3. DESCRIPTION OF PROGRAM OR FUNCTION
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 withineach 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.
IAEA1379/05
This version include the updates up to 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:
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History Updated April, 2010
Activate: Generate activation cross sections (MF=10) from MF=3 and 9 data
VERS. 2010-1 (Apr. 2010) *General update based on user feedback
Complot: Plot comparisons of cross sections (MF=3, 23), see also Comhard
for hardcopy
VERS. 2010-1 (July 2010) *Allow comparison plot even if there
is no difference (just see data).
*ONLY plot linearly interpoolable data
*Include threshold energy points to show cross
sections, but NOT ratios near threshold.
*Moved points near resonance region boundary to
boundary - this attempts to change NJOY approximation
to move points on boundary slightly off, so there is
no discontinuity.
Convert: Convert codes for computer/precision/compiler
VERS. 2010-1 (Apr. 2010) *General update based on user feedback
Dictin: Create reaction dictionary (MF=1, MT=451)
VERS. 2010-1 (Apr. 2010) *General update based on user feedback
Evalplot: Plot evaluated data (MF=3, 4, 5, 23, 27), see also Evalhard for
hardcopy
VERS. 2010-1 (Aug. 2010) *Extended to plots up to 100 Legendre Coefficients
versus incident energy.
Fixup: Correct format and cross sections, define cross sections by summation
VERS. 2010-1 (Apr. 2010) *Defining cross sections by summation to now
mandatory - either build-in rules or by user input.
Groupie: Calculate group averages and multi-band parameters
VERS. 2010-1 (Apr. 2010) *Increased weighting spectrum to 30,000 from 3,000
energy points.
*Added output to plot/compare shielded and unshielded
cross sections.
Legend: Calculate/correct angular distributions
VERS. 2010-1 (Apr. 2010) *General update based on user feedback
Linear: Linearize cross sections
VERS. 2010-1 (Apr. 2010) *Skipped leading cross section = 0 up to effective
start, unless keeping ALL original energy points.
*Replaced ETHRES by ESTART - it is not a threshold
- just a minimum energy - if a section starts above
this energy with a positive cross section,
an additional point will inserted with x-section = 0.
Merger: Retrieve and/or Merge evaluated data
VERS. 2010-1 (Apr. 2010) *General update based on user feedback
Mixer: Calculate mixtures of cross sections
VERS. 2010-1 (Apr. 2010) *General update based on user feedback
Recent: Reconstruct cross sections from resonance parameters
VERS. 2010-1 (April 2010) *Added SAMRML LOGIC to handle all LRF=7 cases.
*Extended SAMRML LOGIC to process all evaluations
= resolved + unresolved + tabulated - SAMRML only
does one section of resolved LRF=7 data without
tabulated background.
*Updated elastic potential calculation for total
(SLBW) and correction for missing sequences
(MLBW, RM, HRF).
*Added hidden (optional) unresolved competition
listing (not ENDF/B).
Relabel: Relabel and sequence programs
VERS. 2010-1 (Apr. 2010) *General update based on user feedback
Sigma-1: Doppler broaden cross sections
VERS. 2010-1 (Apr. 2010) *Assume low energy log-log variation up to 1/a (eV)
for all but total and elastic.
*Changed default uncertainty to 0.01% from 0.1%
*Allow multiple, adjacent unresolved resonance regions
= combine into one larger energy range to copy.
*Do not broaden sections that start above 1 million
Kt - previously it was assumed total, elastic,
capture and fission, and large sections
(over 10,000 energy points) would broaden.
Sixpak: Convert double differential data (MF=6) to single differential
VERS. 2010-1 (Apr. 2010) *General update based on user feedback
Spectra: Convert model and general tabulation to linearized spectra (MF=5)
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.
Virgin: Calculated transmitted uncollided (virgin) flux and reactions
VERS. 2010-1 (Apr. 2010) *General update based on user feedback
*Increased incore page size to 600,000 from 240,000.