International Atomic
Energy Agency

Nuclear Data Services

DOCUMENTATION SERIES OF
THE IAEA NUCLEAR DATA SECTION

__________________________________________________

IAEA-NDS-39

Rev.
13, March 17, 2007

PREPRO 2007

2007 ENDF/B Pre-processing Codes

(ENDF/B-VII Tested)

Owned,
Maintained and Distributed

by

The Nuclear
Data Section

International
Atomic Energy Agency

P.O. Box 100

A-1400, Vienna , Austria

Originally
Written

by

Dermott E.
Cullen

University of California

Lawrence Livermore
National Laboratory

L-159

P.O. Box 808

Livermore, CA
94550, U.S.A.

tele:
925-423-7359

e.mail:
[email-masked]

website:
http://home.cast.net/~redcullen1

Abstract: The codes are named "the Pre-processing" codes,
because they are designed to pre-process ENDF formatted data, for later,
further processing for use in applications. This is a modular set of computer
codes, each of which reads and writes evaluated nuclear data in the ENDF
format. Each code performs one or more independent operations on the data, as
described below. These codes are designed to be computer independent, and are
presently operational on every type of computer from large mainframe computer
to small personal computers, such as IBM-PC and Power MAC. The codes are available on CD-ROM or diskettes from the
IAEA Nuclear Data Section, free of charge upon request or can be downloaded
from http://www-nds.iaea.org/ndspub/endf/prepro/

Nuclear Data Section

International Atomic Energy Agency

P.O.
Box 100

A-1400 Vienna

Austria

e-mail: [email-masked]

fax: (43-1) 26007

cable:
INATOM VIENNA

telex: 1-12645

telephone: (43-1) 2600-21710

Online:    TELNET or FTP:    iaeand.iaea.org

username:   IAEANDS for interactive
Nuclear Data Information System

username:   ANONYMOUS for FTP file
transfer;

Web:   http://www-nds.iaea.org

Note

The IAEA-NDS-reports should
not be considered as formal publications.
When a nuclear data library is sent out by the IAEA Nuclear Data
Section, it will be accompanied by an IAEA-NDS-report which should give the
data user all necessary documentation on contents, format and origin of the
data library.

IAEA-NDS-reports
are updated whenever there is additional information of relevance to the users
of the data library.

Neither
the originator of the data libraries nor the IAEA assume any liability for
their correctness or for any damages resulting from their use.

Citation guidelines

For
citations care should be taken that credit is given to the author of the data
library and/or to the data center which issued the data library.  The editor of the IAEA-NDS-report is
usually not the author of the data library.

This computer code package should be
cited as follows: D.E. Cullen, "PREPRO 2007: 2007 ENDF/B Pre-processing
Codes”, report IAEA-NDS-39, Rev. 13, March 17, 2007

Nuclear Data Section Introduction

ENDF is the
internationally agreed upon format for dissemination of evaluated nuclear data.
The ENDF/B data library has now been through seven (VII) versions; the latest
identified as ENDF/B-VII. Documentation for the current ENDF format and
convention is available in ENDF-102, from the National Nuclear
Data Center,
Brookhaven National Laboratory

http://www.nndc.bnl.gov/nndcscr/documents/endf/endf102/

or the Nuclear Data Section of the IAEA

http://www-nds.iaea.org/ndspub/endf/prepro/DOCUMENT/DOCUMENT.HTM

The 2007 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
Power MAC (OSX).

These codes
are available free of charge on CD_ROM upon request from the Nuclear Data
Section (see addresses on cover page) or downloaded from the Nuclear Data
Section Web page

http://www-nds.iaea.org/ndspub/endf/prepro/

The present
documentation (revision 13) completely
supersedes all previous documentation of earlier versions of the ENDF/B
Pre-processing data. It is strongly
recommended that you use ONLY the latest 2007 version of the PREPRO codes.
Failure to heed this warning can lead to completely erroneous results.

Conditions
for use of the codes

Any comments
on the use of the codes, including difficulties encountered or any suggestions
should be sent to the IAEA Nuclear Data Section. If any results obtained from
using these codes are used or referenced in a publication, a copy of the
publication should be sent to the IAEA Nuclear Data Section.

Dedication

Regardless of whose
name appears on the cover of this report, most of the work involved in
maintaining, testing and distributing the previous and current versions of the
PREPRO codes, was done by Kevin McLaughlin, Nuclear Data Section, IAEA, Vienna. For over 20 years
Kevin has played an invaluable role in updating and testing the PREPRO codes.
After all of these years I am sorry to have to report that Kevin has now
retired. I think I can speak for all present and past members of the Nuclear
Data Section in saying that Kevin will be greatly missed both as a coworker and
as a good friend.

Acknowledgement

I gratefully
acknowledge the contribution of Andrej Trkov in continuing to propose
interesting and useful extensions to these codes; keep those great ideas coming
Andrej. I acknowledge the contribution of Ivan Sirakov in testing these codes
and reporting all problems that he found; Ivan’s testing has greatly
improved the reliability of these codes. I also acknowledge Jennie
Manneschmidt, RSICC, Oak Ridge,
for her review of the documentation and testing of the codes prior to their
distribution through RSICC.

Table of Contents

History and Terminology

Features of 2007 Version

Running Time

All ENDF Formats and
Procedures

Consistent Handling of All
ENDF Formatted Data

Computer Independence

MAC OSX Executables

Bigger, Faster, Improved
Accuracy

On-Line Reports

Execution Timing

Features of All Versions

Code Documentation

Data Documentation

Obtaining the Codes

Your Feedback is
IMPORTANT!!!

Implementing the Codes

What Computers do the codes
run on?

The Most Up-to-Date
Installation Instructions

Register as a User

Use of Codes

Read the Output Reports

Standard and Variable
Filenames

Brief Description

Detailed Description

Verifying Implementation

Use of the Codes in
Combination

Details of Compiling and Loading Codes

Parts of the Codes

Compiling/Loading

Graphics Codes

Postscript Output Files

On Screen Graphics

Comments from Codes

ACTIVATE

CONVERT

COMPLOT

DICTIN

EVALPLOT

FIXUP

GROUPIE

LEGEND

LINEAR

MERGER

MIXER

RECENT

RELABEL

SIGMA1

SIXPAK

VIRGIN

History and Terminology

Originally the
Evaluated Nuclear Data File (ENDF) was divided into two different formats: ENDF/A which was designed to
contain partial evaluations that might later be incorporated into complete
evaluations, and ENDF/B which was designed to contain complete evaluations for
use in applications. Originally these were physically two different formats, but
circa 1970 both adopted the same format. Here I distinguish between the format,
such as the current ENDF-6 format,
and the data in the format, such as the current ENDF/B-VII data.

I try to distinguish
between the ENDF-6 format, and the ENDF/B data that is coded into this
format. The ENDF-6 format is now
used universally to store evaluated nuclear data: in the ENDF/B-VII library in the United States, in JEFF in Western Europe, in JENDL
in Japan, in CENDL in China, in BROND in Russia, etc. Here I will not
be concerned with the differences between the contents of these data libraries.
My only concern will be with the common ENDF-6
format, that all of these data libraries use. The PREPRO codes are designed
to process evaluated data in any version of the ENDF format. The ENDF format has now been through six
major versions, with the current format defined as ENDF-6.

Features
of 2007 Version

Compared to earlier
versions of these codes the 2007 version has the following features,

Running Time

It wasn't too many
years ago that in order to process major ENDF/B evaluations we needed super,
million dollar computers, and even then it could take days to process a large
evaluation, such as U-238.

Need I say it: those
days are gone forever. Today even small personal computers can be used to
quickly process any ENDF evaluations. For example, on my IBM-PC, Pentium IV,
3.6 GHz computer [not a million dollar computer, a $ 1,000 computer (year 2007)], I
can process U-238 in the time it takes me to go and get a cup of coffee - and with the next generation, it will require even less
time.

So I am not going to
list typical running times for the codes, for two reasons: 1) the running times
have now become trivial, and 2) by the time you get a copy of this report any
times I quote here will be outdated by the availability of newer, faster, and
cheaper computers.

Bottom line: running
time is no longer a major concern in processing ENDF data, and even small
personal computers are now powerful enough to be used to process all ENDF
evaluations.

All ENDF Formats and Procedures

These
codes can automatically determine the ENDF format version that each evaluation
is coded in and use the appropriate procedures. It should be particularly
noted, that these codes now handle all ENDF formats and procedures through
ENDF-6, and they have even been tested with all of the new ENDF/B-VII.0
evaluations that were approved by CSEWG in November 2006 and released for
public use in December 2006

WARNING: The 2007 codes include extensions to handle all current
ENDF formats and procedures, and corrections to problems that existed in
earlier versions of these codes. As such the 2007 codes completely supersede all earlier versions and it is strongly
recommended that all users of these codes only use the 2007 version of these
codes. Failure to heed this warning can lead to completely erroneous
results.

Consistent Handling of All ENDF Formatted Data

All of the codes now
use exactly the same routines to handle all ENDF formatted input and output.
This has resulted in a completely consistent interpretation of all ENDF
formatted data by all of the codes, and has also allowed the precision of the
ENDF output to be consistently extended in all codes. For 2007 the ENDF output
is completely consistent for input into C and C++ codes, while still
maintaining the accuracy of the data.

Optional Input Parameters

All
of the codes now allow input parameter files and ALL input parameters to be
optional; all input parameters now have built-in default values. Of particular
note is that allowable uncertainties are now optional input. This allows us to
select what we consider the best choices, based on the most recent advances in
the speed and size of computer.

Computer Independence

The only computer
dependence in the 2007 codes is to define running time. Routines to define
running time are supplied for most types of computers, and instructions are
provided in this report to help you define a timing routine for any other type
of computer.

MAC OSX Executables

Earlier versions of
PREPRO supplied executables for MAC OS9. The current PREPRO supplies executable
for MAC OSX (there is no executables for OS9). Under OSX the codes run much
faster than under OS9. Under OSX the codes appear to the user very similar to
how they appear on a UNIX or LINUX computer. The exception being the on-screen
graphics codes COMPLOT and EVALPLOT, which use the UNIX X11 graphics library.
On a MAC to execute these codes you must first start an X11 window and use this
as if it were a UNIX or Linux Window.

Bigger, Faster, Improved Accuracy

In line with the
enormous increase in computer sizes during the last few years, the 2007
versions are bigger, allowing more
complicated problems to be run much more efficiently, and in general allowing
each problem to be run much faster.

All of the codes now
use double precision throughout, resulting in improved accuracy. Compared to the earlier versions that used a
mixture of single and double precision, with modern compilers and hardware,
using double precision throughout has also contributed to making the codes faster.

On-Line Reports

All of the codes now
include an on-line report to your screen, and a report to an output file; the
on-line report allows users to monitor the progress of each code as it executes.
Earlier versions had no on-line report; as far as what the user saw, the code
started and ran to conclusion without printing anything on-line. This made it
impossible to monitor the progress of each code, and for long running problems
often resulted in users terminating the codes before they completed execution,
because it appeared that the codes weren't doing anything.

Execution Timing

The codes now include
a timer, to print execution time at the end of processing each evaluation
(MAT), and at the end of execution.

Features of All Versions

Code Documentation

These codes are
designed to be self-documenting, in the sense that the latest documentation for
each code is included as comments at the beginning of each code. Printed
documentation, such as this report, is periodically published and consists
mostly of a copy of the comment lines from the beginning of each code.

The user should be
aware that the comment lines within the codes are continually updated to
reflect the most recent status of the codes and these comments within the codes
should always be considered to be the most recent documentation for the codes
and may supersede published documentation, such as this document. Therefore
users are advised to always read the documentation within the actual code that
is being used.

Data Documentation

It is essential that
the pedigree of the evaluated data be documented. This is the purpose of the
comment lines at the beginning of each ENDF/B evaluation. The PREPRO codes are
designed to document any operations that they perform on ENDF/B data. If one of
these codes produces ENDF/B formatted output which in any way effects the
actual evaluated data, what the code did is documented by adding additional
comment lines at the end of the comment lines at the beginning of each
evaluation, defining the code and input parameters that it used. The sequence
of all such comments completely documents all of the operations that have been
performed on the data. Code users are advised that it is very important to leave
this documentation directly inside each evaluation, i.e., please do not modify
these codes or the evaluations to remove this documentation.

Obtaining the Codes

These codes are available free of charge on CD ROM upon
request from the Nuclear Data Section (see addresses on cover page) or
downloaded from the Nuclear Data Section Web page

http://www-nds.iaea.org/ndspub/endf/prepro/

Your Feedback
is IMPORTANT!!!

We are trying to develop a set of codes that are as
computer independent as possible. In this effort your feedback is IMPORTANT!!!
It is impossible for us to test these codes on all available computer/compiler
combinations. Therefore your experience, on your specific computer/compiler can
help us to improve the computer independence of these codes. It is also in your
best interest to share your experience with us, since it will insure that
future versions of these codes are as compatible as possible to meet your
needs.

Please send all feedback via e. mail at,

mailto:[email-masked]

Implementing the Codes

What
Computers do the codes run on?

The codes are designed to run on virtually any
computer. The exceptions to this rule are the interactive graphics codes complot and evalplot, which are designed to produce on-screen graphics on UNIX
workstations, IBM-PC, PowerMAC and VMS, i.e., not mainframe computers. However,
even these codes can be used in their non-interactive mode, named comhard and evalhard (note the names to indicate hardcopy output), to produce Postscript formatted files that can be
printed on any Postscript printer.

For use on IBM-PC running Windows or Linux, and on
PowerMAC, the distribution includes executables, ready to use immediately. For
use on a variety of UNIX based computers, the distribution includes a batch
file for each type of computer, to compile and load all programs, and to then
clean up by deleting everything not required to execute the programs. For other
types of computers, see the section below on, Details of Compiling and Loading Codes

The Most
Up-to-Date Installation Instructions

The most up-to-date installation instructions,
documentation, and the codes, can be downloaded from the website,

http://www-nds.iaea.org/ndspub/endf/prepro/

Read the text and then select “Download Codes”
or “Download Documentation”

We try to maintain these installation instructions
as up-to-date as possible, based on user feedback. So if you have any problems
or suggestions regarding installation please e.mail them to the Nuclear Data Section at,

mailto:[email-masked]

Register as a
User

We try to maintain these
codes and data as up-to-date as possible. So if you are using any of these
codes it is important that you tell us about this, so that the Nuclear Data
Section can put your name on the distribution list to inform you about the
latest updates. This is a FREE!!! service which is  provided to users of these codes. We
have tried to make this as easy as possible for you - PLEASE take a moment to
e.mail to mailto:[email-masked], and tell what codes you are using, and what type of
computer(s) you are using - it’s as simple as that.

Use of
Codes

Read the
Output Reports

MOST
IMPORTANT! You cannot use these codes like a black box and assume that
everything is perfect. Don't make the mistake of assuming that all ENDF/B data
is perfect, or that these codes are perfect. It's up to you, the code user, to
check and be sure that the data output by these codes is accurate and can be
used in applications. If you don't, you are wasting your time, and will produce
inaccurate results in your applications.

You can do this by reading the output reports
produced by each code. These output reports will generally be quite small. They
are intended to be used by you to quickly scan through them and look for
WARNING or ERROR messages - these indicate problems with the ENDF/B data that
you should check before using the data in any applications. You need not read
each output report in detail; it is sufficient to merely search for the words
WARNING or ERROR – these will always accompany important messages.

Checking these output reports doesn't take very much
time, but failing to check them can cause you to waste an awful lot of time and
can cause you headaches later, if you try to use data that a code has clearly
indicated to be bad. If there are errors in the ENDF/B data, you are clearly in
a “garbage in, garbage out” situation as far as the result you
calculate in your applications. Caveat
Emptor!

Standard and
Variable Filenames

Currently all input files and input parameters are
optional, and have built-in default values.

All of the codes have standard, built-in, filenames,
that they will use by default, unless input parameters explicitly define other
filenames.

The default filenames have been defined to make it
easy for you to remember, and to be compatible with as many operating systems
as possible, e.g., DOS, that only allows short filenames, and Unix, that allows
longer filenames. The default filenames are all of the form NAME.EXT, where
NAME identifies a program name, and EXT identifies the type of file. All
default filenames use ONLY upper
case characters. The basic filenames include,

1) ???.INP
- The INPut parameters for each
code, where ??? is the name of the code. For example, the input parameters for RECENT are in a file named RECENT.INP. This name cannot be changed
by input. Currently these input files are optional; if they are not present
default values are used for all input parameters.

2) ???.LST
- The output LiSTing from each code, where ??? is the name of the code. For
example, the output listing from RECENT
is in a file named RECENT.LST. This
name cannot be changed by input.

3) ???.IN
- ENDF formatted data to be read (INput)
be each code, where ??? is the name of the code. For example, the ENDF/B data
read by RECENT are in a file named RECENT.IN. This name can be changed by
input.

4) ???.OUT
- ENDF formatted data written (OUTput)
be each code, where ??? is the name of the code. For example, the ENDF/B data
written by RECENT are in a file
named RECENT.OUT. This name can be
changed by input.

The above simple filename conventions will allow you
to easily remember for each code, where the input parameters and output report
are located, as well as where the ENDF/B data that is read and written by the code
are located.

By input you can
change the filenames of the ENDF formatted data files; data read and/or
written.

If you input blank
filenames the codes will use the default names (described above).

If you input anything
else, the code will use the filenames you have defined. Variable filenames for
each code can be up to 60 characters long. This allows you to specify directory
structures, so that you can store your ENDF/B data in some rational way within
a directory file structure.

For example if you
store all of the ENDF/B-VI data files in a directory named ENDFB6, the
following input filename used with linear
will read a file named za092238 on an IBM-PC,

\ENDFB6\ORIGINAL\za092238

or on a Unix
workstation,

/ENDFB6/ORIGINAL/za092238

Warning - generally on Unix workstations you will have to include
the complete path to files. For example, the path to my files on my workstation
may be /home/pd11/cullen, in which case my filename should be,

/home/pd11/cullen/ENDFB6/ORIGINAL/za092238

The ability to directly
reference file structures is a very powerful facility that you should not
overlook in organizing your ENDF/B data.

Brief Description

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 (MF=6) to single differential

Fixup             -
Correct format and cross sections, define cross sections 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            -
Calculated transmitted uncollided (virgin) flux and reactions

Convert          -
Convert codes for computer/precision/compiler

Relabel           -
Relabel and sequence programs

Detailed Description

The codes can be used
to: 1) extensively check and correct evaluated data prior to using them in
applications, 2) pre-process the data into a form that will make subsequent use
of the data much easier.

The normal sequence
in which the codes are used is described below. WARNING  - this is the
recommended sequence of codes that you should run to produce LEGAL ENDF formatted data, that conforms
to ALL ENDF formats and conventions.
Note in particular that if you do not run FIXUP
and DICTIN at the end of this
sequence the resulting ENDF data WILL
NOT conform to all ENDF formats and conventions, and may cause problem if
you subsequently try to use the data.

1) LINEAR - Linearize cross sections. ENDF
format allows cross sections to be represented as 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 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 cross sections, i.e., replace the original
tabulated data points and interpolation law by a new table where one can use
linearly interpolation between tabulated points to within any required
accuracy.

