PREPRO2010: Pre-processing Code System for Data in ENDF/B Format
International Atomic Energy Agency, Nuclear Data Center, Vienna, Austria.
Fortran 77 on Pentium PC, MacOS X, LINUX, UNIX and VMS (MIS00013MNYCP00).
The ENDF/B pre-processing codes are designed to be a modular set of computer codes, each of which reads evaluated nuclear data in the ENDF/B format, processes the data and outputs it in the ENDF/B format. Each code performs one or more independent operations on the data. The codes are named “the pre‑processing” codes because they are designed to pre‑process ENDF/B data for subsequent use in applications. These codes are designed to operate on virtually any type of computer with the included capability of optimization on any given computer. They can process datasets in any ENDF/B format, ENDF/B-I through ENDF/B-VI, and are even designed to handle new ENDF/B-VII evaluations. Additional information is available on the PREPRO website http://www-nds.iaea.org/ndspub/endf/prepro/.
Each of the PREPRO2010 modules performs a different function on ENDF/B data files. A brief description of how the codes are used is listed below:
Linear ‑ Linearize cross sections
Recent‑ Reconstruct cross sections from resonance parameters
Sigma1‑ Doppler broaden cross sections
Activate ‑ generate activation cross sections (MF=10) from MF=3 and 9 data
Legend‑ Calculate/correct angular distributions
Sixpak‑ Convert double differential data to single differential
Fixup ‑ Correct format and cross sections, define by summation
Dictin ‑ Create reaction dictionary (MF=1, MT=451)
Merger ‑ Retrieve and/or Merge evaluated data
Groupie ‑ Calculate group averages and multi‑band parameters
Complot ‑ Plot comparisons of cross sections (MF=3, 23), Comhard for hardcopy
Evalplot ‑ Plot evaluated data (MF=3, 4, 5, 23, 27), Evalhard for hardcopy
Mixer ‑ Calculate mixtures of cross sections
Virgin ‑ Calculate transmitted uncollided (virgin) flux and reactions
Convert ‑ Convert codes for computer/precision/compiler
Relabel ‑ Relabel and sequence programs
Spectra - Linearize and tabulate neutron emission spectra (MF=5).
Test cases for each code are included to ensure it is operating correctly. After you have tested the codes it is recommended that you use the “BEST INPUT” provided in a separate directory for each code. MORE COMPLETE packages are included for each type of computer; in particular the graphics codes EVALPLOT and COMPLOT, included so users can quickly view nuclear data on their computer screen and/or produce postscript files for later use, i.e., as in reports.
The 2010 codes include extensions to handle all current ENDF formats and procedures, and corrects problems that existed in earlier versions of these codes. The 2010 codes supersede all earlier versions and it is strongly recommended that all users of these codes only use the 2010 version of these codes. Failure to heed this warning can lead to completely erroneous results.
Running time is no longer a major concern in processing ENDF/B data and even small personal computers are powerful enough to be used to process all ENDF/B evaluations.
PREPRO2010 runs on UNIX workstations, Linux and Windows PCs, MacOSX, and VMS.
PREPRO2010 is written in standard Fortran. UNIX, Linux, and OpenVMS systems require X11 for the graphics capability. Distribution includes executables for LINUX, Windows, and MacOS All other systems require a Fortran compiler. PREPRO2010 was tested at RSICC on several computers.
D. E. Cullen, “PREPRO 2010: 2010 ENDF/B Pre-processing Codes,” IAEA-NDS-39, Rev. 14 (Oct. 31, 2010).
The package is transmitted on a CD which contains the referenced document in electronic form and 5 machine-dependent compressed files. The extracted directories contain Fortran 77 source files for unix, executables for PC, Linux and MacOS, sample input and output, and information files.
January 1995, Sept. 1997, October 2000, May 2001, May 2003, February 2005, June 2007, December 2010
KEYWORDS: ENDF/B FORMAT; MULTIGROUP CROSS SECTION PROCESSING; PLOTTING; MICROCOMPUTER; WORKSTATION