8. RELATED AND AUXILIARY PROGRAMS
The following programs are all part of the PRE-PRO94 package.
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.
DICTION: 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
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
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
PLOTTAB: Plots any combination of continuous curves and/or points
(with associated error bars) using user-supplied titles
and (x,y) axis labels and units.
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
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.