IAEA1321 COMPLOT2010.

1. NAME OR DESIGNATION OF PROGRAM:  COMPLOT2010.

3. DESCRIPTION OF PROGRAM OR FUNCTION

COMPLOT compares ENDF/B formatted data from two separate input files. The program produces a series of comparative plots containing the standard cross section and second cross section and/or the ratio of the second cross section to the first cross section.

This version include the updates up to July 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:
-------------------------------------
Complot VERS. 2010-1 (July 2010):
- Allow comparison plot even if there is no difference (just see data).
- ONLY plot linearly interpoolable data
- Include threshold energy points to show cross sections, but NOT ratios near threshold.
- Moved points near resonance region boundary to boundary - this attempts to change NJOY approximation to move points on boundary slightly off, so there is no discontinuity.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The program only uses the ENDF/B card image format (as opposed to the binary format) and can handle data in any version of ENDF/B format (I to VI).
- Only reactions of file 2 (resonance parameters) and files 3, 23, and 27 (tabulated data) will be read. All others are skipped.
- The user may specify up to 100 MAT/MT/energy or ZA/MT/energy ranges.
- Cross sections must be either in histogram or linearly interpolable form.
If not, the program will terminate execution.

6. TYPICAL RUNNING TIME:  A few seconds.

7. UNUSUAL FEATURES OF THE PROGRAM

COMPLOT includes an interactive interface for use with a mouse. The user can zoom in on any smaller  energy range by selecting a lower and upper energy limit with the mouse. - To force all comparable reactions to be plotted the user need only specify an allowable difference of zero.

8. RELATED OR 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.

10. 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)

11. MACHINE REQUIREMENTS

The package is designed to be used with many machines. Make files for almost all kind of computers are included.

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  Several OS can be used.

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))

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