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IAEA1433 SPECTRA2010.

SPECTRA2010, Convert model and general tabulation to linearized spectra (MF=5)

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1. NAME OR DESIGNATION OF PROGRAM:  SPECTRA2010.
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2. COMPUTERS
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Program name Package id Status Status date
SPECTRA2010 IAEA1433/01 Tested 31-AUG-2011

Machines used:

Package ID Orig. computer Test computer
IAEA1433/01 Many Computers Linux-based PC,PC Windows
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3. DESCRIPTION OF PROGRAM OR FUNCTION

SPECTRA is an extension of LINEAR to linearize and tabulate neutron emission spectra (MF=5). ENDF format allows neutron spectra to be represented as nuclear models or tables of data points using a number of different interpolation laws between tabulated points; in order to obtain accurate results it is important to interpret the data using these interpolation laws. The nuclear models and tables with interpolation laws are very useful during evaluation, but can present problems when they are used in applications. The subsequent use of the data can be greatly simplified and the accuracy of results improved by first linearizing all of the spectra, i.e., replace the original nuclear model or tabulated data points and interpolation law by a new table where one can use linearly interpolation between tabulated points to within any required accuracy.
IAEA1433/01
This version include the updates up to June 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:
-------------------------------------
Spectra VERS. 2010-1 (June 2010):
- Added MF = 5 - MF = 6 still planned.
- 72 Character file names.
- Only process MF=5 - skip all others to prevent conflict with linear thinning.
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4. METHODS

Each section of data is considered separately. Each section of ENDF/B data to linearize is represented by a table of energy vs. cross section and any one of five allowable interpolation laws between any two tabulated points. This program will replace each section of data cross sections by a new table of energy vs. cross section in which the interpolation law is always linear in energy and cross section between any two tabulated points. Data is read and linearized a page at a time (one page contains 60000 data points). If the final linearized section contains two pages or less, data points it will be entirely core resident
After it has been linearized and will be written directly from core to the output tape. If the linearized section is larger than two pages, after each page is linearized it will be written to
scratch. After the entire section has been linearized it will be read back from scratch, two pages at a time, and written to the output tape.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

This program is designed to convert ENDF/B file 3, 23 and 27 data to linear-linear interpolable form. Any section that is already linear-linear interpolable will be thinned.
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6. TYPICAL RUNNING TIME:  A few seconds.
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7. UNUSUAL FEATURES OF THE PROGRAM

Since this program uses a logical paging system there is no limit to the number of points in any section, e.g., the total cross section may be represented by 200,000 data points.
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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.
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9. STATUS
Package ID Status date Status
IAEA1433/01 31-AUG-2011 Tested at NEADB
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10. REFERENCES
IAEA1433/01, included 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)
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11. HARDWARE REQUIREMENTS

The package is designed to be used with many machines. Make files for almost all kind of computers are included.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA1433/01 FORTRAN
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13. SOFTWARE REQUIREMENTS:  Several OS can be used.
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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))
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16. MATERIAL AVAILABLE
IAEA1433/01
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
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17. CATEGORIES
  • M. Data Management

Keywords: ENDF/B, cross sections, data processing, interpolation, linear.