5, 12, 14, and 15).
SPECTRA: Convert model and general tabulation to linearized spectra (MF=5).
VIRGIN:  Calculates uncollided flux and reactions due to transmission of a
         monodirectional beam of neutrons through any thickness of material.
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9. STATUS
Package ID Status date Status
IAEA0849/16 30-AUG-2011 Tested at NEADB
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10. REFERENCES:
IAEA0849/16, included references:
- Dermott E. Cullen and IAEA NDS:
PREPRO 2010, 2010 ENDF/B Pre-processing Codes (ENDF/B-VII Tested)
IAEA-NDS-39 (Rev. 14, October 31, 2010)
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11. MACHINE REQUIREMENTS

The package is designed to be used with many machines. Make files for almost all kind of computers are included.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA0849/16 FORTRAN
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  Several OS can be used.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR

Nuclear Data Section
IAEA
P.O. Box 100
A-1400 VIENNA
AUSTRIA
Originally Written
by
Dermott E. Cullen (University of California (retired))
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16. MATERIAL AVAILABLE
IAEA0849/16
Author's Make file for PCLinux
Author and NEA LINUX executable
Author's PC Windows compile batch
Author and NEA PC Windows executable
Fortran source files for different platforms
UNIX Makefiles for different platforms
Author's VMS executable, Author's compile command file
Author's MAC executable, Author's compile command file
Documentation, General description
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17. CATEGORIES
  • B. Spectrum Calculations, Generation of Group Constants and Cell Problems

Keywords: ENDF/B, cross sections, group constants, self-shielding.