2) RECENT - Add the contribution of
resonances to the cross sections. ENDF format allows cross sections to be
represented as a contribution of resonance parameters and tabulated background
corrections. This code will add the resonance contribution to the background cross
sections in order to define the cross sections as linearly interpolable tables
at 0 Kelvin (cold). Therefore subsequent codes need only deal with tabulated,
linearly interpolable, 0 Kelvin cross sections.

3) SIGMA1 - Doppler broaden cross sections
to any temperature of interest in applications. As in the case of LINEAR and
RECENT all cross sections read and written by this code are tabulated, linearly
interpolable. All subsequent codes need not explicitly consider temperature
effects and need only deal with tabulated, linearly interpolable cross sections
at a given temperature.

4) ACTIVATE – Combine neutron
interaction cross sections (MF=3) and multipliers (MF=9) to create activation
cross sections (MF=10). LINEAR and GROUPIE have been updated to process
multipliers (MF=9) and activation cross sections (MF=10). The sequence of codes
LINEAR, ACTIVATE, and GROUPIE allow you to produce group averaged activation
cross sections.

5) LEGEND - Convert tabulated
distributions and Legendre coefficients to linearly interpolable tables
(similar to what LINEAR does for
cross sections). Check all angular distributions and Legendre coefficients, in
particular check for negative angular distributions and if found, correct the
distributions to make them positive. Note, negative angular distributions can
lead to numerical instabilities and unreliable results if they are used in
applications.

6) SIXPAK - ENDF-6 format introduced
double differential data (MF=6) into the ENDF/B system for the first time. If
your application codes have not yet been updated to handle double differential
data, you can use SIXPAK to obtain
single differential (MF=4 and 5) approximations to double differential data.
Earlier versions of SIXPAK only output results for outgoing (emitted) neutrons
and photons, however currently SIXPAK will output angular distributions for
discrete charged particle levels.

7) FIXUP - Define all cross sections to be
consistently exactly equal to the sum of their parts, make format corrections,
and a number of other tests and corrections to the data, BEFORE the data is
actually used in applications. It is extremely important for use in
applications to guarantee that the cross sections are exactly consistent. For
example, the total cross section MUST to defined as equal to the sum of its
parts at all energies that appear in one or more of the contributing parts. In
addition it should be mentioned that the total will be equal to the sum of its
parts at all energies (not just the energies at which the total is tabulated),
only if all of the cross sections are linearly interpolable; this illustrates
the importance of the steps described above in processing data through each of
these codes. Note, if FIXUP's option to output all cross sections on a uniform
energy grid is used, the FIXUP output is compatible for use as NJOY input.

8) DICTIN - Update the section index in
MF=1, MT=451. This step need only be run if the subsequent codes that use the
data refer to this index. If you are unsure whether or not this is the case, it
is always best to include this step, since relative to the other codes
described above this step requires very little running time.

After this sequence
of codes has been run the results will be evaluated data that has been
carefully checked for consistency and has been reduced to a form that can be
used more easily and reliably in subsequent applications.

In addition to the
codes mentioned above, this package includes a number of useful utility codes
including,

1) MERGER - Retrieve and/or combine
evaluated data. This code can be used to create a single file of data in the
ENDF format from a number of different files, each of which is in the ENDF
format. It can also be used to retrieve specific evaluated data from a larger
ENDF/B library in order to simplify and optimize the subsequent use of the data
in applications, e.g., if you have an entire ENDF/B library, but will only be
using five evaluations for your applications, you can first use this code to
create a mini-library containing only the five evaluations that you need for
your application.

2) GROUPIE - Calculates self-shielded,
multigroup cross sections and multiband parameters. This code can be used as a
simple and very economical means of obtaining multigroup cross sections, in the
ENDF format, which can be used in many applications where only multigroup cross
sections are required, e.g., dosimetry. For comparing data using COMPLOT this code can be used to reduce
evaluations that have many resonances, to a form in which integral differences
through the resonance region can be more easily seen.

3) COMPLOT – Plot a comparison of
cross sections from two different evaluations. This code can be used to compare
cross sections, for each reaction, to define exactly how two evaluations
differ. This can be extremely important if one has already used a given
evaluation in applications and wishes to quickly and inexpensively determine
whether or not a newer evaluation can be expected to produce significantly
different results when used in applications. It is also an excellent and simple
means of documenting the differences between two evaluations, e.g., what's the
difference between the ENDF/B-VI, Release 4 and 5, U-235 cross sections? See
the above comments under GROUPIE for
suggestions concerning comparing evaluations that have many resonances. This
code can be used as a simple means of visually checking all of these cross
section data types and is often very useful to help understand the results
obtained when data is used in applications. In addition, the graphic Postscript
output can serve as a part of the documentation for evaluations. Two versions
of exactly the same code are provided: complot
to produce on-screen graphics, and comhard
to produce Postscript, hardcopy, output.

4) EVALPLOT - Plot cross sections,
angular distributions, Legendre coefficients and/or energy distributions, for
neutron interaction data, neutron induced photon production data, and photon
interaction data. This code can be used as a simple means of visually checking
all of these data types and is often very useful to help understand the results
obtained when data is used in applications. In addition, the graphic Postscript
output can serve as a part of the documentation for evaluations. Two versions
of exactly the same code are provided: evalplot
to produce on-screen graphics, and evalhard
to produce Postscript, hardcopy, output.

5) MIXER - Can be used to define the cross
sections for a combination of materials, e.g., stainless steel. This code can
be used in combination with COMPLOT
to see which energy ranges are important for each material and each constituent
of a material. This code can also be used to define the correct total cross
section for use in transmission calculations (see, VIRGIN), as well as in self-shielding calculations (see, GROUPIE), in order to avoid the
approximations normally incoherent in the Bonderenko method of self-shielding.
Since ENDF/B-VI has moved in the direction of representing separate isotopes
for each element, this code is particularly useful if your applications only
requires a natural mixture of isotopes, e.g., use MIXER to combine isotopes
into the natural element.

6) VIRGIN - Can be used to perform exact
uncollided (virgin) transmission calculations (exact, assuming the tabulated,
linearly interpolable cross sections are exact - no other approximations are
used). By using the data that has been prepared by a combination of LINEAR, RECENT, SIGMA1, MIXER, etc.,
this code can be used to simulate transmission through any given material, or
layers of different materials, at any given temperature. The results include
both transmitted flux and reaction rates (as measured in self-indication
measurements) vs. material thickness. The results can be obtained either on a
continuous energy basis, or they can be binned (energy integrated) to simulate
any given experimental resolution.

In addition there are
two utility codes that operate on the codes, rather than on ENDF/B data.

1) RELABEL - Is a file maintenance code
used to maintain all of the codes in this package. This code will normally not
be used by users, unless they plan to modify these codes.

2) CONVERT - Format and optimize codes for
use at any given computer installation. This code is no longer required by the
PREPRO, since the codes are now completely computer independent. It is still
included in this package only because users have found it useful for other
purposes. Generally this code was used only once to format all of the codes
prior to their first use on any computer.

Verifying Implementation

This distribution
comes with a file named VERIFY, which is designed to run all of the codes, one
after another, with the final two steps being to run EVALPLOT and COMPLOT, so
that you can see the final results. VERIFY is a simple text file; its contents
are shown below,

linear

recent

sigma1

activate

legend

fixup

dictin

groupie

mixer

virgin

evalplot

complot

When executed as a
batch file, this will run the codes in the order indicated. The distributed
input parameters have been defined so that each code reads the ENDF formatted
data file produced by the preceding code, and writes the ENDF formatted data
file that will be read by the following code.

To verify
implementation immediately after you have installed the codes, DO NOT change
any input parameters for ANY codes, and execute VERIFY. It will take between 5
minutes and an hour (depending on the speed of your computer), to run all of
the codes. When you get to the final two graphics codes, EVALPLOT and COMPLOT,
you can be assured that all of the codes have run successfully.

COMPLOT will compare
the cross sections calculated by you on your computer to a standard set of
results distributed with PREPRO 2007. In both cases cross sections are
calculated by each code to within an accuracy of 1 %. Therefore when COMPLOT
compares the results you may find differences of about 1 %. This difference is
o.k., and merely indicates the differences due to precision to which the cross
sections have been calculated. Subsequently, for use in your applications you
can feel free to modify the input parameters for each code to meet the
precision that you require.

WARNING – for
UNIX users - some UNIX systems now include diction as a system command. In
order to avoid this conflict, in PREPRO 2007 the code previously named diction
has been renamed dictin.

Use of the Codes in Combination

Almost any computer
will allow you to submit a batch job, in which case you can perform any number
of operations one after the other, as is done in the above verification. These
computers can utilize this facility to run any number of these codes in
combination, minimize the total amount of disk space used, and most important,
optimize the use of your time.

In order to run any
number of codes one after the other, all you need is the facility to: 1) start
a program, 2) rename a file, 3) delete a file, if you want to minimize disk
space.

For example, if I
want to run the sequence of codes, LINEAR,
RECENT, SIGMA1, ACTIVATE, LEGEND, FIXUP and DICTIN and only keep the original data read by LINEAR and the final results output by DICTIN, I can use the standard ENDF filenames for the data read
and written by each code, and submit the following batch file on an IBM-PC,

linear

rename LINEAR.OUT
RECENT.IN

recent

delete RECENT.IN

rename RECENT.OUT
SIGMA1.IN

sigma1

delete SIGMA1.IN

rename SIGMA1.OUT
ACTIVTE.IN

activate

delete ACTIVATE.IN

rename ACTIVATE.OUT
LEGEND.IN

legend

delete LEGEND.IN

rename LEGEND.OUT
FIXUP.IN

fixup

delete FIXUP.IN

rename FIXUP.OUT
DICTIN.IN

dictin

delete DICTIN.IN

Note, when each code
finishes the above batch deck renames the ENDF formatted data output by the
code to the filename of the ENDF formatted data input to the next code. When
the next code finishes, the ENDF formatted data input to it is deleted (we no
longer need it), and the cycle starts for the next code. More efficiently you
could have defined ENDF input and output file names in the input parameter
files for each code to link them together, e.g., instead of copying LINEAR.OUT
to RECENT.IN, you could have defined the input file to RECENT to be named
LINEAR.OUT.

The result will be
the original data read by LINEAR is
still in the file named LINEAR.IN,
and the final result is in the file named DICTIN.OUT.
All other intermediate files have been deleted.

On any other system,
such as Unix, the names delete and rename may be different, but the basic
idea remains the same.

An alternative to the
above approach is to use the facility of the codes to read and write files from
any file structure. For example, assume I have a directory named ENDFB6, and
within this directory I have three sub-directories: ORIGINAL, TMP, and K300
(data Doppler broadened to 300 Kelvin). What I can do is define LINEAR input parameters to read a file
from ENDFB6/ORIGINAL, define input parameters to RECENT, SIGMA1, ACTIVATE, LEGEND and FIXUP to produce ENDF output in ENDFB6/TMP, and have each code read
the output from the preceding code. Finally I can define DICTIN input parameters to write the ENDF output into ENDFB6/K300,
with its final filename. In this case if I do not worry about deleting the
intermediate files, the batch input need only be the names of the codes to run,
i.e.,

linear

recent

sigma1

activate

legend

fixup

dictin

Using a batch
approach can save you a great deal of your precious time. You don't have to sit
there and babysit your terminal in order to start each code as the preceding
one finishes. You can use batch jobs to combine code executions, and go off to
work (or play) until the sequence of codes finishes. If you then want to be sure
that everything ran correctly, you can read the output reports from each code,
i.e., see the ???.LST from each
code, e.g., for RECENT see RECENT.LST – it is HIGHLY Recommended that you always read these files.

Details of Compiling and Loading Codes

For use on IBM-PC
running Windows or Linux, and on PowerMAC, the distribution includes
executables, ready to immediately use. For use on a variety of UNIX based
computers, the distribution includes a batch file for each type of computer, to
compile and load all programs, and to then clean up by deleting everything not
required to execute the programs. Only for other types of computers need you be
concerned with the details concerning compiling and loading the codes, which
are described here.

Parts of the
Codes

The codes have now been divided into a number of
parts that should be combined when compiling and loading; see, example
compile/load instructions below. The parts are,

1) The basic code

2) An include file to define code storage

3) Routines to allow all codes to now uniformly
treat all ENDF formatted input and output (endfio.f)

4) Routines to allow scratch files to be defined
either with or without file names,

scratcha.f
= with file name

scratchb.f
= without file name

Most compilers/computers allow scratch files to be
defined without scratch file names, so use either scratcha.f or scratchb.f.
However, some compilers/system combinations get confused when there are
multiple scratch files without file names, e.g., Lahey on IBM-PC (use scratcha.f), and some compilers do not
allow scratch files with file names, e.g., ABSOFT on IBM-PC and Power MAC (use scratchb.f).

4) A timer, to define the execution time for each
code. The standard timer routine (timer.f)
distributed with the codes uses the standard Unix routine ETIME; on some computers you will have to consult the on-line
manual to see how to link to ETIME,
e.g., HP.

If you are not using a Unix based computer, you will
have to supply your own timing routine. It is recommended that you use the
distributed version of timer.f, and
add a function ETIME, that defines
the execution time on your computer - see, the timing routines included for a
variety of UNIX computers

If you do define a non-standard timer, try to define
EXECUTION - NOT WALL CLOCK time - on some computers this isn't possible, e.g.,
IBM-PC running DOS - in which case use whatever you can.

If you can't figure out how to define running time,
or you don't want the codes to print running time, instead of using the
distributed timer.f, define and use
the following dummy routine,

SUBROUTINE TIMER

RETURN

END

If you do define a non-standard timer, PLEASE send
us a copy, identifying what computer/compiler you are using - over a period of
time we intend to build up a library of timer routines for as many different
computers as possible - which we will then distribute with the codes = future
versions will be more compatible to meet your needs.

5) A graphics interface, for complot and evalplot.

Compiling/Loading

This section applies to all of the codes, except the
graphics codes, complot and evalplot; see, below under graphics
codes. Below is an example of how to compile/load the codes on a Unix based
computer. For this example I illustrate how to create executables on a SUN
workstation; timing routines are provided for most types of computers. Note,

1) No special libraries are used by these codes, so
that compile/load instructions are very simple.

2) How the pieces are combined.

3) Use the HIGHEST LEVEL OPTIMIZATION available on
your computer - this can make a BIG difference in running time.

4) SUN.f is the timing routine to use on a SUN
workstation. Similar timing routines are provided for most types of computers.

f77 -o linear
-O linear.f  endfio.f
scratchb.f timer.f SUN.f

f77 -o recent
-O recent.f  endfio.f
scratchb.f timer.f SUN.f

f77 -o sigma1
-O sigma1.f  endfio.f
scratchb.f timer.f SUN.f

f77 -o fixup   -O fixup.f   endfio.f scratchb.f timer.f SUN.f

f77 -o legend
-O legend.f  endfio.f
scratchb.f timer.f SUN.f

f77 -o sixpak
-O sixpak.f  endfio.f
scratchb.f timer.f SUN.f

f77 -o mixer   -O mixer.f   endfio.f scratchb.f timer.f SUN.f

f77 -o merger
-O merger.f  endfio.f
scratchb.f timer.f SUN.f

f77 -o dictin
-O dictin.f  endfio.f
scratchb.f timer.f SUN.f

f77 -o virgin
-O virgin.f  endfio.f scratchb.f
timer.f SUN.f

f77 -o groupie -O groupie.f endfio.f scratchb.f
timer.f SUN.f

f77 -o relabel -O relabel.f

f77 -o convert -O convert.f

Graphics
Codes

The graphics codes - complot and evalplot -
can be used to produce either,

1) Postscript output files for printed hardcopy,
using executables named comhard and evalhard.

2) On screen graphics, using executables named complot and evalplot.

The two executables, complot and comhard, are
exactly the same code, loaded with different graphics interfaces; both
executables use the same input and output files, COMPLOT.INP and COMPLOT.LST.
Similarly, the two executables, evalplot
and evalhard, are exactly the same
code, loaded with different graphics interfaces; both executables use the same
input and output files, EVALPLOT.INP
and EVALPLOT.LST.

Postscript
Output Files

The Postscript graphics interface should be
completely computer independent, and as such should run on any computer.

It will create a series of output files - none of
which are sent to your printer during execution of the code.

Output for each plot is saved on disk, so when the
code ends all of the plot files will still be on disk, and you can then send
them to your printer, and/or, save them for later use.

WARNING -
the codes always use the same file names, PLOT0001.ps,
PLOT0002.ps, etc. So that running a code again will overwrite any files
that you previously created. If you want to save files, moved them or rename
them before running a code again.

To use this method to create these Postscript files
use hardsave.f with the codes.

For Postscript graphics, no special libraries are
used, and an example of how to compile/load the codes on a Unix based computer
is shown below - this is very similar to the compile instructions shown above, with
the addition of hardsave.f,

f77 -o comhard
-O complot.f  endfio.f
scratchb.f timer.f hardsave.f SUN.f

f77 -o evalhard -O evalplot.f endfio.f scratchb.f
timer.f hardsave.f SUN.f

Note, that here the executables are given the names
for the hardcopy versions of the codes, comhard
and evalhard.

On Screen
Graphics

For on screen graphics the codes are loaded with screen.f, in contrast to the hardcopy
version of the codes, described above, for Postscript graphics that are loaded
with  hardsave.f.

Example Makefiles are included for a variety of Unix
systems.

On screen graphics is VERY computer dependent, so on
Unix computers you may have to modify the Unix Makefile - this should only
involve finding out where the X11 graphics library is on your computer, and
setting the correct path in the Makefile.

If you do have to modify the Makefile, please send
me a copy of the modified file, identifying your computer, so that we can build
up a library of Makefiles to be distributed with the codes then future versions
will be compatible with your needs.

The codes are distributed with graphics interfaces
for,

1) Unix, MAC OSX, and openVMS systems, using the X11
graphics library (screen.f, nodash.c, dash.c)

2) If you are using
any other system, you will have to supply your own graphics interface - see, screen.f for a description of the
simple interface used by these codes.

Interacting with Graphics

When you are using evalplot there is no true on-screen
interaction with the plots. If you wish to view different data over different
energy ranges your only option is to change your input parameters in the file EVALPLOT.INP.

When
you are using complot you can
interact with the on-screen plots. Once a plot is displayed on your screen if
you would like to see a portion of the energy range of the plot in greater
detail, you can do this by using your mouse to zoom in by indicating the lower
and upper energy limits of the energy range you would like to see. As soon as
you select the range the next zoomed plot will appear on your screen, with the
same data as on the previous plot, but only over the energy range that you have
selected. WARNING – complot
only generates plots when the two evaluations differ by more than the allowable
uncertainty you define by input in the file COMPLOT.INP. This also applies when you interact with the plots.
Therefore, if you use your mouse to select an energy range over which the two
evaluations do not differ by more than your allowable uncertainty a zoomed plot
will not be produced, but the results of the comparison will be reported in the
output file COMPLOT.LST, and complot
will proceed to its next comparison.

