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IAEA1283 SIXPAK2007. (Abstract last modified 07-DEC-2007)
1.
NAME OR DESIGNATION OF PROGRAM - SIXPAK2007. 2.
COMPUTER FOR WHICH THIS PACKAGE IS DESIGNED -
To request or retrieve programs click on the one of the active versions below.
A password and special authorization is required. Explanation of the status codes.
Machines used:
Package-ID Orig.Computer Test Computer
IAEA1283/06 Many Computers Linux-based PC,PC Windows
3.
DESCRIPTION OF PROGRAM OR FUNCTION - SIXPAK has two main functions: (1) check all double-differential ENDF-6 format data (MF=6); 4.
METHOD OF SOLUTION - All of the ENDF-6 MF=6 data is checked. The MF=6 data is not corrected and output in the ENDF/B format is merely checked. If errors are found it is up to the user to take corrective action on the MF=6 data. 5.
RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM - 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. No error checking is performed.
6.
TYPICAL RUNNING TIME - A few seconds. 7.
UNUSUAL FEATURES OF THE PROGRAM - 8.
RELATED AND AUXILIARY PROGRAMS - 9.
STATUS 10.
REFERENCES - 11.
MACHINE REQUIREMENTS - The package is designed to be used with many machines. Make files for almost all kind of computers are included. 12.
PROGRAMMING LANGUAGE(S) USED - 13.
OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED - Several OS can be used. 14.
OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS - 15.
NAME AND ESTABLISHMENT OF AUTHORS - 16.
MATERIAL AVAILABLE - 17.
CATEGORIES - Keywords: ANGULAR DISTRIBUTION, CROSS SECTIONS, DATA PROCESSING, ENDF/B
Program-name Package-ID Status
SIXPAK-94.1 IAEA1283/01 Obsolete
SIXPAK-96.1 IAEA1283/02 Obsolete
SIXPAK2000 IAEA1283/03 Obsolete
SIXPAK2002 IAEA1283/04 Obsolete
SIXPAK2004 IAEA1283/05 Obsolete
SIXPAK2007 IAEA1283/06 Tested
(2) output equivalent uncorrelated data (MF = 4, 5, 12, 14,and 15
data.
IAEA1283/06:
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:
-------------------------------------
Sixpak VERS. 2007-1 (JAN. 2007): checked against all ENDF/B-VII; increased maximum table size from 12,000 to 120,000
In contrast, when problems are found in data which will be output in the ENDF/B format (MF=4, 5, and 15), corrective action will be taken, whenever possible.
SIXPAK changes correlated (MF=6) vs. uncorrelated (MF=4 and 5) data. The ENDF/B double differential correlated data in MF=6 represent data in the form
F(E,EP,COS) = SIG(E)*Y(E)*G0(E,EP)*F(E,EP,COS)
with:
SIG(E) = MF=3 cross sections
Y(E) = yield (multiplicity)
G0(E,EP) = energy spectrum
F(E,EP,COS) = angular distribution
The uncorrelated data produced by this code replaces the correlated data by the uncorrelated data,
F(E,EP,COS) = SIG(E)*Y(E)*G0(E,EP)*F0(E,COS)
by integrating G0(E,EP)*F(E,EP,COS) over secondary energy (EP) to define an average angular distribution, F0(E,COS). What is lost in this process is the correlation between EP and COS so that in a transport calculation all moments of the flux will have the same spectrum, G0(E,EP) and each will be effected by the average angular distribution.
Three ENDF/B formatted output files are produced for neutron incident data:
1) ENDFB.MF4 - angular distributions and Legendre coefficients
2) ENDFB.MF5 - tabulated neutron energy spectra
3) ENDFB.M12 - photon emission multiplicity
4( ENDFB.M14 - photon emission angular distributions (always
isotropic)
All of this data is in normalized form suitable for use with the cross sections in MF=3.
All of the data in ENDF-6 MF=6 are quite small tables. As such this program only allows tables of up to 6000 points (6000 x and y
values). This size is more than adequate to handle all of the current ENDF/B-VI data, and it can be easily increased to handle any newer data as it becomes available.
The following programs are all part of the PREPRO2002 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.
IAEA1283/01: 07-APR-1997 Obsolete
IAEA1283/02: 11-DEC-2000 Obsolete
IAEA1283/03: 24-JUL-2003 Obsolete
IAEA1283/04: 29-SEP-2006 Obsolete
IAEA1283/05: 10-DEC-2007 Obsolete
IAEA1283/06: 07-DEC-2007 Tested at NEADB
IAEA1283/06:
- IAEA Nuclear Data Section:
PREPRO2007, 2007 ENDF/B Pre-processing Codes (ENDF/B-VII Tested)
IAEA-NDS-39, Rev. 13, March 17, 2007
IAEA1283/06: FORTRAN-77
Nuclear Data Section
IAEA
P.O. Box 100
A-1400 VIENNA
AUSTRIA
IAEA1283/06:
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
- M. Data Management
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