IAEA1311: LINEAR2007, Linear-Linear Interpolation of ENDF Format Cross-Sections

Program-name Package-ID Status LINEAR IAEA1311/01 Obsolete LINEAR IAEA1311/02 Obsolete LINEAR-82.1 IAEA1311/03 Obsolete LINEAR-83.2 IAEA1311/04 Obsolete LINEAR-86.1 IAEA1311/05 Obsolete LINEAR-87.1 IAEA1311/06 Obsolete LINEAR-87.1 IAEA1311/07 Obsolete LINEAR-89.1 IAEA1311/08 Obsolete LINEAR-92.1 IAEA1311/09 Obsolete LINEAR-94.1 IAEA1311/10 Obsolete LINEAR-96.1 IAEA1311/11 Obsolete LINEAR2000 IAEA1311/12 Obsolete LINEAR2002 IAEA1311/13 Obsolete LINEAR2004 IAEA1311/14 Obsolete LINEAR2007 IAEA1311/15 Tested

Machines used: Package-ID Orig.Computer Test Computer IAEA1311/15 Many Computers Linux-based PC,PC Windows

3. DESCRIPTION OF PROBLEM OR FUNCTION - LINEAR converts evaluated cross sections in the ENDF/B format into a tabular form that is subject to linear-linear interpolation in energy and cross section. The code also thins tables of cross sections already in that form. Codes used subsequently need thus to consider only linear-linear data.

IAEA1311/15:

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:
-------------------------------------
Linear VERS. 2007-1 (JAN. 2007): checked against all ENDF/B-VII; increased page size from 60,000 to 600,000 points

4. METHOD OF SOLUTION - Each section of data is considered separately. Each section of File 3, 23, and 27 data consists of a table of cross section versus energy with any of five interpolation laws. LINEAR will replace each section with a new table of energy versus cross section data in which the interpolation law is always linear in energy and cross section. The histogram (constant cross section between two energies) interpolation law is converted to linear-linear by substituting two points for each initial point. The linear-linear is not altered. For the log-linear, linear-log and log- log laws, the cross section data are converted to linear by an interval halving algorithm. Each interval is divided in half until the value at the middle of the interval can be approximated by linear-linear interpolation to within a given accuracy. The LINEAR program uses a multipoint fractional error thinning algorithm to minimize the size of each cross section table.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM -

6. TYPICAL RUNNING TIME - A few seconds.

7. UNUSUAL FEATURES OF THE PROGRAM - LINEAR: An energy dependent interpolation error can be specified with a tabulated function of up to 20 (energy, error) pairs. This can be used to emphasize energy regions of interest and reflect the accuracy with which cross sections are known.

8. RELATED AND AUXILIARY PROGRAMS -
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.

9. STATUS
IAEA1311/01: 09-SEP-1981 Obsolete
IAEA1311/02: 14-DEC-1981 Obsolete
IAEA1311/03: 26-MAR-1984 Obsolete
IAEA1311/04: 17-SEP-1986 Obsolete
IAEA1311/05: 23-JUN-1987 Obsolete
IAEA1311/06: 29-MAY-1989 Obsolete
IAEA1311/07: 29-MAY-1989 Obsolete
IAEA1311/08: 28-AUG-1992 Obsolete
IAEA1311/09: 22-JUL-1994 Obsolete
IAEA1311/10: 07-APR-1997 Obsolete
IAEA1311/11: 11-DEC-2000 Obsolete
IAEA1311/12: 24-JUL-2003 Obsolete
IAEA1311/13: 29-SEP-2006 Obsolete
IAEA1311/14: 10-DEC-2007 Obsolete
IAEA1311/15: 07-DEC-2007 Tested at NEADB

10. REFERENCES -
IAEA1311/15:
- IAEA Nuclear Data Section:
PREPRO2007, 2007 ENDF/B Pre-processing Codes (ENDF/B-VII Tested)
IAEA-NDS-39, Rev. 13, March 17, 2007

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 -
IAEA1311/15: FORTRAN-77

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 AUTHOR -
Nuclear Data Section
IAEA
P.O. Box 100
A-1400 VIENNA
AUSTRIA

16. MATERIAL AVAILABLE -
IAEA1311/15:
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 -

- M. Data Management

Keywords: CROSS SECTIONS, ENDF/B, INTERPOLATION, LINEAR