Comments from Codes

These codes are
designed to be self-documenting, in the sense that the most up-to-date
documentation is included as comments at the beginning of each code.
Periodically documentation, such as this report, is published. But the user is
warned that the comments in the codes are continuously updated and it is these
comments within the codes that should be considered to be the most up-to-date
documentation, and the user should read these comments before, and while, using
these codes.

The following section
contains a listing of the comments from the codes as of the publication date of
this report. The comments are listed for each code alphabetically according to
the name of the code, including,

ACTIVATE

CONVERT

COMPLOT

DICTIN

EVALPLOT

FIXUP

GROUPIE

LEGEND

LINEAR

MERGER

MIXER

RECENT

RELABEL

SIGMA1

SIXPAK

VIRGIN

=======================================================================
Activate

Activate

PROGRAM
ACTIVATE
Activate

VERS. 2000-1
(APRIL 2000)   *INITIAL
VERSION.
Activate

VERS. 2002-1
(MAY 2002)
*OPTIONAL INPUT PARAMETERS
Activate

VERS. 2004-1
(JAN. 2004)    *CORRECTED
ERROR - FIRST RECORD AFTER  Activate

MF=10 WAS MISSING.
Activate

*ADDED
INCLUDE TO DEFINE COMMON
Activate

*INCREASED MAX. POINTS FROM 100,000    Activate

TO 1,000,000.
Activate

VERS. 2007-1
(JAN. 2007)    *CHECKED
AGAINST ALL ENDF/B-VII
Activate

Activate

Acknowledgement
2004
Activate

--------------------
Activate

Currently almost
all improvements to this code are based upon      Activate

feedback from
code users who report problems. This feedback
Activate

benefits ALL
users of this code, and ALL users are encouraged      Activate

to report
problems.
Activate

Activate

Improvements on
the 2004 version of this code based on user
Activate

feedback
including,
Activate

1) Andrej Trkov
- reported that the first record of the section    Activate

after an inserted MF=10 was missing.
Activate

Activate

OWNED,
MAINTAINED AND DISTRIBUTED BY
Activate

------------------------------------
Activate

THE NUCLEAR DATA
SECTION
Activate

INTERNATIONAL
ATOMIC ENERGY AGENCY
Activate

P.O. BOX 100
Activate

A-1400, VIENNA, AUSTRIA
Activate

EUROPE
Activate

Activate

ORIGINALLY WRITTEN
BY
Activate

------------------------------------
Activate

DERMOTT E.
CULLEN
Activate

UNIVERSITY OF CALIFORNIA
Activate

LAWRENCE
LIVERMORE
NATIONAL LABORATORY
Activate

L-159
Activate

P.O. BOX 808                                                       Activate

LIVERMORE, CA
94550
Activate

U.S.A.
Activate

TELEPHONE  925-423-7359                                            Activate

E. MAIL    [email-masked]
Activate

WEBSITE
HTTP://WWW.LLNL.GOV/CULLEN1
Activate

Activate

AUTHORS
MESSAGE
Activate

---------------
Activate

THE REPORT
DESCRIBED ABOVE IS THE LATEST PUBLISHED DOCUMENTATION   Activate

FOR THIS
PROGRAM. HOWEVER, THE COMMENTS BELOW SHOULD BE CONSIDERED Activate

THE LATEST
DOCUMENTATION INCLUDING ALL RECENT IMPROVEMENTS. PLEASE Activate

READ ALL OF
THESE COMMENTS BEFORE IMPLEMENTATION.                  Activate

Activate

AT THE PRESENT
TIME WE ARE ATTEMPTING TO DEVELOP A SET OF COMPUTER Activate

INDEPENDENT
PROGRAMS THAT CAN EASILY BE IMPLEMENTED ON ANY ONE     Activate

OF A WIDE
VARIETY OF COMPUTERS. IN ORDER TO ASSIST IN THIS PROJECT Activate

IT WOULD BE
APPECIATED IF YOU WOULD NOTIFY THE AUTHOR OF ANY       Activate

COMPILER
DIAGNOSTICS, OPERATING PROBLEMS OR SUGGESTIONS ON HOW TO  Activate

IMPROVE THIS
PROGRAM. HOPEFULLY, IN THIS WAY FUTURE VERSIONS OF    Activate

THIS PROGRAM
WILL BE COMPLETELY COMPATIBLE FOR USE ON YOUR
Activate

COMPUTER.
Activate

Activate

PURPOSE
Activate

-------
Activate

THIS PROGRAM IS
DESIGNED TO CREATE FILE 10 ACTIVATION CROSS
Activate

SECTIONS BY
COMBINING FILE 3 CROSS SECTIONS AND FILE 9 MULTIPLIERS Activate

Activate

IN THE FOLLOWING
DISCUSSION FOR SIMPLICITY THE ENDF/B TERMINOLOGY  Activate

---ENDF/B
TAPE---WILL BE USED. IN FACT THE ACTUAL MEDIUM MAY BE    Activate

TAPE, CARDS,
DISK OR ANY OTHER MEDIUM.
Activate

Activate

ASSUMPTIONS
Activate

-----------
Activate

IT IS ASSUMED
THAT THE FILE 3 AND 9 DATA HAVE BEEN LINEARIZED      Activate

BEFORE THIS CODE
IS USED - FILE 3 AND 9 DATA CAN BE LINEARIZED     Activate

USING PROGRAM
LINEAR.
Activate

Activate

IT IS ASSUMED
THAT THE FILE 9 MULTIPLIERS ARE FAIRLY SMOOTH VERSUS Activate

ENERGY, AND THAT
THE ACTIVATION CROSS SECTIONS FOR FILE 10 CAN BE  Activate

DEFINED AT
EXACTLY THE SAME ENERGIES AS THE FILE 3 CROSS SECTIONS, Activate

AND THAT THESE
NEED MERELY BE MULTIPLIED BY THE FILE 9 TO DEFINE   Activate

THE FILE 10
ACTIVATION CROSS SECTIONS.
Activate

Activate

ENDF/B
FORMAT
Activate

-------------
Activate

THIS PROGRAM
ONLY USES THE ENDF/B BCD OR CARD IMAGE FORMAT (AS     Activate

OPPOSED TO THE
BINARY FORMAT) AND CAN HANDLE DATA IN ANY VERSION   Activate

OF THE ENDF/B
FORMAT (I.E., ENDF/B-I, II,III, IV, V OR VI FORMAT). Activate

Activate

IT IS ASSUMED
THAT THE DATA IS CORRECTLY CODED IN THE ENDF/B       Activate

FORMAT AND NO
ERROR CHECKING IS PERFORMED. IN PARTICULAR IT IS     Activate

ASSUMED THAT THE
MAT, MF AND MT ON EACH LINE IS CORRECT. SEQUENCE  Activate

NUMBERS (COLUMNS
76-80) ARE IGNORED ON INPUT, BUT WILL BE
Activate

CORRECTLY OUTPUT
ON ALL LINES. THE FORMAT OF SECTION MF=1, MT=451  Activate

AND ALL SECTIONS
OF MF=3 MUST BE CORRECT. THE PROGRAM COPIES ALL   Activate

OTHER SECTION OF
DATA AS HOLLERITH AND AS SUCH IS INSENSITIVE TO   Activate

THE CORRECTNESS
OR INCORRECTNESS OF ALL OTHER SECTIONS.
Activate

Activate

OUTPUT
FORMAT
Activate

-------------
Activate

ALL ENERGIES
WILL BE OUTPUT IN F (INSTEAD OF E) FORMAT IN ORDER    Activate

TO ALLOW
ENERGIES TO BE WRITTEN WITH UP TO 9 DIGITS OF ACCURACY.   Activate

COMPARISON OF
THE NORMAL ENDF/B CONVENTION OF 6 DIGITS TO
THE 9    Activate

DIGIT OUTPUT
FROM THIS PROGRAM DEMONSTRATED THAT FAILURE TO USE    Activate

THE 9 DIGIT
OUTPUT CAN LEAD TO LARGE ERRORS IN THE DATA DUE TO     Activate

TRUNCATION OF
ENERGIES TO 6 DIGITS DURING OUTPUT.
Activate

Activate

CONTENTS OF
OUTPUT
Activate

------------------
Activate

ENTIRE
EVALUATIONS ARE OUTPUT, NOT JUST THE PROCESSED DATA, E.G.,  Activate

ANGULAR AND
ENERGY DISTRIBUTIONS ARE ALSO INCLUDED.
Activate

Activate

DOCUMENTATION
Activate

-------------
Activate

THE FACT THAT
THIS PROGRAM HAS OPERATED ON THE DATA IS DOCUMENTED  Activate

BY THE ADDITION
OF 3 COMMENT LINES AT THE END OF EACH HOLLERITH    Activate

SECTION IN THE
FORM
Activate

Activate

***************** PROGRAM ACTIVATE (2007-1) ****************       Activate

FILE 10
ACTIVATION CROSS SECTIONS HAVE BEEN DEFINED BY COMBINING   Activate

FILE 3 CROSS
SECTIONS AND FILE 9 MULTIPLIERS. FILE 9 DELETED.      Activate

Activate

THE ORDER OF
SIMILAR COMMENTS (FROM RECENT, SIGMA1 AND GROUPIE)    Activate

REPRESENTS A
COMPLETE HISTORY OF ALL OPERATIONS PERFORMED ON       Activate

THE DATA BY
THESE PROGRAMS.
Activate

Activate

THESE COMMENT
LINES ARE ONLY ADDED TO EXISTING HOLLERITH SECTIONS, Activate

I.E., THIS
PROGRAM WILL NOT CREATE A HOLLERITH SECTION. THE FORMAT Activate

OF THE HOLLERITH
SECTION IN ENDF/B-V DIFFERS FROM THE THAT OF      Activate

EARLIER VERSIONS
OF ENDF/B. BY READING AN EXISTING MF=1, MT=451    Activate

IT IS POSSIBLE
FOR THIS PROGRAM TO DETERMINE WHICH VERSION OF      Activate

THE ENDF/B
FORMAT THE DATA IS IN. WITHOUT HAVING A SECTION OF      Activate

MF=1, MT=451
PRESENT IT IS IMPOSSIBLE FOR THIS PROGRAM TO
Activate

DETERMINE WHICH
VERSION OF THE ENDF/B FORMAT THE DATA IS IN, AND   Activate

AS SUCH IT IS
IMPOSSIBLE FOR THE PROGRAM TO DETERMINE WHAT FORMAT  Activate

SHOULD BE USED
TO CREATE A HOLLERITH SECTION.
Activate

Activate

REACTION
INDEX
Activate

--------------
Activate

THIS PROGRAM
DOES NOT USE THE REACTION INDEX WHICH IS GIVEN IN     Activate

SECTION MF=1,
MT=451 OF EACH EVALUATION.
Activate

Activate

THIS PROGRAM
DOES NOT UPDATE THE REACTION INDEX IN MF=1, MT=451.   Activate

THIS CONVENTION
HAS BEEN ADOPTED BECAUSE MOST USERS DO NOT
Activate

REQUIRE A
CORRECT REACTION INDEX FOR THEIR APPLICATIONS AND IT WAS Activate

NOT CONSIDERED
WORTHWHILE TO INCLUDE THE OVERHEAD OF CONSTRUCTING  Activate

A CORRECT
REACTION INDEX IN THIS PROGRAM. HOWEVER, IF YOU REQUIRE  Activate

A REACTION INDEX
FOR YOUR APPLICATIONS, AFTER RUNNING THIS PROGRAM Activate

YOU MAY USE
PROGRAM DICTIN TO CREATE A CORRECT REACTION INDEX.     Activate

Activate

SECTION
SIZE
Activate

------------
Activate

SECTIONS OF MF=9
MULTIPLIERS ARE LIMITED TO A MAXIMUM OF 10,000    Activate

ENERGY
POINTS.
Activate

Activate

THERE IS NO
LIMIT ON THE NUMBER OF ENERGY POINTS IN MF=3 AND 10    Activate

TABLES.
Activate

Activate

SELECTION OF
DATA
Activate

-----------------
Activate

THE PROGRAM
PROCESSES ALL ENDF/B DATA ON A SERIES OF ENDF/B TAPES. Activate

Activate

PROGRAM
OPERATION
Activate

-----------------
Activate

PASS #1
Activate

-------
Activate

THE ENTIRE MAT
IS COPIED TO A SCRATCH FILE IN THE ENDF/B ASCII     Activate

FORMAT AND WHILE
COPYING IT TO SCRATCH MF=3, 9, AND 10 ARE ALSO    Activate

COPIED TO
SEPERATE SCRATCH FILES, I.E., THERE ARE A TOTAL OF 4     Activate

SCRATCH FILES -
SEE THEIR DEFINITIONS BELOW.
Activate

Activate

PASS #2
Activate

-------
Activate

IF NO MF=9
MULTIPLIERS ARE FOUND DURING PASS #1, THE ENTIRE MAT    Activate

IS COPIED FROM
SCRATCH TO THE OUTPUT FILE, WITHOUT ANY CHECKS.     Activate

Activate

IF MF=9
MULTIPLIERS ARE FOUND THEY ARE USED WITH MF=3 CROSS
Activate

SECTIONS TO
CREATE MF=10 ACTIVATION CROSS SECTIONS.
Activate

Activate

FOR ANY SECTION
OF MF=10 DATA FOR WHICH NO MF=9 MULTIPLIERS ARE    Activate

FOUND, THE
ORIGINAL MF=10 IS OUTPUT.
Activate

Activate

FOR CONSISTENCY
ALL MF=9 MULTIPLIERS ARE DELETED, I.E., THEY ARE   Activate

NOT INCLUDED IN
THE OUTPUT.
Activate

Activate

KEEP EVALUATED
DATA POINTS
Activate

--------------------------
Activate

THE FILE 10
OUTPUT WILL BE AT EXACTLY THE SAME ENERGY POINTS AS    Activate

THE FILE 3 CROSS
SECTIONS USED TO DEFINE THE FILE 10 ACTIVATION    Activate

CROSS
SECTIONS.
Activate

Activate

INPUT FILES
Activate

-----------                                                        Activate

UNIT  DESCRIPTION
Activate

----  -----------
Activate

2  INPUT LINES (BCD - 80
CHARACTERS/RECORD)
Activate

10  ORIGINAL ENDF/B DATA (BCD
- 80 CHARACTERS/RECORD)
Activate

Activate

OUTPUT
FILES
Activate

------------
Activate

UNIT  DESCRIPTION
Activate

----  -----------
Activate

3  OUTPUT REPORT (BCD - 120
CHARACTERS/RECORD)
Activate

11  FINAL ENDF/B DATA (BCD -
80 CHARACTERS/RECORD)
Activate

Activate

SCRATCH
FILES
Activate

-------------
Activate

UNIT  DESCRIPTION
Activate

----  -----------
Activate

12  SCRATCH FILE FOR ALL MAT
(BCD - 80 CHARACTERS/RECORD)
Activate

14  SCRATCH FILE FOR MF=3
DATA (BCD - 80 CHARACTERS/RECORD)      Activate

15  SCRATCH FILE FOR MF=9
DATA (BCD - 80 CHARACTERS/RECORD)      Activate

16  SCRATCH FILE FOR MF=10
DATA (BCD - 80 CHARACTERS/RECORD)     Activate

Activate

OPTIONAL
STANDARD FILE NAMES (SEE SUBROUTINE FILEIO)
Activate

----------------------------------------------------
Activate

UNIT  FILE NAME
Activate

----  ----------
Activate

2   ACTIVATE.INP
Activate

3   ACTIVATE.LST
Activate

10   ENDFB.IN                                                     Activate

11   ENDFB.OUT
Activate

12   (SCRATCH)
Activate

14   (SCRATCH)
Activate

15   (SCRATCH)
Activate

Activate

INPUT
PARAMETERS
Activate

----------------
Activate

Activate

LINE  COLS.  DESCRIPTION
Activate

----  -----  -----------
Activate

1   1-60  ENDF/B INPUT DATA FILENAME
Activate

(STANDARD OPTION = ENDFB.IN)
Activate

2   1-60  ENDF/B OUTPUT DATA FILENAME
Activate

(STANDARD OPTION = ENDFB.OUT)
Activate

Activate

ANY NUMBER OF
PAIRS OF INPUT LINES MAY BE USED, TO PROCESS ANY     Activate

NUMBER OF ENDF/B
TAPES, ONE AFTER ANOTHER.
Activate

Activate

EXAMPLE INPUT
NO. 1
Activate

-------------------
Activate

PROCESS ENDF/B
TAPES NAMED, TAPE121, TAPE122, AND TAPE123, AND     Activate

NAME THE OUTPUT
FILES ACTIVATE121, ACTIVATE122, AND ACTIVATE123.   Activate

Activate

IN THIS CASE THE
FOLLOWING 6 INPUT LINES ARE REQUIRED
Activate

Activate

TAPE121
Activate

ACTIVATE121
Activate

TAPE122
Activate

ACTIVATE122
Activate

TAPE123
Activate

ACTIVATE123
Activate

Activate

EXAMPLE INPUT
NO. 2
Activate

-------------------
Activate

SAME AS THE
ABOVE CASE, EXCEPT THAT IN THIS CASE THE ORIGINAL      Activate

3 TAPES ARE IN A
DIRECTORY NAMED \ENDFB6\ORIGINAL, AND THE
Activate

RESULTS WILL BE
WRITTEN INTO A DIRECTORY NAMED \ENDFB6\ACTIVATE.   Activate

Activate

IN THIS CASE THE
FOLLOWING 6 INPUT LINES ARE REQUIRED
Activate

Activate

\ENDFB6\ORIGINAL\TAPE121
Activate

\ENDFB6\ACTIVATE\ACTIVATE121
Activate

\ENDFB6\ORIGINAL\TAPE122
Activate

\ENDFB6\ACTIVATE\ACTIVATE122
Activate

\ENDFB6\ORIGINAL\TAPE123
Activate

\ENDFB6\ACTIVATE\ACTIVATE123
Activate

Activate

=======================================================================
