IAEA1380 ACTIVATE2007.
ACTIVATE2007, Activation Cross Section by Combining Cross Section and Multiplier (ENDF Format)
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHODS, TYPICAL RUNNING TIME, RELATED OR AUXILIARY PROGRAMS, STATUS, REFERENCES, HARDWARE REQUIREMENTS, LANGUAGE, SOFTWARE REQUIREMENTS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES
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are available here.
| Program name | Package id | Status | Status date |
|---|---|---|---|
| ACTIVATE2007 | IAEA1380/04 | Tested | 07-DEC-2007 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| IAEA1380/04 | Many Computers | Linux-based PC,PC Windows |
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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.
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
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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.
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.
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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 broa
dens 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.
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 broa
dens 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.
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IAEA1380/04, included references:
- IAEA Nuclear Data Section:PREPRO2007, 2007 ENDF/B Pre-processing Codes (ENDF/B-VII Tested)
IAEA-NDS-39, Rev. 13, March 17, 2007
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IAEA1380/04
General description of the PrePro2007 programsDocumentation
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
Keywords: ENDF/B, cross sections, data processing.