IAEA1380: ACTIVATE2007, Activation Cross Section by Combining Cross Section and Multiplier (ENDF Fomat)

Program-name Package-ID Status ACTIVATE2000 IAEA1380/01 Obsolete ACTIVATE2002 IAEA1380/02 Obsolete ACTIVATE2004 IAEA1380/03 Obsolete ACTIVATE2007 IAEA1380/04 Tested

Machines used: Package-ID Orig.Computer Test Computer IAEA1380/04 Many Computers Linux-based PC,PC Windows

3. DESCRIPTION OF PROGRAM OR FUNCTION - ACTIVATE is designed to create file 10 activation cross sections by combining file 3 cross sections and file 9 multipliers.

IAEA1380/04:

This version include the updates up to JANUARY 30, 2007.
Changes in ENDF/B-VII Format and procedures, as well as the evaluations themselves, make it impossible for versions of the ENDF/B pre-processing codes earlier than PREPRO 2007 (2007 Version) to accurately process current ENDF/B-VII evaluations.
The present code can handle all existing ENDF/B-VI evaluations through release 8, which will be the last release of ENDF/B-VI.

MODIFICATIONS FROM PREVIOUS VERSIONS:
-------------------------------------
Activate VERS. 2007-1 (JAN. 2007): checked against all ENDF/B-VII

4. METHODS - This program only uses the ENDF/B BCD or card image format (as opposed to the binary format) and can handle data in any version of the ENDF/B format (i.e., ENDF/B-I, II, III, IV, V or VI format).
It is assumed that the data is correctly coded in the ENDF/B format and no error checking is performed. In particular it is assumed that the mat, mf and mt on each line is correct.

Sequence numbers (columns 76-80) are ignored on input, but will be correctly output on all lines. The format of section mf=1, mt=451 and all sections of mf=3 must be correct. The program copies all other section of data as hollerith and as such is insensitive to the
Correctness or incorrectness of all other sections.

6. TYPICAL RUNNING TIME - A few seconds. It depends on the problem submitted.

8. RELATED OR AUXILIARY PROGRAMS -
The following programs are all part of the PREPRO2007 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)
VIRGIN:  Calculates uncollided flux and reactions due to
         transmission of a monodirectional beam of neutrons
         through any thickness of material.

9. STATUS
IAEA1380/01: 23-JUL-2003 Obsolete
IAEA1380/02: 29-SEP-2006 Obsolete
IAEA1380/03: 07-DEC-2007 Obsolete
IAEA1380/04: 07-DEC-2007 Tested at NEADB

10. REFERENCES -
IAEA1380/04:
- IAEA Nuclear Data Section:
PREPRO2007, 2007 ENDF/B Pre-processing Codes (ENDF/B-VII Tested)
IAEA-NDS-39, Rev. 13, March 17, 2007

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

12. PROGRAMMING LANGUAGE -IAEA1380/04: FORTRAN-77

13. SOFTWARE REQUIREMENTS - Several OS can be used.

15. NAME AND ESTABLISHMENT OF AUTHORS -
Nuclear Data Section
IAEA
P.O. Box 100
A-1400 VIENNA
AUSTRIA

16. MATERIAL AVAILABLE -IAEA1380/04:
General description of the PrePro2007 programs
Documentation
Compressed files for MAC, Readme file for MAC
Author's Make file for PCLinux, Author's LINUX executable
Author's PCWindows compile batch
Author's PCWindows executable
Fortran source files for different platfor
UNIX Makefiles for different platforms
Author's VMS executable, Author's compile command file

17. CATEGORIES -

- N. Subsidiary Calculations

Keywords: CROSS SECTIONS, DATA PROCESSING, ENDF/B