Activate

=======================================================================
Complot

Complot

PROGRAM
COMPLOT
Complot

===============
Complot

VERSION 83-1
(FEBRUARY, 1983)
Complot

VERSION 83-2
(MAY, 1983)
Complot

VERSION 83-3
(DECEMBER, 1983) *MAJOR MODIFICATION.
Complot

*ADDED SELECTION OF PLOTS BY MAT OR
Complot

ZA/MT/ENERGY RANGE (EV).
Complot

*ADDED VARIABLE AXIS UNITS (PROGRAM
Complot

CONTROLLED..X=MILLI-EV, EV, KEV,    Complot

MEV...Y=MILLI-BARNS, BARNS).
Complot

VERSION 84-1
(APRIL, 1984)    *ADDED
SELECTION BY REACTION/ENERGY
Complot

RANGE.
Complot

*ADDED IDENTIFY DATA POINTS OPTION   Complot

(SMALL BOX DRAWN AROUND EACH CROSS
Complot

SECTION AND RATIO POINT).
Complot

*IMPROVED NON-IBM GRAPHICS INTERFACE Complot

(ALL CHARACTER POSITIONING NOW      Complot

BASED ON CHARACTER, NOT RASTER,    Complot

SIZE).
Complot

VERSION 85-1
(APRIL, 1985)    *SPECIAL
I/O ROUTINES TO GUARANTEE
Complot

ACCURACY OF ENERGY.
Complot

*DOUBLE
PRECISION TREATMENT OF
Complot

ENERGY (REQUIRED FOR NARROW
Complot

RESONANCES).
Complot

*ADDED
(ZA,MT)
EQUIVALENCE OPTION.   Complot

*ADDED SMALL PLOT OPTION.
Complot

VERSION 85-2
(AUGUST, 1985)   *FORTRAN-77/H
VERSION
Complot

VERSION 86-1
(JANUARY, 1986)  *ENERGY DEPENDENT
SCATTERING RADIUS  Complot

VERSION 86-2
(DECEMBER, 1986) *DOUBLE PRECISION PLOT SCALING       Complot

(REQUIRED FOR
NARROW ENERGY
RANGES) Complot

VERSION 88-1
(JULY 1988)
*MAJOR REVISION TO MAKE CODE EASILY
Complot

INTERFACEABLE TO ALMOST ANY PLOTTER Complot

*WARNING..INPUT PARAMETERS FROM BEEN Complot

CHANGED (SEE, DESCRIPTION BELOW)    Complot

*COMPUTER INDEPENDENT SOFTWARE       Complot

CHARACTERS.
Complot

*COLOR PLOTS.
Complot

*MT NUMBER DEFINITIONS FROM DATA     Complot

FILE READ BY PROGRAM
Complot

*FORTRAN-77 REQUIRED (FORTRAN-H NO
Complot

SUPPORTED BY THIS PROGRAM).
Complot

*OPTION...INTERNALLY DEFINE ALL I/O
Complot

FILE NAMES (SEE, SUBROUTINE FILEIO
Complot

FOR DETAILS).
Complot

*IMPROVED BASED ON USER COMMENTS.    Complot

VERSION 88-2
(OCTOBER 1988)   *IMPROVED
BASED ON USER COMMENTS.
Complot

*ADDED
LIVERMORE CIVIC
COMPILER
Complot

CONVENTIONS.
Complot

*UPDATED TO USE NEW PROGRAM CONVERT
Complot

KEYWORDS.
Complot

VERSION 89-1
(JANUARY 1989)
*PSYCHOANALYZED BY PROGRAM FREUD TO
Complot

INSURE PROGRAM WILL NOT DO ANYTHING Complot

CRAZY.
Complot

*FORTRAN-77/FORTRAN-H COMPATIBLE     Complot

*SPECIAL ENDF/B MATERIAL DEFINITIONS Complot

(ZA.LT.1000) FROM DATA FILE READ    Complot

BY PROGRAM.
Complot

VERSION 89-2
(MARCH 1989)
*ADDED ENDF/B-V AND VI MT
Complot

DEFINITIONS. PROGRAM WILL DETERMINE Complot

ENDF/B FORMAT BASED ON MF=1,
Complot

MT=451 AND USE AS PPROPRIATE MT     Complot

DEFINITIONS. IF NO MF=1, MT=451     Complot

PROGRAM WILL USE ENDF/B-VI
Complot

MT DEFINITIONS.
Complot

VERSION 90-1
(AUGUST 1990)    *A NEW
PROGRAM
Complot

*ADDED INTERACTIVE MOUSE INPUT       Complot

*ADDED 3 CHARACTER FONTS
Complot

*ADDED PHOTON DATA, MF=23 AND 27     Complot

*ADDED FORTRAN SAVE OPTION.
Complot

*ADDED MAXIMUM RATIO RANGE WHEN      Complot

PLOTTING RATIOS.
Complot

*ADDED
GRID TYPES
Complot

*ADDED VARIABLE LINE THICKNESS       Complot

*WARNING...INPUT PARAMETER FORMAT    Complot

HAS
BEEN CHANGED...SEE DESCRIPTION
Complot

BELOW.
Complot

VERSION 92-1
(JANUARY 1992)   *ADDED
INCIDENT CHARGED PARTICLES
Complot

(IDENTIFIED
IN PLOT TITLES)
Complot

*ADDED COMPLETELY COMPATIBLE I/O     Complot

FOR READING
FLOATING POINT NUMBERS. Complot

VERSION 92-2
(MAY 1992)
*CORRECTED DESCRIPTION OF INPUT      Complot

PARAMETERS AND EXAMPLE PROBLEMS.    Complot

*ADDED VARIABLE CHARACTER SIZE INPUT Complot

VERSION 93-1
(MARCH 1993)
*UPDATE FOR ON SCREEN GRAPHIC
Complot

OUTPUT USING THE LAHEY COMPILER     Complot

*ADDED NU-BAR (TOTAL, DELAYED,       Complot

PROMPT).
Complot

VERSION 94-1
(JANUARY 1994)   *VARIABLE
ENDF/B DATA FILENAMES      Complot

TO ALLOW ACCESS TO FILE STRUCTURES
Complot

(WARNING - INPUT PARAMETER FORMAT   Complot

HAS BEEN CHANGED)
Complot

*CLOSE ALL FILES BEFORE TERMINATING
Complot

(SEE, SUBROUTINE ENDIT)
Complot

VERSION 95-1
(MARCH 1995)
*CORRECTED CROSS SECTION
Complot

MULTIPLIER FOR EQUIVALENCES
Complot

*CORRECTED RATIO SCALING, FOR
Complot

MAXIMUM
RATIO LESS THAN 1.0
Complot

VERSION 96-1
(JANUARY 1996)   *COMPLETE
RE-WRITE
Complot

*IMPROVED COMPUTER INDEPENDENCE      Complot

*ALL
DOUBLE PRECISION
Complot

*UNIFORM TREATMENT OF ENDF/B I/O     Complot

*IMPROVED OUTPUT PRECISION
Complot

*DEFINED
SCRATCH FILE NAMES
Complot

*INCREASED PAGE SIZE FROM 24000      Complot

TO 48000 POINTS
Complot

VERSION 97-1
(APRIL 1997)     *INCREASED
PAGE SIZE FROM 48000      Complot

TO 480000 POINTS
Complot

VERSION 99-1
(MARCH 1999)   *CORRECTED
CHARACTER TO FLOATING       Complot

POINT READ FOR MORE DIGITS
Complot

*UPDATED TEST FOR ENDF/B FORMAT
Complot

VERSION BASED ON RECENT FORMAT CHANGE Complot

*GENERAL IMPROVEMENTS BASED ON
Complot

USER FEEDBACK
Complot

VERS. 2000-1
(FEBRUARY 2000)*GENERAL IMPROVEMENTS BASED ON
Complot

USER FEEDBACK
Complot

VERS. 2002-1
(MAY 2002)     *INPUT
PARAMETERS OPTIONAL
Complot

*CONTROL MINIMUM RATIO
RANGE BY INPUT  Complot

*OPTIONAL BLACK OR WHITE BACKGROUND    Complot

VERS. 2004-1
(SEPT. 2004)   *ADDED INCLUDE
FOR COMMON
Complot

*INCREASED PAGE SIZE FROM 480000       Complot

TO 600000 POINTS
Complot

*ADDED
NEW REICH-MOORE TO FILE2 TO     Complot

ALLOW IDENTIFICATION OF RESOLVED AND  Complot

ANY FOLLOWING UNRESOLVED RESONANCE    Complot

REGIONS.
Complot

VERS. 2007-1
(JAN.  2007)   *CHECKED AGAINST ALL ENDF/B-VII.       Complot

*INCREASED MAXLOAD TO 600,000 FROM     Complot

12,000
Complot

Complot

OWNED,
MAINTAINED AND DISTRIBUTED BY
Complot

------------------------------------
Complot

THE NUCLEAR DATA
SECTION
Complot

INTERNATIONAL
ATOMIC ENERGY AGENCY
Complot

P.O. BOX 100
Complot

A-1400, VIENNA, AUSTRIA
Complot

EUROPE
Complot

Complot

ORIGINALLY
WRITTEN BY
Complot

------------------------------------
Complot

DERMOTT E.
CULLEN
Complot

UNIVERSITY OF CALIFORNIA
Complot

LAWRENCE
LIVERMORE
NATIONAL LABORATORY
Complot

L-159
Complot

P.O. BOX 808
Complot

LIVERMORE, CA
94550
Complot

U.S.A.
Complot

TELEPHONE  925-423-7359
Complot

E. MAIL    [email-masked]
Complot

WEBSITE
HTTP://WWW.LLNL.GOV/CULLEN1
Complot

Complot

Complot

AUTHORS
MESSAGE
Complot

---------------                                                    Complot

THE COMMENTS
BELOW SHOULD BE CONSIDERED THE LATEST DOCUMENTATION   Complot

ALL RECENT
IMPROVEMENTS. PLEASE READ ALL OF THESE COMMENTS BEFORE, Complot

PARTICULARLY THE
COMMENTS CONCERNING MACHINE DEPENDENT CODING.     Complot

Complot

AT THE PRESENT
TIME WE ARE ATTEMPTING TO DEVELOP A SET OF COMPUTER Complot

INDEPENDENT
PROGRAMS THAT CAN EASILY BE IMPLEMENTED ON ANY ONE     Complot

OF A WIDE
VARIETY OF COMPUTERS. IN ORDER TO ASSIST IN THIS PROJECT Complot

IT WOULD BE
APPECIATED IF YOU WOULD NOTIFY THE AUTHOR OF ANY       Complot

COMPILER
DIAGNOSTICS, OPERATING PROBLEMS OR SUGGESTIONS ON HOW TO  Complot

IMPROVE THIS
PROGRAM. HOPEFULLY, IN THIS WAY FUTURE VERSIONS OF    Complot

THIS PROGRAM
WILL BE COMPLETELY COMPATIBLE FOR USE ON YOUR
Complot

COMPUTER.
Complot

Complot

PURPOSE
Complot

-------
Complot

COMPARE ENDF/B
FORMATTED DATA FROM TWO SEPARATE INPUT TAPES.       Complot

REACTIONS ARE
CONSIDERED TO BE COMPARABLE IF THEY HAVE THE SAME    Complot

(ZA,MF,MT).
RESULTS ARE PRESENTED IN GRAPHICAL FORM.
Complot

Complot

IN THE FOLLOWING
FOR SIMPLICITY THE ENDF/B TERMINOLOGY--ENDF/B     Complot

TAPE--WILL BE
USED. IN FACT THE ACTUAL MEDIUM MAY BE TAPE, CARDS,  Complot

DISK OR ANY
OTHER MEDIUM.
Complot

Complot

ON WHAT
COMPUTERS WILL THE PROGRAM RUN
Complot

------------------------------------------------------------------
Complot

THE PROGRAM HAS
BEEN IMPLEMENTED ON A VARIETY OF COMPUTERS FROM    Complot

CRAY AND IBM
MAINFRAME TO SUN WORKSTATIONS TO AN IBM-AT PC. THE    Complot

PROGRAM IS SMALL
ENOUGH TO RUN ON VIRTUALLY ANY COMPUTER.
Complot

Complot

THE PROGRAM USES
A SIMPLE CALCOMP LIKE GRAPHICS INTERFACE
Complot

(DESCRIBED
BELOW) AND ALLOWS THE USER SPECIFY THE PHYSICAL SIZE    Complot

OF THE PLOTTER
BEING USED, BY INPUT PARAMETERS. USING THESE
Complot

CONVENTIONS THIS
PROGRAM CAN BE EASILY INTERFACED TO VIRTUALLY     Complot

ANY
PLOTTER.
Complot

Complot

FOR SPECIAL
CONSIDERATIONS SEE THE SECTIONS BELOW ON,
Complot

(1) COMPUTER
DEPENDENT CODING
Complot

(2)
PLOTTER/GRAPHICS TERMINAL INTERFACE
Complot

Complot

GRAPHICS
INTERFACE
Complot

------------------------------------------------------------------
Complot

THIS PROGRAM
USES A SIMPLE CALCOMP LIKE GRAPHICS INTERFACE WHICH   Complot

REQUIRES ONLY 3
SUBROUTINES...PLOTS, PLOT AND PEN (DESCRIBED IN    Complot

DETAIL BELOW).
ALL CHARACTERS AND SYMBOLS ARE DRAWN USING TABLES   Complot

OF PEN STROKES
(SUPPLIED WITH THIS PROGRAM). USING THIS METHOD     Complot

THE PROGRAM
SHOULD BE SIMPLE TO INTERFACE TO VIRTUALLY ANY PLOTTER Complot

OR GRAPHICS
TERMINAL AND THE APPEARANCE AND LAYOUT OF THE PLOTS    Complot

SHOULD BE
INDEPENDENT OF WHICH PLOTTER IS USED.
Complot

Complot

ON WHAT PLOTTERS
WILL THE PROGRAM RUN
Complot

------------------------------------------------------------------
Complot

THE PLOTTER MAY
USE UNITS OF INCHES, CENTIMETERS, MILLIMETERS,     Complot

VIRTUALLY
ANYTHING. INTERNALLY THE PROGRAM WILL DEFINE PLOTS IN    Complot

APPROXIMATELY A4
OR 8-1/2 BY 11 INCH FORMAT. AS PART OF THE
Complot

INPUT THE USER
DEFINES THE ACTUAL SIZE OF THE PLOT IN THE UNITS    Complot

(I.E., INCHES,
CENTIMETERS, MILLIMETERS, WHATEVER) OF THE REAL     Complot

PLOT. THE PLOT
IS TRANSFORMED TO THE SIZE OF THE LOCAL PLOTTER     Complot

AND OUTPUT.
USING THIS CONVENTION THIS PROGRAM SHOULD BE EASY      Complot

TO INTERFACE TO
VIRTUALLY ANY PLOTTER OR GRAPHICS TERMINAL.
Complot

Complot

PROGRAM
IDENTIFICATION
Complot

----------------------
Complot

AS DISTRIBUTED
THE FIRST FRAME OF PLOTTED OUTPUT WILL DOCUMENT     Complot

THE PROGRAM
NAME, VERSION AND INSTALLATION. THIS INFORMATION IS    Complot

STORED AS DATA
IN THE ARRAY VERSES NEAR THE BEGINNING OF           Complot

SUBROUTINE
FRAME1. IF YOU WISH TO CUSTOMIZE THE OUTPUT TO IDENTIFY Complot

YOUR
INSTALLATION CHANGE THE LAST TWO LINES OF THE ARRAY (VERSES). Complot

Complot

ENDF/B
FORMAT
Complot

-------------
Complot

THIS PROGRAM
ONLY USES THE ENDF/B BCD OR CARD IMAGE FORMAT (AS     Complot

OPPOSED TO THE
BINARY FORMAT) AND CAN HANDLE DATA IN ANY VERSION   Complot

OF THE ENDF/B
FORMAT (I.E., ENDF/B-I, II,III, IV, V OR VI FORMAT). Complot

Complot

BOTH SETS OF
EVALUATED DATA MUST BE IN THE ENDF/B FORMAT. ONLY     Complot

SECTIONS OF FILE
2 (RESONANCE PARAMETERS) AND FILES 3, 23 AND 27   Complot

(TABULATED DATA)
WILL BE READ AND ALL OTHER SECTIONS WILL BE       Complot

SKIPPED. IN FILE
2 THE ONLY IMPORTANT INFORMATION IS THE ENERGY    Complot

LIMITS OF THE
RESOLVED AND UNRESOLVED RESONANCE REGION WHICH IS    Complot

LOCATED IN THE
SAME FIELDS IN ALL VERSIONS OF THE ENDF/B FORMAT.   Complot

SIMILARLY THE
FORMAT OF FILES 3, 23 AND 27 IS THE SAME IN ALL      Complot

VERSIONS OF
ENDF/B. THEREFORE THIS PROGRAM CAN BE USED WITH DATA   Complot

IN ANY ENDF/B
FORMAT (I.E. ENDF/B-I, II, III, IV, V OR VI).
Complot

Complot

CROSS SECTION
INTERPOLATION
Complot

---------------------------
Complot

CROSS SECTIONS
MUST BE IN EITHER HISTOGRAM (I.E., INTERPOLATION    Complot

LAW 1) OR
LINEARLY INTERPOLABLE (I.E. INTERPOLATION LAW 2) FORM.   Complot

IF THEY ARE NOT
A WARNING MESSAGE WILL BE PRINTED AND EXECUTION    Complot

WILL BE
TERMINATED. SEE INSTRUCTIONS BELOW ON HOW TO CONVERT       Complot

DATA TO
HISTOGRAM OR LINEARLY INTERPOLABLE FORM.
Complot

Complot

REACTION
INDEX
Complot

--------------
Complot

THIS PROGRAM
DOES NOT USE THE REACTION INDEX WHICH IS GIVEN IN     Complot

SECTION MF=1,
MT=451 OF EACH EVALUATION.
Complot

Complot

SECTION
SIZE
Complot

------------
Complot

SINCE THIS
PROGRAM USES A LOGICAL PAGING SYSTEM THERE IS NO LIMIT  Complot

TO THE NUMBER OF
POINTS IN ANY SECTION, E.G., THE TOTAL CROSS      Complot

SECTION MAY BE
REPRESENTED BY 200,000 DATA POINTS.
Complot

Complot

DATA
SELECTION
Complot

--------------
Complot

THE USER MAY
SPECIFYING THE DATA TO BE COMPARED BY INPUTTING UP    Complot

TO 100
MAT/MT/ENERGY OR ZA/MT/ENERGY RANGES. IF THE UPPER LIMIT    Complot

OF THE MAT OR ZA
RANGE IS LESS THAN THE LOWER LIMIT IT WILL BE SET Complot

EQUAL TO THE
LOWER LIMIT (I.E. THIS INDICATE ONLY COMPARE ONE      Complot

MAT OR ZA). IF
THE UPPER LIMIT IS STILL ZERO IT WILL BE SET TO     Complot

9999 (NO LIMIT).
IF THE UPPER MF OR MT LIMIT IS ZERO IT WILL BE    Complot

SET TO 99 OR
999, RESPECTIVELY (NO LIMIT). IF THE UPPER ENERGY     Complot

LIMIT IS ZERO IT
WILL BE SET TO A LARGE NUMBER (NO LIMIT).
Complot

Complot

THE LIST OF
RANGES MUST BE TERMINATED BY A BLANK LINE (I.E. ZERO   Complot

LOWER AND UPPER
MAT/MF/MT OR ZA/MF/MT LIMITS).
Complot

Complot

IF THE FIRST
RANGE LINE IS BLANK THIS LINE WILL TERMINATE THE      Complot

