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IAEA1322 EVALPLOT2010.

EVALPLOT2010, ENDF Plots Cross Section, Angular Distribution and Energy Distribution

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1. NAME OR DESIGNATION OF PROGRAM:  EVALPLOT2010.
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2. COMPUTERS
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Program name Package id Status Status date
EVALPLOT2010 IAEA1322/17 Tested 30-AUG-2011

Machines used:

Package ID Orig. computer Test computer
IAEA1322/17 Many Computers Linux-based PC,PC Windows
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3. DESCRIPTION OF PROGRAM OR FUNCTION

EVALPLOT is designed to plot evaluated cross sections in the ENDF/B format. The program plots cross sections, angular distributions, energy distributions and other parameters.
IAEA1322/17
This version include the updates up to August 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:
-------------------------------------
Evalplot VERS. 2010-1 (Aug. 2010): Extended to plots up to 100 Legendre Coefficients versus incident energy.
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4. METHOD OF SOLUTION

In the case of processing neutron and photon cross sections (MF=3 or 23) and parameters (MF=1 or 27), all data in a file (MF) is read, grouped together by type, and plotted. All reactions of a data type appear on the same plot.
The data types for MF=1 and 3 (neutrons) are:
(1)  total, elastic, capture, fission and total inealstic;
(2)  (n,2n), (n,3n) and (n,n' charged particle);
(3)  (n,charged particle);
(4)  particle production (proton, deuteron, etc.) and damage;
(5)  total, first, second, etc. chance fission;
(6)  total inealstic, inelastic discrete levels and continuum;
(7)  (n,p) total and levels (only if levels are given);
(8)  (n,d) total and levels (only if levels are given);
(9)  (n,t) total and levels (only if levels are given);
(10) (n,3He) total and levels (only if levels are given);
(11) (n,4He) total and levels (only if levels are given);
(12) parameters mu-bar, xi and gamma;
(13) nu-bar - total, prompt an delayed.
The data types for MF=23 and 27 (photons) are:
(14) total, coherent, incoherent, total photoelectrtic, total pair production;
(15) total and subshell photoelectric;
(16) total, nuclear and electron pair production;
(17) coherent form factor and incoherent scattering function;
(18) real and imaginary scattering factors.
In the case of processing angular and energy distributions (MF=4 or  5), only one section of data at a time is read and plotted. Each plot will contain data for a single reaction (MT) and different incident neutron energies. For Legendre coefficients the data in the ENDF/B format will be inverted to present each Legendre coefficient  versus incident energy.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

EVALPLOT uses only the ENDF/B BCD format and can handle data in the ENDF/B-I, II, III,  IV, V, and VI formats. - The format of section MT=452, 455 of MF=1 and all sections of MF=2,4,5 must be correct. - All tabulated data must be completely either histogram or linear interpolation law (the two interpolation laws cannot be mixed together in one table). The user may specify up to 100 MAT/MF/MT or ZA/MF/MT ranges.
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6. TYPICAL RUNNING TIME:  A few seconds.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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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
IAEA1322/17 30-AUG-2011 Tested at NEADB
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10. REFERENCES
IAEA1322/17, 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
IAEA1322/17 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 AUTHORS

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
IAEA1322/17
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
  • N. Subsidiary Calculations

Keywords: ENDF/B, computer graphics, cross sections, plotting.