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IAEA0848 RECENT2010.

RECENT2010, Reconstruction of Cross Sections Data from Resonance Parameters

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1. NAME OR DESIGNATION OF PROGRAM:  RECENT2010.
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2. COMPUTERS
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Program name Package id Status Status date
RECENT2010 IAEA0848/18 Tested 31-AUG-2011

Machines used:

Package ID Orig. computer Test computer
IAEA0848/18 Many Computers Linux-based PC,PC Windows
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3. DESCRIPTION OF PROBLEM OR FUNCTION

RECENT reconstructs energy- dependent neutron total elastic, capture, and fission cross sections from a combination of resonance parameters and tabulated background  cross sections. RECENT uses the linearly interpolable form of cross  sections and resonance parameters. The cross section output is linearly interpolable over the entire energy range. Entire calculations, not just cross sections, are output in the result file, which is in ENDF/B format. The output includes the original resonance parameters in a form that can be used in Doppler broadening and self-shielding calculations.
IAEA0848/18
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:
-------------------------------------
Recent VERS. 2010-1 (Apr. 2010):
- Added SAMRML LOGIC to handle all LRF=7 cases.
- Extended SAMRML LOGIC to process all evaluations = resolved + unresolved + tabulated - SAMRML only does one section of resolved LRF=7 data without tabulated background.
- Updated elastic potential calculation for total (SLBW) and correction for missing sequences (MLBW, RM, HRF).
- Added hidden (optional) unresolved competition listing (not ENDF/B).
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4. METHOD OF SOLUTION

Resonance parameters may be represented using any combination of the representations allowed in ENDF/B:
(1) Resolved data
    a) single-level Breit-Wigner
    b) multi-level Breit-Wigner
    c) Adler-Adler
    d) Reich-Moore
    e) hybrid. R-functions.
(2) Unresolved data
    a) all parameters constant or energy independent
    b) fission parameters energy dependent
    c) all parameters energy dependent.
RECENT starts by calculating the cross sections at the energies corresponding to the peak of each resonance, as well as a fixed number of half-widths on each side of each resonance. Starting from  this basic grid of points the program will continue to halve each interval until the cross sections for all reactions at the center of the interval can be defined by linear interpolation from the ends of the interval to within the user specified accuracy criteria. All resonances are treated exactly.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

RECENT uses only the ENDF/B BCD format, not binary and can handle data in any version of  the ENDF/B format (I through VI). In order to be combined with the resonance contribution, the background cross sections must be given  at temperature 0K and must be linearly interpolable. If these conditions are not met, the background cross section will be ignored and only the resonance contribution will be output.
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6. TYPICAL RUNNING TIME:  A few seconds.
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7. UNUSUAL FEATURES OF THE PROGRAM

The Edit mode provides an inexpensive method of determining the type of resonance parameters used by any given set of parameters. In this mode the user can also  determine the amount of common core allocation necessary to carry out the resonance reconstruction. - The allowable error may be energy independent or energy dependent. It is described with a tabulated function of up to 20 (energy,error) pairs. - The backward  thinning minimizes the number of data points output for each reaction.
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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
IAEA0848/18 31-AUG-2011 Tested at NEADB
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10. REFERENCES:
IAEA0848/18, 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
IAEA0848/18 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
IAEA0848/18
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
  • A. Cross Section and Resonance Integral Calculations

Keywords: Breit-Wigner formula, ENDF/B, cross sections, processing, resolved region, resonance integrals, unresolved region.