LIST OF REQUESTS
(I.E. A SECOND BLANK LINE NEED NOT BE INPUT)      Complot

AND ALL
PHYSICALLY COMPARABLE DATA WILL BE PLOTTED.
Complot

Complot

WHICH REACTIONS WILL BE
PLOTTED
Complot

-------------------------------
Complot

THOSE REACTIONS
WITH THE SAME (ZA, MF, MT) WILL BE COMPARED, BUT   Complot

ONLY THOSE DATA
WHICH DIFFER BY A USER SPECIFIED ALLOWABLE
Complot

DIFFERENCE WILL
BE PLOTTED. IN ORDER TO FORCE ALL COMPARABLE       Complot

REACTIONS TO BE
PLOTTED THE USER NEED ONLY SPECIFY AN ALLOWABLE    Complot

DIFFERENCE OF ZERO.
Complot

Complot

EQUIVALENT
REACTIONS
Complot

--------------------                                               Complot

IN ORDER TO
COMPARE REACTIONS WHICH HAVE DIFFERENT ZA, MF OR MT    Complot

THE USER IS
ALLOWED TO SPECIFY AN EQUIVALENCE LIST OF UP TO
Complot

100 (ZA,MF,MT)
COMBINATIONS ON THE MASTER FILE WHICH ARE TO BE     Complot

EQUATED TO
DIFFERENT (ZA,MF,MT) ON THE SECOND FILE. THIS OPTION    Complot

MAY BE USED TO
COMPARE SIMILAR REACTIONS FROM DIFFERENT MATERIALS  Complot

(E.G. IRON AND
NICKEL INELASTIC SCATTERING) OR DIFFERENT REACTIONS Complot

FROM THE SAME OR
DIFFERENT MATERIALS (E.G. U-235 CAPTURE AND       Complot

FISSION - IN
WHICH CASE THE RATIO WILL BE THE CAPTURE TO FISSION   Complot

RATIO) OR THE
SAME REACTION IN DIFFERENT VERSIONS OF THE ENDF/B    Complot

FORMAT WHICH MAY
BE ASSIGNED DIFFERENT MT NUMBERS, E.G., THE       Complot

PHOTOELECTRIC
CROSS SECTION IS MT=602 IN ENDF/B-V AND EARLIER      Complot

VERSIONS OF
ENDF/B, BUT IS MT=522 IN ENDF/B-VI.
Complot

Complot

IN THESE
EQUIVALENCE LISTS A ZERO FIELD IMPLIES ALL. FOR EXAMPLE,  Complot

TO EQUATE MT=522
FROM ONE FILE TO MT=602 ON THE OTHER, FOR ALL     Complot

MATERIALS, ONE
NEED ONLY SPECIFY ZA=0, MF=23, MT=522 EQUIVALENT    Complot

TO ZA=0, MF=23
AND MT=602.
Complot

Complot

PLOT
FORMATS
Complot

------------
Complot

THE TWO CROSS
SECTIONS ARE CONSIDERED TO BE A STANDARD (THE FIRST  Complot

CROSS SECTION)
AND A CROSS SECTION TO BE COMPARED TO THE STANDARD  Complot

(THE SECOND
CROSS SECTION). THE OUTPUT FROM THIS PROGRAM IS A      Complot

SERIES OF PLOTS.
EACH PLOT WILL CONTAIN THE STANDARD CROSS SECTION Complot

AND IN ADDITION
THE USER MAY SPECIFY THAT EACH PLOT ALSO CONTAIN   Complot

THE SECOND CROSS
SECTION AND/OR THE RATIO OF THE SECOND CROSS      Complot

SECTION TO THE
FIRST CROSS SECTION.
Complot

Complot

THE USER MAY
SELECT ONE OF THE FOLLOWING FIVE PLOT FORMATS (THE    Complot

NUMBER PRECEDING
THE OPTION IS THE VALUE OF THE PLOT MODE SELECTOR Complot

THAT THE USER
SHOULD SPECIFY AS INPUT ON THE FIRST LINE).
Complot

Complot

(0) THE STANDARD
CROSS SECTION (I.E. FIRST EVALUATION) AND THE     Complot

RATIO OF THE SECOND EVALUATION TO THE FIRST EVALUATION. THE    Complot

DATA WILL BE PRESENETED AS TWO SUB-PLOTS PER PLOT WITH THE     Complot

STANDARD CROSS SECTION IN THE UPPER HALF OF THE PLOT AND THE   Complot

RATIO IN THE LOWER HALF OF THE PLOT.
Complot

Complot

(1) THE STANDARD
CROSS SECTION (I.E. FIRST EVALUATION) AND THE     Complot

SECOND EVALUATION. THE DATA WILL BE PRESENTED AS TWO SUB-PLOTS Complot

PER PLOT WITH THE STANDARD CROSS SECTION ON THE UPPER HALF     Complot

OF THE PLOT AND THE SECOND CROSS SECTION IN THE LOWER HALF OF  Complot

THE PLOT.
Complot

Complot

(2) THE STANDARD
CROSS SECTION (I.E. FIRST EVALUATION) AND THE     Complot

SECOND EVALUATION. THE DATA WILL BE PRESENTED AS ONE PLOT      Complot

CONTAINING BOTH THE STANDARD AND SECOND CROSS SECTION. THE     Complot

STANDARD CROSS SECTION WILL BE PRESENTED AS A SOLID LINE AND   Complot

THE SECOND CROSS SECTION WILL BE PRESENTED AS A DASHED LINE.   Complot

Complot

(3) THE STANDARD
CROSS SECTION, SECOND CROSS SECTION AND RATIO OF  Complot

THE SECOND CROSS SECTION TO THE FIRST CROSS SECTION. THE DATA  Complot

WILL BE PRESENTED AS THREE SUB-PLOTS PER PLOT WITH THE
Complot

STANDARD CROSS SECTION IN THE UPPER THIRD OF THE PLOT, THE     Complot

SECOND CROSS SECTION IN THE MIDDLE THIRD AND THE RATIO OF THE  Complot

TWO IN THE LOWER THIRD OF THE PLOT (RECOMMENDED OPTION).       Complot

Complot

(4) THE STANDARD
CROSS SECTION, SECOND CROSS SECTION AND RATIO OF  Complot

THE SECOND CROSS SECTION TO THE FIRST CROSS SECTION. THE DATA  Complot

WILL BE PRESENTED AS TWO SUB-PLOTS PER PLOT WITH THE STANDARD  Complot

AND SECOND CROSS SECTION ON THE SAME SUB-PLOT IN THE UPPER     Complot

TWO THIRDS OF THE PLOT AND THE RATIO OF THE TWO IN THE LOWER   Complot

THIRD OF THE PLOT. THE STANDARD CROSS SECTION WILL BE
Complot

PRESENTED AS A SOLID LINE AND THE SECOND CROSS SECTION WILL BE Complot

PRESENTED AS A DASHED LINE.
Complot

Complot

ADDITIONAL PLOT
FEATURES
Complot

------------------------
Complot

IN ADDITION TO
THE CROSS SECTIONS AND/OR RATIO THE FOLLOWING       Complot

INFORMATIONS
WILL BE INCLUDED ON EACH PLOT.
Complot

Complot

(1) AN IDENTIFICATION
FOR EACH SET OF CROSS SECTIONS (UP TO 30     Complot

CHARACTERS FOR EACH SET).
Complot

Complot

(2) THE MAXIMUM
NEGATIVE AND POSITIVE PER-CENT DIFFERENCE BETWEEN  Complot

THE TWO CROSS SECTIONS.
Complot

Complot

(3) ARROWS
INDICATING THE ENERGY AT WHICH THE MAXIMUM DIFFERENCES  Complot

(MINIMUM AND MAXIMUM RATIO) OCCUR.
Complot

Complot

(4) THE ENERGY
LIMITS OF THE RESOLVED AND UNRESOLVED RESONANCE     Complot

REGION (IF THEY FALL WITHIN THE ENERGY LIMITS OF THE PLOT).    Complot

Complot

RATIO DATA
Complot

----------
Complot

IF RATIO OUTPUT
IS REQUESTED THE RATIO WILL BE DEFINED AT EACH     Complot

ENERGY THAT
APPEARS IN EITHER EVALUATION. BETWEEN THESE ENERGIES   Complot

THE RATIO WILL
BE PLOTTED ASSUMING LINEAR DEPENDENCE BETWEEN       Complot

TABULATED
VALUES. FOR HISTOGRAM OR LINEARLY INTERPOLABLE CROSS     Complot

SECTIONS THIS REPRESENTATION WILL POINT
OUT ALL EXTREMA OF THE
Complot

RATIO, BUT NOT
NECESSARILY THE ENERGY DEPENDENCE BETWEEN TABULATED Complot

VALUES.
Complot

Complot

IF THE EVALUATED DATA
IS NOT IN EITHER HISTOGRAM OR LINRARLY       Complot

INTERPOLABLE
FORM THE RATIO MAY NOT EVEN FIND ALL EXTREMA. FOR     Complot

EXAMPLE, IF ONE
EVALUATION IS LINEARLY INTERPOLABLE AND THE
Complot

OTHER NON-LINEAR,
BUT BOTH AGREE AT ALL TABULATED ENERGIES THE     Complot

RATIO WILL
APPEAR TO BE EQUAL TO UNITY AT ALL ENERGIES, BUT IN     Complot

FACT THE CROSS
SECTION BETWEEN TABULATED ENERGIES MAY BE QUITE     Complot

DIFFERENT USING
LINEAR VS. NON-LINEAR INTERPOLATION. FOR THIS      Complot

REASON ONLY
LINEARLY INTERPOLABLE OR HISTOGRAM DATA IS ALLOWED     Complot

AS INPUT TO THIS
PROGRAM.
Complot

Complot

LINEAR
INTERPOLABLE
Complot

-------------------
Complot

ALL CROSS
SECTIONS MAY BE CONVERTED TO LINEARLY INTERPOLABLE FORM  Complot

BE USING PROGRAM
LINEAR (UCRL-50400, VOL. 17, PART A).
Complot

Complot

HISTOGRAM
Complot

---------
Complot

ALL LINEARLY
INTERPOLABLE CROSS SECTION MAY BE CONVERTED TO
Complot

HISTOGRAM (I.E.
MULTIGROUP) FORM BY USING PROGRAM GROUPIE          Complot

(UCRL-50400,
VOL. 17, PART D).
Complot

Complot

INPUT UNITS
Complot

-----------
Complot

UNIT  DESCRIPTION
Complot

----  -----------
Complot

2   INPUT LINE
Complot

9   MT DEFINITIONS.
Complot

10   FIRST ENDF/B FORMATTED EVALUATION
(STANDARD).
Complot

11   SECOND ENDF/B FORMATTED
EVALUATION.
Complot

17   SOFTWARE CHARACTERS.
Complot

18   SOFTWARE SYMBOLS AND LINE
TYPES
Complot

Complot

OUTPUT
UNITS
Complot

------------
Complot

UNIT  DESCRIPTION
Complot

----  -----------
Complot

3   NORMAL OUTPUT
REPORT.
Complot

16   PLOTTER UNIT
Complot

Complot

SCRATCH
UNITS
Complot

-------------
Complot

UNIT  DESCRIPTION
Complot

----  -----------
Complot

12   SCRATCH UNIT FOR FIRST
EVALUATION
Complot

13   SCRATCH UNIT FOR SECOND
EVALUATION
Complot

14   SCRATCH UNIT FOR RATIO (ONLY USED
IF RATIOS REQUESTED).      Complot

Complot

OPTIONAL
STANDARD FILE NAMES (SEE SUBROUTINE FILIO1 AND FILIO2)    Complot

---------------------------------------------------------------    Complot

UNIT  FILE NAME
Complot

----  ----------
Complot

2   COMPLOT.INP
Complot

3   COMPLOT.LST
Complot

9   MT.DAT
Complot

10   ENDFB.IN1    (OR AS READ FROM INPUT)
Complot

11   ENDFB.IN2    (OR AS READ FROM INPUT)
Complot

12-14  (SCRATCH)
Complot

15   PLOT.CHR
Complot

16   (PLOTTER UNIT...USUALLY A
DUMMY)
Complot

Complot

INPUT
PARAMETERS
Complot

------------------------------------------------------------------
Complot

LINE  COLUMNS  FORMAT  DESCRIPTION
Complot

----  -------  ------  -----------
Complot

1
1-11    E11.4  LOWER X LIMIT OF PLOTTER
Complot

12-22    E11.4  UPPER X LIMIT OF PLOTTER
Complot

23-33    E11.4  LOWER Y LIMIT OF PLOTTER
Complot

34-44    E11.4  UPPER Y LIMIT OF PLOTTER
Complot

45-55
I11   NUMBER OF PLOTS
PER FRAME IN X DIRECTION
Complot

56-66
I11   NUMBER OF PLOTS
PER FRAME IN Y DIRECTION
Complot

67-70
F4.1  CHARACTER SIZE
MULTIPLIER
Complot

= 0 TO 1    - NORMAL CHARACTER SIZE         Complot

= OTHERWISE - CHARACTERS SCALED BY THIS     Complot

FACTOR
Complot

Complot

PLOT ORIENTATION IS BASED ON THE UPPER X    Complot

LIMIT
Complot

= .GT.0 - X HORIZONTAL/Y VERTICAL
Complot

=
.LT.0 - Y HORIZONTAL/X VERTICAL
Complot

AFTER TESTING THE UPPER X LIMIT WILL BE     Complot

SET TO ITS ABSOLUTE VALUE.
Complot

2     1-72     A60   FILENAME FOR FIRST ENDF/B DATA
FILE
Complot

(LEAVE BLANK FOR ENDFB.IN1)
Complot

3
1-72
A60   FILENAME FOR
SECOND ENDF/B DATA FILE
Complot

(LEAVE BLANK FOR
ENDFB.IN2)
Complot

4
1-11
I11   RETRIEVAL MODE
(0=MAT, 1=ZA)
Complot

12-22
I11   GRID (SPEED)
OPTION.
Complot

= 0 - TICK MARKS ON BORDER
Complot

= 1 - SOLID AT COARSE INTERVALS
Complot

= 2 - DASHED AT COARSE INTERVALS
Complot

= 3 - SOLID AT COARSE AND FINE INTERVALS    Complot

= 4 - DASHED AT COARSE AND FINE INTERVALS   Complot

= 5 - SOLID COARSE/DASHED FINE INTERVALS    Complot

23-33
I11   SHOULD BORDER BE
PLOTTED AROUND EACH PLOT
Complot

= 0 - NO
Complot

= 1 - YES
Complot

34-44
I11   LINE THICKNESS
Complot

= 0 TO  5 - LINES AND
CHARACTERS
Complot

=-1 TO -5 - ONLY LINES
Complot

45-55
I11   OUTPUT MODE
Complot

=-1 - ONLY COMPARISON LISTING. NO PLOTS.    Complot

= 0 - CROSS SECTION OVER RATIO.
Complot

= 1 - CROSS SECTION OVER CROSS SECTION.     Complot

=
2 - TWO CROSS SECTIONS ON SAME PLOT.      Complot

= 3 - CROSS SECTION OVER CROSS SECTION OVER Complot

RATIO.
Complot

=
4 - TWO CROSS SECTIONS ON SAME PLOT OVER
Complot

RATIO.
Complot

56-66
I11   STARTING PLOT
NUMBER
Complot

= 0     - DO NOT NUMBER
PLOTS
Complot

= .GT.0 - NUMBER PLOTS IN LOWER LEFT HAND   Complot

CORNER STARTING WITH INPUT NUMBER Complot

67-70
I41   BACKGROUND
COLOR
Complot

= 0
= BLACK
Complot

= OTHERWISE = WHITE
Complot

5    1-11    E11.4  ALLOWABLE FRACTIONAL DIFFERENCE. USED
WHEN  Complot

PLOTTING RATIOS. ANY REACTION WHERE THE     Complot

TWO EVALUATIONS DIFFER BY MORE THAN THE     Complot

ALLOWABLE DIFFERENCE WILL BE PLOTTED. IF    Complot

ZERO IS INPUT THE STANDARD ALLOWABLE
Complot

DIFFERENCE OF 0.001 (0.1 PER-CENT) WILL BE  Complot

USED.
Complot

12-22    E11.4  MAXIMUM ALLOWABLE RATIO. IF RATIOS
ARE      Complot

PLOTTED THEY WILL BE IN THE RANGE RATMAX    Complot

TO 1/RATMAX. IF 0.0 IS INPUT THERE WILL     Complot

BE NO LIMIT ON THE RANGE OF THE RATIOS.     Complot

THIS OPTION MAY BE USED TO IGNORE LARGE     Complot

DIFFERENCES OVER VERY NARROW
ENERGY RANGES  Complot

(WHICH
MAY BE UNIMPORTANT) AND ALLOW ONE    Complot

TO SEE IMPORTANT, BUT SMALLER DIFFERENCES,  Complot

OVER EXTENDED ENERGY
RANGES.
Complot

6     1-40     40A1  IDENTIFICATION FOR UPPER
EVALUATIONS
Complot

7
1-40
40A1  IDENTIFICATION FOR
LOWER EVALUATIONS
Complot

(IDENTIFICATIONS SHOULD BE LEFT ADJUSTED    Complot

TO START IN
COLUMN 1).
Complot

8-N     1- 6      I6   LOWER MAT OR ZA LIMIT (SEE
SELECTION MODE,  Complot

INPUT LINE 1, COLUMNS 1-11).
Complot

7- 8
I2   LOWER MF LIMIT
Complot

9-11
I3   LOWER
MT LIMIT
Complot

12-22    E11.4  LOWER ENERGY LIMIT
Complot

23-28
I6   UPPER MAT OR ZA
LIMIT (SEE SELECTION MODE,  Complot

INPUT LINE 1, COLUMNS 1-11).
Complot

29-30
I2   UPPER MF LIMIT
Complot

31-33
I3   UPPER
MT LIMIT
Complot

34-44    E11.4  UPPER ENERGY LIMIT
Complot

45-55
I11   IDENTIFY EVALUATED
DATA POINTS OPTION.      Complot

= 0 - DO NOT IDENTIFY DATA POINTS.
Complot

= 1 - IDENTIFY DATA POINTS (BY DRAWING A    Complot

SMALL BOX AROUND EACH POINT).
Complot

56-66
I11   INTERACTIVE INPUT
FLAG
Complot

= 0 - NO INTERACTIVE INPUT ALLOWED
Complot

= 1 - INTERACTIVE INPUT ALLOWED
Complot

*SETTING THIS OPTION =1 WILL TURN ON THE     Complot

MOUSE AFTER EACH PLOT AND ALLOW YOU TO      Complot

INTERACTIVELY SPECIFY PLOT LIMITS.
Complot

*IF YOU DO NOT WISH TO INTERACT WITH A PLOT  Complot

OR
IF YOU HAVE NO INTERACTIVE CAPABILITY    Complot

THIS OPTION SHOULD BE SET = 0.
Complot

Complot

*WARNING...DATA
POINTS IDENTIFIED OPTION IS  Complot

NOT RECOMMENDED FOR PLOTS CONTAINING MANY   Complot

(I.E. THOUSANDS) OF DATA POINTS SINCE IT    Complot

WILL MERELY INCREASE THE RUNNING TIME OF    Complot

THE PROGRAM AND STILL NOT ALLOW ONE TO      Complot

ACCURATELY SEE DATA POINTS.
Complot

Complot

*UP TO 100 MAT OR ZA RANGES ARE ALLOWED.     Complot

THE LIST IS TERMINATED BY A BLANK LINE.     Complot

IF THE UPPER LIMIT IS LESS THAN THE LOWER   Complot

LIMIT IT WILL BE SET EQUAL TO THE LOWER     Complot

LIMIT. IF THE FIRST RANGE LINE IS BLANK     Complot

ALL DATA WILL BE RETRIEVED. IF THE UPPER    Complot

MT LIMIT IS ZERO IT WILL BE SET EQUAL TO    Complot

999 (NO LIMIT). IF THE UPPER ENERGY LIMIT   Complot

IS ZERO IT WILL BE INTREPRETED TO MEAN NO   Complot

LIMIT. IF THE FIRST RANGE LINE SPECIFIES    Complot

ZERO LOWER AND UPPER MAT OR ZA RANGE IT     Complot

WILL TERMINATE THE LIST BE RANGE LINES      Complot

(A SECOND BLANK LINE NEED NOT BE INPUT)     Complot

AND THE ENTIRE
RANGE OF MATS WILL
BE
Complot

COMPARED FOR THE SPECIFIED MT AND ENERGY    Complot

RANGES.
Complot

Complot

N+1-M
EQUIVALENCES
Complot

1- 6      I6   MASTER ZA.
Complot

7- 8
I2   MASTER MF.
Complot

9-11
I3   MASTER MT.
Complot

12-17
I6   EQUIVALENT ZA FROM
SECOND FILE.
Complot

18-19
I2   EQUIVALENT MF FROM
SECOND FILE.
Complot

20-22
I3   EQUIVALENT MT FROM
SECOND FILE.
Complot

23-33    E11.4  MULTIPLICATION FACTOR. ANY EQUATED
ZA,MF,   Complot

MT DATA WILL BE MULTIPLIED BY THIS FACTOR.  Complot

*THIS OPTION MAY BE USED TO RE-NORMALIZE     Complot

THE SECOND CROSS SECTION OR IF COMPARING    Complot

ONE CONSTITUENT OF A MIXTURE TO THE MIXED   Complot

CROSS SECTION THIS MAY BE USED TO CONVERT   Complot

THE SECOND CROSS SECTION TO BARNS PER MIXED Complot

ATOM BY USING A MULTIPLICATION FACTOR WHICH Complot

IS EQUAL TO THE NUMBER OF ATOMS OF THE ONE  Complot

CONSTITUENT PER ATOM OF THE MIXTURE.        Complot

= 0.0 - ON INPUT WILL BE INTERPRETED AS 1.0 Complot

(WITH THIS CONVENTION THE USER NEED ONLY    Complot

INPUT MULTIPLICATION FACTORS IF THEY ARE    Complot

NOT 1.0).
Complot

*UP TO 100 MAT OR ZA EQUIVALENCES ARE
Complot

ALLOWED.
Complot

*THE
LIST IS TERMINATED BY A BLANK LINE.     Complot

*A ZERO INPUT FIELD IMPLIES ALL. TO EQUATE   Complot

A GIVEN MT NUMBER TO ANOTHER MT NUMBER YOU  Complot

NEED
MERELY SPECIFY ZA=0 ON INPUT.
Complot

*NOTE, IN ALL CASES THE TITLE AT TOP OF PLOT Complot

WILL ONLY INDENTIFY MASTER (ZA,MF,MT). THE  Complot

USER INPUT TITLES MUST
BE USED TO IDENTIFY  Complot

THE SECOND REACTION (SEE, EXAMPLE INPUT 4   Complot

BELOW).
Complot

Complot

Complot

EXAMPLE
DEFINITION OF PLOTTER
Complot

-----------------------------
Complot

THE FIRST INPUT
LINE DEFINES THE DIMENSIONS OF THE PLOTTER BEING   Complot

USED IN ANY
UNITS (INCHES, CENTIMETERS, MILLIMETERS, ANYTHING)     Complot

WHICH APPLY TO
THE PLOTTER. IN ADDITION THE FIRST LINE DEFINES     Complot

HOW MANY PLOTS
SHOULD APPEAR ON EACH FRAME. THE PLOTTING AREA      Complot

DEFINED ON THE
FIRST INPUT LINE MAY BE SUBDIVIDED INTO ANY NUMBER  Complot

OF PLOTS IN THE
X AND Y DIRECTION. FOR EXAMPLE, TO PRODUCE A       Complot

SERIES OF FRAMES
EACH CONTAINING 3 PLOTS IN THE X DIRECTION AND    Complot

2 PLOTS IN THE Y
DIRECTION (6 PLOTS PER FRAME) COLUMN 45-55 OF     Complot

THE FIRST INPUT
LINE SHOULD BE 3 AND COLUMNS 56-66 SHOULD BE 2.    Complot

Complot

IF THE LOCAL
PLOTTER USES DIMENSIONS OF INCHES IN ORDER TO OBTAIN  Complot

10 X 10 INCH
FRAMES WITH 3 X 2 PLOTS PER FRAME THE FIRST INPUT     Complot

LINE SHOULD BE,
Complot

Complot

0.0
10.0
0.0
10.0
3
2
Complot

Complot

IF THE LOCAL
PLOTTER USES DIMENSION OF MILLIMETERS THE SAME
Complot

PHYSICAL SIZE
PLOT MAY BE OBTAINED IF THE FIRST INPUT LINE IS,     Complot

Complot

0.0
254.0
0.0    254.0
3
2
Complot

Complot

FOR SIMPLICITY
THE FOLLOWING EXAMPLE INPUTS WILL NOT DISCUSS THE   Complot

PHYSICAL
DIMENSIONS OF THE PLOTTER AND THE FIRST INPUT LINE WILL   Complot

IN ALL CASES
INDICATE 10 X 10 INCH PLOTS WITH ONLY 1 PLOT PER      Complot

FRAME.
Complot

Complot

IN THE FOLLOWING
EXAMPLES IN ALL CASES THESE OPTIONS WILL BE USED, Complot

1) DASHED
GRID
- COLUMNS 12-22 OF SECOND INPUT LINE =  1     Complot

2) NO
BORDER
- COLUMNS 23-33 OF SECOND INPUT LINE =  0     Complot

3) LINE
THICKNESS    - COLUMNS
34-44 OF SECOND INPUT LINE = -2     Complot

4) OUTPUT
MODE
- COLUMNS 45-55 OF SECOND INPUT LINE =  3     Complot

5) FIRST PLOT
NUMBER - COLUMNS 56-66 OF SECOND INPUT LINE =  1     Complot

Complot

EXAMPLE INPUT
1
Complot

---------------
Complot

RETRIEVE MATS
1023, 1056 AND 1065 THROUGH 1072, MT = 1 AND 2       Complot

(TOTAL AND
ELASTIC) FROM THE FIRST INPUT FILE AND COMPARE TO       Complot

ANY SECTION FROM THE SECOND
FILE THAT HAS THE SAME ZA/MF/MT. ONLY
Complot

COMPARE DATA
OVER THE ENERGY RANGE 0.1 EV TO 1 KEV. IDENTIFY       Complot

THE TWO SETS OF
DATA AS ENDF/B-V AND ENDF/B-IV, RESPECTIVELY.      Complot

ONLY PLOT THOSE
REACTIONS WHICH DIFFER AT ONE OR MORE ENERGIES     Complot

BY MORE THAN 1
PER-CENT (NOTE, 1 PER-CENT = 0.01 AS INPUT
Complot

FRACTION). NO
EQUIVALENT REACTIONS ARE SPECIFIED. FILERNAMES       Complot

ARE STANDARD
(THSE CAN EITHER BE EXPLICITLY INCLUDED, OR SIMPLY    Complot

LEFT
BLANK).
Complot

Complot

THE FOLLOWING 12
INPUT LINES ARE REQUIRED.
Complot

Complot

0.0
10.0
0.0
10.0
3
2
Complot

ENDFB.IN1
Complot

ENDFB.IN2
Complot

0
1
0
-2
3
1
Complot

0.01
0.0
Complot

ENDF/B-V DATA (STANDARD)
Complot

ENDF/B-IV DATA
Complot

1023 3  1 0.1
3  2 1000.0
0
Complot

1056 3  1 0.1
3  2 1000.0
0
Complot

1065 3  1 0.1       1072
3  2 1000.0
0
Complot

(TERMINATES REQUEST LIST)        Complot

(TERMINATES EQUIVALENCE LIST)    Complot

Complot

EXAMPLE INPUT
2
Complot

---------------
Complot

TO USE ALL OF
THE SAME OPTIONS AS SPECIFIED IN EXAMPLE INPUT 1,    Complot

EXCEPT TO
RETRIEVE U-235, U-238 AND PU-239 THROUGH PU-242 THE      Complot

FOLLOWING 12
INPUT LINES ARE REQUIRED.
Complot

Complot

0.0
10.0
0.0
10.0
3
2
Complot

ENDFB.IN1
Complot

ENDFB.IN2
Complot

1
1
0
-2
3
1
Complot

0.01
0.0                                                  Complot

ENDF/B-V DATA (STANDARD)
Complot

ENDF/B-IV DATA
Complot

92235
3  1 0.1
3  2 1000.0                0
Complot

92238
3  1 0.1
3  2 1000.0
0
Complot

94239
3  1 0.1      94242 3  2 1000.0
0
Complot

(TERMINATES REQUEST LIST)
Complot

(TERMINATES EQUIVALENCE LIST)    Complot

EXAMPLE INPUT
3
Complot

---------------
Complot

TO USE ALL OF
THE SAME OPTIONS AS SPECIFIED IN EXAMPLE INPUT 1,    Complot

EXCEPT TO
RETRIEVE AND COMPARE ALL MATS THE FOLLOWING 10 INPUT     Complot

LINES ARE
REQUIRED.
Complot

Complot

0.0
10.0
0.0
10.0
3
2
Complot

ENDFB.IN1
Complot

ENDFB.IN2
Complot

0
1
0
-2
3
1
Complot

0.01
0.0
Complot

ENDF/B-V DATA (STANDARD)
Complot

ENDF/B-IV DATA
Complot

1 1  1 0.0       999999999
0.0
0
Complot

(TERMINATES
REQUEST LIST)
Complot

(TERMINATES EQUIVALENCE LIST)    Complot

NOTE, ZERO LOWER AND UPPER      Complot

MAT
LIMITS INDICATES NO LIMIT.  Complot

Complot

EXAMPLE INPUT
4
Complot

---------------
Complot

RETRIEVE U-235
AND EQUATE THE FISSION CROSS SECTION (MT=18) ON     Complot

THE MASTER FILE
TO CAPTURE (MT=102) ON THE SECOND FILE. PLOT       Complot

THE CAPTURE,
FISSION AND CAPTURE TO FISSION RATIO OVER THE ENERGY  Complot

RANGE 0.0253 EV
TO 1 KEV. THE FOLLOWING 11 INPUT LINES ARE
Complot

REQUIRED.
Complot

Complot

0.0
10.0
0.0
10.0
3
2
Complot

ENDFB.IN1
Complot

ENDFB.IN2
Complot

1
1
0
-2
3
1
Complot

0.01
0.0
Complot

FISSION
Complot

CAPTURE
Complot

92235
3 18 0.0253   92235 3 18
1000.0
0
Complot

(TERMINATES REQUEST LIST)
Complot

92235
3 18 92235 3102
(MULTIPLICATION OF 1.0 INFERRED) Complot

(TERMINATES EQUIVALENCE LIST)    Complot

Complot

EXAMPLE INPUT
5
Complot

---------------
Complot

IN DIFFERENT
VERSIONS OF THE ENDF/B FORMAT DIFFERENT MT NUMBERS    Complot

ARE ASSIGNED TO
THE SAME REACTION. FOR EXAMPLE, IN ENDF/B-V AND    Complot

EARLIER VERSIONS
OF ENDF/B THE PHOTOELECTRIC CROSS SECTION IS      Complot

MT=602, WHILE IN
ENDF/B-VI IT IS MT=522. IN ORDER TO COMPARE       Complot

ASSUMING THAT
THE MASTER IS ENDF/B-VI AND THE OTHER ENDF/B FILE    Complot

IS ENDF/B-V (OR
EARLIER) YOU MAY EQUATE MT=522 TO 602.
Complot

Complot

WHEN COMPARING
PHOTOELECTRIC CROSS SECTIONS WE EXPECT THERE TO BE  Complot

LARGE
DIFFERENCES NEAR EDGES, SINCE IT IS UNLIKELY THAT TWO
Complot

INDEPENDENT
EVALUATIONS USE EXACTLY THE SAME EDGE ENERGIES. FROM   Complot

A PRACTICAL
VIEWPOINT THESE DIFFERENCES ARE NOT IMPORTANT IF THEY  Complot

ONLY OCCUR OVER NARROW
ENERGY RANGES
NEAR ENERGIES. HOWEVER THESE
Complot

LARGE
DIFFERENCES MAY MAKE IT DIFFICULT TO SEE DIFFERENCES OVER    Complot

OTHER ENERGY RANGES,
WHICH MAY BE IMPORTANT. IN ORDER TO BE ABLE   Complot

TO SEE IMPORTANT
DIFFERENCES IN THE FOLLOWING COMPARISON WE WILL   Complot

CONSTRAIN THE
PLOTTED RATIO TO THE RANGE ABOUT 0.9 TO 1.1 IN       Complot

ORDER TO BE ABLE
TO SEE DIFFERENCES OF UP TO 10 PER-CENT. WE WILL  Complot

DO THIS BY
SPECIFYING A MAXIMUM RATIO OF 1.1, WHICH WILL IN TURN   Complot

DEFINE A MINIMUM
RATIO OF 1/1.1, OR ABOUT 0.9.
Complot

Complot

IN ORDER TO COMPARE THE PHOTOELECTRIC
CROSS SECTION FOR ALL
Complot

MATERIALS THE
FOLLOWING 11 INPUT LINES ARE REQUIRED.
Complot

Complot

0.0       10.0      0.0     10.0
3
2
Complot

ENDFB.IN1
Complot

ENDFB.IN2
Complot

0
1        0       -2
3
1
Complot

0.01
1.1
Complot

ENDF/B-VI
Complot

ENDF/B-V
Complot

023522
999923522
0
Complot

(TERMINATES REQUEST LIST)
Complot

023522     023602
(MULTIPLICATION OF 1.0 INFERRED) Complot

(TERMINATES EQUIVALENCE LIST)    Complot

Complot

EXAMPLE INPUT
6
Complot

---------------
Complot

THE SAME EXAMPLE
AS ABOVE, EXCEPT THAT DIFFERENT FILENAMES WILL    Complot

BE USED TO READ
THE DATA FROM A FILE TREE STRUCTURE. THE FOLLOWING Complot

11 INPUT LINES
ARE REQUIRED.
Complot

Complot

0.0
10.0
0.0
10.0
3
2
Complot

/Evaluated/ENDFB6/PHOTON.IN
Complot

/Evaluated/ENDFB5/PHOTON.IN
Complot

0
1
0
-2
3
1
Complot

0.01
1.1
Complot

ENDF/B-VI
Complot

ENDF/B-V
Complot

023522           999923522
0
Complot

(TERMINATES REQUEST LIST)
Complot

023522     023602
(MULTIPLICATION OF 1.0 INFERRED) Complot

(TERMINATES
EQUIVALENCE LIST)
Complot

Complot

EXAMPLE INPUT
7
Complot

---------------
Complot

THE OUTPUT FOR
ALL OF THE ABOVE EXAMPLES ARE ORIENTED WITH X       Complot

HORIZONTAL AND Y
VERTICAL. TO CHANGE THE ORIENTATION OF THE PLOTS  Complot

YOU NEED MERELY
SPECIFY A NEGATIVE UPPER X LIMIT OF THE SIZE OF    Complot

THE PLOTS ON THE
FIRST INPUT LINE.
Complot

Complot

THE FOLLOWING
EXAMPLE IS EXACTLY THE SAME AS THE ABOVE EXAMPLE,    Complot

EXCEPT THAT THE
ORIENTATION OF THE PLOTS HAS BEEN CHANGED. THE     Complot

FOLLOWING 11
INPUT LINES ARE REQUIRED.
Complot

Complot

0.0
-10.0
0.0
10.0
3
2
Complot

/Evaluated/ENDFB6/PHOTON.IN
Complot

/Evaluated/ENDFB5/PHOTON.IN
Complot

0
1
0
-2
3
1
Complot

0.01
1.1
Complot

ENDF/B-VI
Complot

ENDF/B-V
Complot

023522
999923522
0
Complot

(TERMINATES REQUEST LIST)
Complot

023522     023602
(MULTIPLICATION OF 1.0 INFERRED) Complot

(TERMINATES EQUIVALENCE LIST)    Complot

Complot

=====
PLOTTER/GRAPHICS TERMINAL INTERFACE ============================= Complot

Complot

NON-INTERACTIVE
Complot

------------------------------------------------------------------
Complot

THIS
PROGRAM USES A SIMPLE CALCOMP LIKE INTERFACE INVOLVING       Complot

ONLY 5
SUBROUTINES,
Complot

Complot

STARPLOT     -
INITIALIZE PLOTTER
Complot

NEXTPLOT     -
CLEAR SCREEN FOR NEXT PLOT
Complot

ENDPLOTS     -
TERMINATE PLOTTING
Complot

Complot

PLOT(X,Y,IPEN)        -
DRAW OR MOVE FROM LAST LOCATION TO (X,Y), Complot

END OF CURRENT PLOT OR END OF PLOTTING.   Complot

IPEN =   2 - DRAW
Complot

=   3 - MOVE
Complot

Complot

PEN(IPEN)
- SELECT COLOR.
Complot

IPEN- COLOR = 1 TO N (N = ANY POSITIVE INTEGER)
Complot

Complot

BOXCOLOR(X,Y,IFILL,IBORDER) - FILL A RECTANGLE WITH COLOR
Complot

X,Y
= DEFINE THE CORNERS OF THE BOX       Complot

IFILL
= COLOR TO FILL BOX WITH
Complot

IBORDER  = COLOR OF BORDER OF BOX
Complot

Complot

INTERACTIVE
Complot

------------------------------------------------------------------
Complot

THIS
PROGRAM INCLUDES AN INTERACTIVE INTERFACE FOR USE WITH A     Complot

MOUSE. THE
INTERFACE INVOLVES 2 SUBROUTINE,
Complot

Complot

INTERACT(MYACTION)
- WHETHER OR NOT INTERACTION       Complot

MYACTION
= 0 - NO (RETURNED BY INTERACT)    Complot

= 1 - YES (RETURNED BY INTERACT)   Complot

Complot

MOUSEY(IWAY,XI,YI,IWAY1,IWAY2) - READ POSITION OF MOUSE
Complot

IWAY    = 0 - NO INPUT
Complot

= 1 - LEFT BUTTON
Complot

= 2 - MIDDLE BUTTON
Complot

= 3 - RIGHT BUTTON                 Complot

= 4 - KEYBOARD INPUT
Complot

XI      =
X POSITION IN LOCAL UNITS
Complot

YI      =
Y POSITION IN LOCAL UNITS
Complot

IWAY1   = MINIMUM
ALLOWABLE IWAY
Complot

IWAY2   = MAXIMUM
ALLOWABLE IWAY
Complot

Complot

AS USED BY THIS
PROGRAM IWAY1   = 1
Complot

IWAY2   = 4
Complot

KEYBOARD INPUT
(IWAY=4) MEANS NO ZOOMED PLOT REQUESTED.
Complot

MOUSE INPUT
(IWAY=1 TO 3) MEANS A ZOOMED PLOT IS REQUESTED.
Complot

MOUSEY WILL BE
CALLED ONCE TO SEE IF A ZOOMED PLOT IS REQUESTED.   Complot

IF IT IS XI WILL
BE USED TO DEFINE ONE X (E.G., ENERGY) LIMIT OF   Complot

THE ZOOMED PLOT.
MOUSEY WILL THEN BE CALLED A SECOND TIME TO       Complot

DEFINE A SECOND
XI TO DEFINE THE OTHER X LIMIT OF THE ZOOMED       Complot

PLOT.
Complot

Complot

IF YOU DO NOT
WANT INTERACTION YOU SHOULD INCLUDE THE FOLLOWING    Complot

SUBROUTINES IN
YOUR GRAPHIC INTERFACE,
Complot

Complot

SUBROUTINE
INTERACT(MYACTION)
Complot

MYACTION=0
Complot

RETURN
Complot

END
Complot

SUBROUTINE
MOUSEY(IWAY,XI,YI,IWAY1,IWAY2)
Complot

IWAY=4
Complot

XI=0.0
Complot

YI=0.0
Complot

RETURN
Complot

END
Complot

Complot

ALTERNATIVE
INTERACTIVE
Complot

------------------------------------------------------------------
Complot

IF YOU DO NOT
HAVE A MOUSE BUT WOULD STILL LIKE TO INTERACTIVE     Complot

INPUT YOU CAN
REPLACE SUBROUTINE ACTION IN THIS PROGRAM.
Complot

Complot

AS DISTRIBUTED
SUBROUTINE ACTION USES A MOUSE TO DEFINE LOWER      Complot

AND UPPER ENERGY
(OR X) LIMITS WHICH ARE USED TO PRODUCE THE       Complot

NEXT PLOT. A
CALL TO ACTION IS OF THE FORM,
Complot

Complot

CALL
ACTION(KACTV,XACT1,XACT2)
Complot

Complot

KACTV   = 0 - NO
INTERACTIVE INPUT
Complot

= 1 - INTERACTIVE INPUT
Complot

XACT1   = LOWER ENERGY
LIMIT
Complot

XACT2   = UPPER ENERGY
LIMIT
Complot

Complot

IF THERE IS NO
INTERACTIVE INPUT THE PROGRAM WILL PROCEED TO THE   Complot

NEXT PLOT
REQUESTED BY NON-INTERACTIVE INPUT.
Complot

Complot

IF THERE IS
INTERACTIVE INPUT THE PROGRAM WILL USE XACT1 AND       Complot

XACT2 TO DEFINE
THE ENERGY LIMITS OF THE NEXT PLOT USING THE       Complot

SAME DATA AS
APPEARED ON THE LAST PLOT. AS WITH NON-INTERACTIVE    Complot

INPUT, IF YOU
SELECT AN ENERGY RANGE WHERE THE MAXIMUM DIFFERENCE  Complot

IS LESS THAN
THAT SPECIFIED BY INPUT NO PLOT WILL BE PRODUCED      Complot

AND THE CODE
WILL PROCEED TO THE NEXT PLOT REQUESTED BY
Complot

NON-INTERACTIVE
INPUT.
Complot

Complot

YOU CAN REPLACE
SUBROUTINE ACTION FOLLOWING THE ABOVE CONVENTIONS  Complot

TO ALLOW
INTERACTION VIA DIRECT READ OF X LIMITS, LIGHTPEN OR      Complot

WHATEVER FACILITIES YOU HAVE
AVAILABLE.
Complot

Complot

INTERFACING
Complot

------------------------------------------------------------------
Complot

IN ORDER TO
INTERFACE THIS PROGRAM FOR USE ON ANY PLOTTER WHICH    Complot

DOES NOT USE THE
ABOVE CONVENTIONS IT IS MERELY NECESSARY FOR THE  Complot

THE USER TO
WRITE 5 SUBROUTINES DESCRIBED ABOVE AND TO THEN CALL   Complot

THE LOCAL
EQUIVALENT ROUTINES.
Complot

Complot

COLOR PLOTS
Complot

------------------------------------------------------------------
Complot

TO SELECT
PLOTTING COLORS SUBROUTINE PEN (DESCRIBED ABOVE) IS USED Complot

TO SELECT ONE OF
THE AVAILABLE COLORS. WHEN RUNNING ON A MAINFRAME Complot

USING AN IBM
GRAPHICS TERMINAL OR ON AN IBM-PC USING A HEWLETT-    Complot

PACKARD PLOTTER
THE GRAPHICS INTERFACE (DESCRIBED ABOVE) WILL      Complot

PRODUCE COLOR
PLOTS.
Complot

Complot

BLACK AND WHITE
PLOTS
Complot

------------------------------------------------------------------
Complot

WHEN PRODUCING
BLACK AND WHITE HARDCOPY ON A MAINFRAME THE USER    Complot

SHOULD ADD A
DUMMY SUBROUTINE PEN TO THE END OF THE PROGRAM TO     Complot

IGNORE ATTEMPTS
TO CHANGE COLOR. ADD THE FOLLOWING SUBROUTINE,     Complot

Complot

SUBROUTINE
PEN(IPEN)
Complot

RETURN
Complot

END
Complot

Complot

CHARACTER
SET
Complot

------------------------------------------------------------------
Complot

THIS PROGRAM
USES COMPUTER AND PLOTTER DEVICE INDEPENDENT SOFTWARE Complot

CHARACTERS. THIS
PROGRAM COMES WITH A FILE THAT DEFINES THE PEN    Complot

STROKES REQUIRED
TO DRAW ALL CHARACTERS ON AN IBM KEYBOARD (UPPER  Complot

AND LOWER CASE
CHARACTERS, NUMBERS, ETC.) PLUS AN ALTERNATE SET OF Complot

ALL UPPER AND
LOWER CASE GREEK CHARACTERS AND ADDITIONAL SPECIAL   Complot

SYMBOLS.
Complot

Complot

THE SOFTWARE
CHARACTER TABLE CONTAINS X AND Y AND PEN POSITIONS TO Complot

DRAW EACH
CHARACTER. IF YOU WISH TO DRAW ANY ADDITIONAL CHARACTERS Complot

OR TO MODIFY THE
FONT OF THE EXISTING CHARACTERS YOU NEED ONLY     Complot

MODIFY THIS
TABLE.
Complot

Complot

CONTROL
CHARACTERS
Complot

------------------------------------------------------------------
Complot

IN THE SOFTWARE
CHARACTER TABLE ALL CHARACTERS TO BE PLOTTED WILL  Complot

HAVE PEN
POSITION = 2 (DRAW) OR = 3 (MOVE). IN ADDITION THE TABLE  Complot

CURRENTLY
CONTAINS 4 CONTROL CHARACTERS,
Complot

Complot

PEN POSITION =
0
Complot

----------------
Complot

SHIFT THE NEXT
PRINTED CHARACTER BY X AND Y. 3 CONTROL CHARACTERS  Complot

ARE PRESENTLY
INCLUDED IN THE SOFTWARE CHARACTER TABLE TO ALLOW    Complot

SHIFTING.
Complot

Complot

{   = SHIFT UP (FOR
SUPERSCRIPTS..............X= 0.0, Y= 0.5)      Complot

}   = SHIFT DOWN (FOR
SUBSCRIPTS..............X= 0.0, Y=-0.5)      Complot

\   = SHIFT LEFT 1 CHARACTER (FOR
BACKSPACE...X=-1.0, Y= 0.0)      Complot

Complot

PEN POSITION
=-1
Complot

----------------
Complot

SELECT THE NEXT
PRINTED CHARACTER FROM THE ALTERNATE CHARACTER     Complot

SET. AT PRESENT
THIS CONTROL CHARACTER IS,
Complot

Complot

]   = SWITCH TO ALTERNATE CHARACTER
SET
Complot

Complot

THESE 4 CONTROL
CHARACTERS ARE ONLY DEFINED BY THE VALUE OF THE    Complot

PEN POSITION IN
THE SOFTWARE CHARACTER TABLE (I.E., THEY ARE NOT   Complot

HARD WIRED INTO
THIS PROGRAM). AS SUCH BY MODIFYING THE SOFTWARE   Complot

CHARACTER TABLE
THE USER HAS THE OPTION OF DEFINING ANY CONTROL    Complot

CHARACTERS TO
MEET SPECIFIC NEEDS.
Complot

Complot

THESE CHARACTERS
MAY BE USED IN CHARACTER STRINGS TO PRODUCE       Complot

SPECIAL EFFECTS.
FOR EXAMPLE, TO PLOT SUBSCRIPT 5, B, SUPERSCRIPT  Complot

10 USE THE
STRING,
Complot

Complot

}5B{1{0
Complot

Complot

TO PLOT B,
SUBSCRIPT 5 AND SUPERSCRIPT 10 WITH THE 5 DIRECTLY      Complot

BELOW THE 1 OF
THE 10 WE CAN USE THE BACKSPACE CHARACTER TO
Complot

POSITION THE 1
DIRECTLY ABOVE THE 5 USING THE STRING,
Complot

Complot

B}5\{1{0
Complot

Complot

TO PLOT UPPER
CASE GREEK GAMMA FOLLOWED BY THE WORD TOTAL (I.E.,   Complot

RESONANCE TOTAL
WIDTH) USE THE STRING.
Complot

Complot

]G TOTAL
Complot

Complot

NOTE, WHEN THESE
CONTROL CHARACTERS ARE USED THEY ONLY EFFECT THE  Complot

NEXT 1 PRINTED
CHARACTER (SEE, ABOVE EXAMPLE OF PLOTTING SUPER-    Complot

SCRIPT 10 WHERE
THE SHIFT UP CONTROL CHARACTER WAS USED BEFORE THE Complot

1 AND THEN AGAIN
BEFORE THE 0 AND THE BACKSPACE AND SHIFT UP       Complot

CONTROL
CHARACTERS WERE USED IN COMBINATION).
Complot

Complot

IF THESE 4
CONTROL CHARACTERS ARE NOT AVAILABLE ON YOUR COMPUTER   Complot

YOU CAN MODIFY
THE SOFTWARE CHARACTER TABLE TO USE ANY OTHER 4     Complot

CHARACTERS THAT
YOU DO NOT NORMALLY USE IN CHARACTER STRINGS (FOR  Complot

DETAILS SEE THE
SOFTWARE CHARACTER TABLE).
Complot

Complot

STANDARD/ALTERNATE CHARACTER SETS
Complot

------------------------------------------------------------------ Complot

THE SOFTWARE
CHARACTER TABLE CONTAINS 2 SETS OF CHARACTERS WHICH   Complot

ARE A STANDARD
SET (ALL CHARACTERS ON AN IBM KEYBOARD) AND AN      Complot

ALTERNATE SET
(UPPER AND LOWER CASE GREEK CHARACTERS AND SPECIAL   Complot

CHARACTERS). TO DRAW A CHARACTER FROM THE
ALTERNATE CHARACTER SET  Complot

PUT A RIGHT
BRACKET CHARACTER (]) BEFORE A CHARACTER (SEE THE      Complot

ABOVE EXAMPLE
AND THE SOFTWARE CHARACTER TABLE FOR DETAILS). THIS  Complot

CONTROL CHARACTER
WILL ONLY EFFECT THE NEXT 1 PLOTTED CHARACTER.   Complot

Complot

SUB AND SUPER
SCRIPTS
Complot

------------------------------------------------------------------
Complot

TO DRAW
SUBSCRIPT PRECEED A CHARACTER BY }. TO DRAW SUPERSCRIPT    Complot

PRECEED A
CHARACTER BY { (SEE THE ABOVE EXAMPLE AND THE SOFTWARE   Complot

CHARACTER TABLE
FOR DETAILS). THESE CONTROL CHARACTER WILL ONLY    Complot

EFFECT THE NEXT
1 PLOTTED CHARACTER.
Complot

Complot

BACKSPACING
Complot

------------------------------------------------------------------
Complot

TO BACKSPACE ONE
CHARACTER PRECEED A CHARACTER BY \ (SEE, THE      Complot

ABOVE EXAMPLE
AND THE SOFTWARE CHARACTER TABLE FOR DETAILS). THIS  Complot

CONTROL
CHARACTER WILL PERFORM A TRUE BACKSPACE AND WILL EFFECT    Complot

ALL FOLLOWING
CHARACTERS IN THE SAME CHARACTER STRING.
Complot

Complot

PLOT
DIMENSIONS
Complot

---------------
Complot

ARE DEFINED BY
USER INPUT. INTERNALLY THE PROGRAM WILL CREATE A    Complot

PLOT IN
APPROXIMATELY A4 OR 8-1/2 BY 11 INCH FORMAT. DURING
Complot

OUTPUT THE PLOT
IS TRANSFORMED TO THE UNITS (INCHES, CENTIMETERS,  Complot

MILLIMETERS,
WHATEVER) OF THE PLOTTER BEING USED AND OUTPUT.       Complot

Complot

=====
PLOTTER/GRAPHICS TERMINAL INTERFACE ============================= Complot

=======================================================================
Complot

=======================================================================
Convert

Convert

PROGRAM
CONVERT
Convert

VERSION 75-1 (APRIL
1975)
Convert

VERSION 78-1
(JANUARY 1978)
Convert

VERSION 80-1
(AUGUST 1980)  IBM VERSION
Convert

VERSION 80-2
(DECEMBER 1980)
Convert

VERSION 82-1
(JANUARY 1982)
Convert

VERSION 83-1
(JANUARY 1983)
Convert

VERSION 86-1
(JANUARY 1986)*NEW PROGRAM
Convert

*FORTRAN-77/H VERSION
Convert

*MULTIPLE INPUT OPTIONS
Convert

VERSION 88-1
(AUGUST 1988) *OPTION...INTERNALLY DEFINE ALL I/O     Convert

FILE NAMES (SEE, SUBROUTINE FILEIO     Convert

FOR DETAILS).
Convert

*IMPROVED BASED ON USER COMMENTS.       Convert

*ADDED NAMES OPTION TO TURN ON/OFF      Convert

STANDARD FILE NAMES.
Convert

*ADDED REWIND OPTION TO TURN ON/OFF     Convert

REWIND AT START OF PROGRAMS.
Convert

*DELETED HARWELL AND JAERI OPTIONS      Convert

(PREVIOUSLY ONLY REQUIRED FOR GRAPHIC  Convert

INTERFACE. NO LONGER REQUIRED).
Convert

VERSION 89-1
(JANUARY 1989)*PSYCHOANALYZED BY PROGRAM FREUD TO     Convert

INSURE PROGRAM WILL NOT DO ANYTHING    Convert

CRAZY.
Convert

*IMPROVED BASED ON USER COMMENTS.       Convert

*ADDED LIVERMORE
CIVIC COMPILER
Convert

CONVENTIONS.
Convert

*UPDATED TO USE NEW PROGRAM CONVERT     Convert

KEYWORDS.
Convert

*ADDED ENDFILE
OPTION TO OPTIONALLY
Convert

ALLOW END OF FILE TO BE WRITTEN
Convert

VERSION 91-1
(JUNE 1991)   *ADDED FORTRAN
SAVE OPTION
Convert

VERSION 92-1
(JANUARY 1992)*ADDED ACTION OPTION - TO CONTROL       Convert

INTERACTIVE INPUT TO CODES
Convert

*ADDED BLANK DELIMITED KEYWORD INPUT    Convert

(REPLACES EARLIER FIXED FIELD INPUT)   Convert

*WARNING...THE INPUT PARAMETER FORMAT   Convert

HAS BEEN GENERALIZED - FOR DETAILS     Convert

SEE BELOW.
Convert

VERSION 94-1
(JANUARY 1994)*VARIABLE PROGRAM FILENAMES
Convert

TO ALLOW ACCESS TO FILE STRUCTURES     Convert

(WARNING - INPUT PARAMETER FORMAT      Convert

HAS BEEN CHANGED)
Convert

*CLOSE ALL FILES BEFORE TERMINATING     Convert

(SEE, SUBROUTINE ENDIT)
Convert

*ADDED KEYWORD CLOSE.
Convert

VERSION 96-1
(JANUARY 1996) *COMPLETE RE-WRITE
Convert

*IMPROVED COMPUTER INDEPENDENCE
Convert

*ALL
DOUBLE PRECISION
Convert

*ON SCREEN OUTPUT
Convert

VERSION 99-1
(MARCH 1999)   *GENERAL
IMPROVEMENTS BASED ON
Convert

USER
FEEDBACK
Convert

VERS. 2000-1
(FEBRUARY 2000)*GENERAL IMPROVEMENTS BASED ON
Convert

USER FEEDBACK
Convert

VERS. 2002-1
(MAY 2002)
*OPTIONAL INPUT PARAMETERS
Convert

VERS. 2004-1
(MARCH 2004)   *GENERAL
UPDATE
Convert

VERS. 2007-1
(JAN.  2007)   *GENERAL UPDATE
Convert

Convert

OWNED,
MAINTAINED AND DISTRIBUTED BY
Convert

------------------------------------
Convert

THE NUCLEAR DATA
SECTION
Convert

INTERNATIONAL
ATOMIC ENERGY AGENCY
Convert

P.O. BOX 100
Convert

A-1400, VIENNA, AUSTRIA
Convert

EUROPE
Convert

Convert

ORIGINALLY
WRITTEN BY
Convert

------------------------------------
Convert

DERMOTT E.
CULLEN
Convert

UNIVERSITY OF CALIFORNIA
Convert

LAWRENCE
LIVERMORE
NATIONAL LABORATORY
Convert

L-159
Convert

P.O. BOX 808
Convert

LIVERMORE, CA
94550
Convert

U.S.A.
Convert

TELEPHONE  925-423-7359
Convert

E. MAIL    [email-masked]
Convert

WEBSITE
HTTP://WWW.LLNL.GOV/CULLEN1
Convert

Convert

AUTHORS
MESSAGE                                                    Convert

---------------
Convert

THE COMMENTS
BELOW SHOULD BE CONSIDERED THE LATEST DOCUMENATION    Convert

FOR THIS PROGRAM
INCLUDING ALL RECENT IMPROVEMENTS. PLEASE READ    Convert

ALL OF THESE
COMMENTS BEFORE IMPLEMENTATION, PARTICULARLY THE      Convert

COMMENTS
CONCERNING COMPUTER DEPENDENT CODING.
Convert

Convert

AT THE PRESENT
TIME WE ARE ATTEMPTING TO DEVELOP A SET OF COMPUTER Convert

INDEPENDENT
PROGRAMS THAT CAN EASILY BE IMPLEMENTED ON ANY ONE     Convert

OF A WIDE
VARIETY OF COMPUTERS. IN ORDER TO ASSIST IN THIS PROJECT Convert

IT WOULD BE
APPECIATED IF YOU WOULD NOTIFY THE AUTHOR OF ANY       Convert

COMPILER
DIAGNOSTICS, OPERATING PROBLEMS OR SUGGESTIONS ON HOW TO  Convert

IMPROVE THIS
PROGRAM. IN PARTICULAR IF YOUR FORTRAN COMPILER, OR   Convert

COMPUTER HAS A
SET OF REQUIREMENTS THAT ARE DIFFERENT FROM THOSE   Convert

OF CDC, CRAY OR
IBM PLEASE NOTIFY THE AUTHOR AND THIS PROGRAM WILL Convert

BE MODIFIED TO
CONSIDER YOUR COMPUTER SEPERATELY. HOWEVER, IN      Convert

ORDER TO PREVENT
A PROLIFERATION OF CODING IT IS IMPERATIVE THAT   Convert

YOU IDENTIFY
EXACTLY HOW YOUR FORTRAN COMPILER OR COMPUTER DIFFERS Convert

FROM THOSE
ALREADY CONSIDERED BY THIS PROGRAM. HOPEFULLY,IN THIS   Convert

WAY FUTURE VERSIONS OF
THIS PROGRAM WILL BE COMPLETELY COMPATIBLE
Convert

FOR USE ON YOUR
COMPUTER.
Convert

Convert

PURPOSE                                                            Convert

-------
Convert

THIS PROGRAM IS
DESIGNED TO AUTOMATICALLY CONVERT FORTRAN PROGRAMS Convert

FOR USE ON ANY
ONE OF A VARIETY OF,
Convert

(1)
COMPUTERS
Convert

(2)
COMPILERS
Convert

(3) PRECISIONS
(SINGLE OR DOUBLE PRECISION)
Convert

(4)
INSTALLATIONS
Convert

(5) STANDARD OR
NON-STANDARD FILE NAMES
Convert

Convert

FORTRAN CODING
CONVENTIONS
Convert

--------------------------
Convert

THIS PROGRAM MAY
BE USED TO CONVERT ANY PROGRAM WHICH USES THE     Convert

FOLLOWING
CONVENTIONS.
Convert

Convert

ALL FORTRAN
STATEMENTS THAT DEPEND ON ANY COMBINATION OF COMPUTER, Convert

COMPILER,
PRECISION AND/OR INSTALLATION AND STANDARD FILE NAMES    Convert

SHOULD BE
PRECEDED AND FOLLOWED BY A COMMENT LINE THAT CONTAINS,   Convert

Convert

C***** DOUBLE
****** ACTIVATE DOUBLE PRECISION (DEFAULT)
Convert

C***** SINGLE
****** ACTIVATE SINGLE PRECISION
Convert

C***** CHARACTER
*** TREAT CHARACTER ARRAYS AS CHARACTERS(DEFAULT) Convert

C***** INTEGER *****
TREAT CHARACTER ARRAYS AS INTEGERS
Convert

C***** STOP
******** ACTIVATE STOP TO TERMINATE PROGRAM
Convert

C***** EXIT
******** ACTIVATE EXIT TO TERMINATE PROGRAM
Convert

C***** PROGRAM
***** ACTIVATE PROGRAM LINE AND CONTINUATIONS       Convert

C***** NAMES
******* ACTIVATE STANDARD FILENAMES
Convert

C***** REWIND
****** ACTIVATE REWIND FILES AT START OF PROGRAM     Convert

C***** ENDFILE *****
ACTIVATE ENDFILE AT END OF PROGRAM
Convert

C***** CIVIC
******* ACTIVATE LIVERMORE
CIVIC COMPILER CONVENTIONS Convert

C***** NOID
******** REMOVE LINE ID IN COLUMNS 73-80 (73-80=BLANK) Convert

C***** SAVE
******** SAVE VARIABLES BETWEEN SUBROUTINE CALLS       Convert

C***** ACTION
****** ACTIVATE INTERACTIVE INPUT TO CODES
Convert

C***** CLOSE
******* ACTIVATE CLOSE ALL FILES BEFORE TERMINATING   Convert

Convert

IF THE USER DOES
NOT SELECT,
Convert

(1) DOUBLE OR
SINGLE      -
THE PROGRAM WILL ACTIVATE DOUBLE       Convert

(2) CHARACTER OR
INTEGER  - THE PROGRAM WILL ACTIVATE
CHARACTER    Convert

(3) STOP OR
EXIT
- THE PROGRAM WILL ACTIVATE STOP
Convert

Convert

IF THE USER
SELECTS,
Convert

(1) DOUBLE AND
SINGLE     - THE
PROGRAM WILL ACTIVATE DOUBLE       Convert

(2) CHARACTER
AND INTEGER - THE PROGRAM WILL ACTIVATE CHARACTER    Convert

(3) STOP AND
EXIT
- THE PROGRAM WILL ACTIVATE STOP         Convert

Convert

IF THE USER DOES
NOT SELECT PROGRAM, NAMES, REWIND, ENDFILE,       Convert

CIVIC, NOID,
SAVE OR ACTION THESE OPTIONS WILL BE TURNED OFF.      Convert

Convert

WHERE CODING IS
COMPUTER OR COMPILER DEPENDENT CODING WILL BE      Convert

PRESENT FOR ALL
POSSIBLE OPTIONS. THIS PROGRAM WILL ALLOW THE      Convert

THE USER TO
CONVERT PROGRAMS FOR USE WITH ANY COMBINATION OF       Convert

OPTIONS. FOR
EXAMPLES OF HOW THIS CONVENTION IS USED SEE THE       Convert

LISTING OF THIS
PROGRAM AND THE COMMENTS BELOW ON COMPUTER
Convert

DEPENDENT CODING.
Convert

Convert

INPUT LINES
Convert

-----------
Convert

LINE   COLS.  DESCRIPTION
Convert

----   -----  --------------------------------------
Convert

1   1-72   BLANK DELIMITED KEYWORDS
Convert

2   1-60   ENDF/B INPUT DATA FILENAME
Convert

(STANDARD OPTION = ENDFB.IN)
Convert

3   1-60   ENDF/B OUTPUT DATA FILENAME                        Convert

(STANDARD OPTION = ENDFB.OUT)
Convert

Convert

*THE FIRST INPUT LINE
IS 72 CHARACTERS.
Convert

*KEYWORDS MAY BE
LOCATED ANYWHERE WITHIN THESE 72 CHARACTERS
Convert

*THERE MAY BE ANY
NUMBER OF KEYWORDS INPUT
Convert

*EACH KEYWORD MUST BE
BLANK DELIMITED, E.G., DOUBLE CHARACTER       Convert

IS LEGAL INPUT -
DOUBLECHARACTER IS NOT LEGAL INPUT.
Convert

*THERE MUST BE ONE OR
MORE BLANKS BETWEEN KEYWORDS
Convert

Convert

*NOTE, THIS NEW INPUT
PARAMETER FORMAT (VERSION 92-1) IS COMPLETELY Convert

COMPATIBLE WITH
THE OLDER FIXED FIELD FORMAT. SO THAT IF YOU HAVE  Convert

INPUT THAT YOU
HAVE USED IN THE PAST YOU CAN CONTINUE TO USE IT.   Convert

Convert

LEGAL KEYWORDS
INCLUDE,
Convert

Convert

DOUBLE        ACTIVATE DOUBLE PRECISION
(DEFAULT)
Convert

SINGLE
ACTIVATE SINGLE PRECISION
Convert

CHARACTER     TREAT CHARACTER ARRAYS
AS CHARACTERS(DEFAULT)
Convert

INTEGER       TREAT CHARACTER
ARRAYS AS INTEGERS
Convert

PROGRAM       ACTIVATE
PROGRAM LINE AND CONTINUATIONS
Convert

NAMES
ACTIVATE STANDARD FILENAMES
Convert

REWIND
ACTIVATE REWIND FILES AT START OF PROGRAM
Convert

ENDFILE       ACTIVATE
ENDFILE AT END OF PROGRAM
Convert

CIVIC
ACTIVATE LIVERMORE
CIVIC COMPILER CONVENTIONS
Convert

NOID
REMOVE LINE ID IN COLUMNS 73-80 (73-80=BLANK)
Convert

SAVE
SAVE VARIABLES BETWEEN SUBROUTINE CALLS
Convert

ACTION
ACTIVATE INTERACTIVE INPUT FOR CODES
Convert

CLOSE
ACTIVATE CLOSE ALL FILES BEFORE TERMINATING
Convert

Convert

EXAMPLE INPUT
NO. 1
Convert

-------------------
Convert

TO USE A PROGRAM
IN SINGLE PRECISION, USE THE STANDARD FILE NAMES, Convert

REWIND ALL UNITS
AT THE START OF THE PROGRAM AND TREAT CHARACTER   Convert

ARRAYS AS
CHARACTER (FORTRAN-77 CONVENTION).
Convert

Convert

READ  \PREPRO93\RECENT\RECENT.OLD AND
Convert

WRITE
\PREPRO93\RECENT\RECENT.NEW
Convert

Convert

THE FOLLOWING 3
INPUT LINES ARE REQUIRED,
Convert

Convert

SINGLE NAMES
REWIND CHARACTER
Convert

\PREPRO93\RECENT\RECENT.OLD
Convert

\PREPRO93\RECENT\RECENT.NEW
Convert

Convert

NOTE, SINCE
CHARACTER IS THE STANDARD OPTION THE KEYWORD CHARACTER Convert

NEED NOT APPEAR
ON THE ABOVE INPUT LINE.
Convert

Convert

EXAMPLE INPUT
NO. 2
Convert

-------------------
Convert

TO USE A PROGRAM
IN DOUBLE PRECISION AND TREAT ALL CHARACTER       Convert

ARRAYS AS
INTEGER (FORTRAN-H CONVENTION).
Convert

Convert

USE THE STANDARD
FILENAMES TO READ = CONVERT.IN AND WRITE =
Convert

CONVERT.OUT
(THIS CAN BE DONE BY LEAVING THE SECOND AND THIRD      Convert

INPUT LINES
BLANK).
Convert

Convert

THE FOLLOWING 3
INPUT LINES ARE REQUIRED,
Convert

Convert

DOUBLE  INTEGER
Convert

(NOTE, THIS IS A
BLANK LINE)
Convert

(NOTE, THIS IS A
BLANK LINE)
Convert

Convert

NOTE, SINCE DOUBLE IS
THE STANDARD OPTION THE KEYWORD DOUBLE       Convert

NEED NOT APPEAR
ON THE ABOVE INPUT LINE.
Convert

Convert

EXAMPLE INPUT
NO. 3
Convert

-------------------
Convert

TO ACTIVATE THE
PROGRAM LINE, USE DOUBLE PRECISION AND TREAT ALL   Convert

CHARACTER ARRAYS
AS CHARACTER.
Convert

Convert

Convert

READ  \PREPRO93\RECENT\RECENT.OLD AND
Convert

WRITE THE
STANDARD FILENAME = CONVERT.OUT (LEAVE THE THIRD INPUT   Convert

LINE
BLANK).
Convert

Convert

THE FOLLOWING 3
INPUT LINES ARE REQUIRED,
Convert

Convert

PROGRAM
Convert

\PREPRO93\RECENT\RECENT.OLD
Convert

(NOTE, THIS IS A
BLANK LINE)
Convert

Convert

NOTE, SINCE
DOUBLE, CHARACTER AND EXIT ARE THE STANDARD OPTIONS    Convert

THEY NEED NOT
APPEAR ON THE ABOVE INPUT LINE AND IN THIS EXAMPLE   Convert

HAVE BEEN
OMITTED.
Convert

Convert

WARNING
Convert

-------
Convert

(1) THE PROGRAM WILL
ALWAYS ACTIVATE DOUBLE OR SINGLE, CHARACTER   Convert

OR INTEGER (AS
DESCRIBED ABOVE).
Convert

Convert

(2) CODING IN
THE PROGRAM FOR ANY KEYWORDS THAT ARE NOT ACTIVATED  Convert

WILL BE
CONVERTED TO COMMENT LINES AND AS SUCH WILL EFFECTIVELY    Convert

DISAPPEAR FROM
THE PROGRAM. THEREFORE IF THE KEYWORDS PROGRAM,     Convert

NAMES, REWIND, ENDFILE,
CIVIC OR NOID ARE NOT INPUT BY THE USER    Convert

THESE OPTIONS
WILL BE TURNED OFF AND ANY CODING USING THESE
Convert

KEYWORDS WILL
EFFECTIVELY DISAPPEAR FROM THE PROGRAM.
Convert

Convert

(3) THE SERIES
OF CODES THAT ARE DESIGNED TO BE AUTOMATICALLY      Convert

TRANSLATED BY
THIS PROGRAM REQUIRE THAT ALL CALCULATIONS BE
Convert

PERFORMED IN
DOUBLE PRECISION ON SHORT WORD LENGTH COMPUTERS       Convert

(E.G., IBM
COMPUTERS). THIS PROGRAM WILL ALLOW YOU TO SPECIFY      Convert

EITHER DOUBLE OR
SINGLE PRECISION. HOWEVER, IF YOU SPECIFY
Convert

SINGLE PRECISION
THIS PROGRAM WILL PRINT A WARNING MESSAGE THAT    Convert

THE CONVERTED
PROGRAM SHOULD ONLY BE USED ON LONG WORD LENGTH      Convert

COMPUTERS (E.G.,
CDC COMPUTERS).
Convert

Convert

PROGRAM
OPERATION
Convert

-----------------
Convert

THE PROGRAM WILL
SEARCH FOR COMMENT LINES THAT START WITH C**      Convert

IN COLUMNS 1-3
FOLLOWED BY ANY ONE OF THE ALLOWED KEYWORDS
Convert

IF THE KEYWORD
IS THE SAME AS ONE OF THE KEYWORDS INPUT BY
Convert

THE USER ALL
LINES UP TO THE NEXT LINE WITH C** IN COLUMNS 1-3     Convert

FOLLOWED BY THE
SAME KEYWORD WILL BE SET ACTIVE BY SETTING COLUMN  Convert

1 TO BLANK. IF
THE KEYWORDS DIFFERS FROM THAT INPUT BY THE USER    Convert

ALL LINES UP TO
THE NEXT LINE WITH C** IN COLUMNS 1-3 FOLLOWED BY  Convert

THE SAME KEYWORD
WILL BE SET INACTIVE BY SETTING COLUMN 1 TO C.    Convert

Convert

KEYWORDS MAY NOT
BE NESTED (I.E., THIS PROGRAM WILL ONLY OPERATE   Convert

PROPERLY IF KEYWORDS
APPEAR IN PAIRS. ONCE A LINE IS FOUND THAT    Convert

CONTAINS A
KEYWORD, THE NEXT LINE THAT CONTAINS A KEYWORD MUST     Convert

CONTAIN THE SAME
KEYWORD).
Convert

Convert

PROGRAM
LINE
Convert

------------
Convert

THE FORTRAN FILE
MAY START WITH A PROGRAM LINE AND CONTINUATIONS.  Convert

FOR USE ON
CDC-7600 OR CRAY-1 COMPUTERS THIS PROGRAM CAN ACTIVATE  Convert

THE PROGRAM LINE
AND CONTINUATION LINES. FOR USE ON OTHER TYPES OF Convert

COMPUTERS THIS
PROGRAM WILL AUTOMATICALLY DE-ACTIVATE THE PROGRAM  Convert

LINE AND
CONTINUATION LINES. THIS CONVENTIONS HAS BEEN INTRODUCED  Convert

BECAUSE SOME
CDC-7600 COMPILERS CONSIDER IT AN ERROR IF THE FIRST  Convert

LINE IS NOT A
PROGRAM LINE. PRECEEDING COMMENT LINES ARE NOT       Convert

ALLOWED.
THEREFORE THE NORMAL CONVENTION, DESCRIBED
ABOVE, OF
Convert

USING PRECEDING
AND FOLLOWING COMMENT LINES, CANNOT BE USED AT     Convert

THE BEGINNING OF
THE PROGRAM.
Convert

Convert

COMMENT
LINES
Convert

-------------
Convert

COMMENT LINES
MAY APPEAR ON LINES BETWEEN PAIRS OF KEYWORD LINES   Convert

ONLY IF THE
COMMENT LINES CONTAINS C-- IN COLUMS 1-3. ANY LINE     Convert

THAT CONTAINS
ANYTHING ELSE IN COLUMNS 1-3 MAY BE ACTIVATED
Convert

BY THIS PROGRAM
BY SETTING COLUMN 1 BLANK AND CAN LEAD TO ERRORS   Convert

DURING
COMPILATION AND/OR EXECUTION.
Convert

Convert

INPUT FILES                                                        Convert

-----------
Convert

UNIT  DESCRIPTION
Convert

----  -----------                                                  Convert

2   INPUT LINE (BCD - 80
CHARACTERS/RECORD)
Convert

10   ORIGINAL PROGRAM (BCD - 80
CHARACTERS/RECORD)
Convert

Convert

OUTPUT
FILES
Convert

------------
Convert

UNIT  DESCRIPTION
Convert

----  -----------
Convert

3   OUTPUT REPORT (BCD -
120 CHARACTERS/RECORD)
Convert

11   RE-FORMATTED PROGRAM (BCD - 80
CHARACTERS/RECORD)
Convert

Convert

OPTIONAL
STANDARD FILE NAMES (SEE SUBROUTINE FILIO1 AND FILIO2)    Convert

---------------------------------------------------------------    Convert

UNIT  FILE NAME
Convert

----  ----------
Convert

2   CONVERT.INP
Convert

3   CONVERT.LST
Convert

10   CONVERT.IN
Convert

11   CONVERT.OUT
Convert

Convert

=======================================================================
Convert

=======================================================================
Dictin

Dictin

PROGRAM DICTIN
(Renamed from DICTION to eliminate conflict with    Dictin

UNIX diction command - 12/22/02)
Dictin

==============                                                     Dictin

VERSION 81-1
(SEPTEMBER 1981)
Dictin

VERSION 82-1
(JANUARY 1982)
Dictin

VERSION 83-1
(JANUARY 1983)  *KEEP ORIGINAL MOD.
NUMBER
Dictin

*NEW, MORE COMPATIBLE I/O UNITS.      Dictin

VERSION 84-1
(SEPTEMBER 1984)*UPDATED TO HANDLE ENDF/B-VI FORMAT.  Dictin

(PROGRAM WILL NOW WORK ON ALL
Dictin

VERSIONS OF THE ENDF/B FORMAT).     Dictin

VERSION 85-1
(AUGUST 1985)   *FORTRAN-77/H
VERSION
Dictin

VERSION 86-1
(JANUARY 1986)  *MAT ORDER
CHECK.                     Dictin

*IF NO HOLLERITH SECTION COPY MAT.    Dictin

VERSION 88-1
(JULY 1988)
*OPTION...INTERNALLY DEFINE ALL I/O   Dictin

FILE NAMES (SEE, SUBROUTINE FILEIO   Dictin

FOR DETAILS).
Dictin

*IMPROVED BASED ON USER COMMENTS.     Dictin

VERSION 89-1
(JANUARY 1989)  *PSYCHOANALYZED BY
PROGRAM FREUD TO   Dictin

INSURE PROGRAM WILL NOT DO ANYTHING
Dictin

CRAZY.
Dictin

*IMPROVED BASED ON USER COMMENTS.     Dictin

*ADDED
LIVERMORE CIVIC
COMPILER
Dictin

CONVENTIONS.
Dictin

*UPDATED TO USE NEW PROGRAM CONVERT   Dictin

KEYWORDS.
Dictin

VERSION 92-1
(JANUARY 1992)  *UPDATED BASED ON
USER COMMENTS.
Dictin

*UP TO 6000 SECTIONS PER TAPE.
Dictin

*CHANGED
DEFAULT MOD NUMBER FOR NEW
Dictin

SECTIONS FROM 0 TO 1
Dictin

VERSION 94-1
(JANUARY 1994)  *VARIABLE ENDF/B
DATA FILENAMES       Dictin

TO ALLOW ACCESS TO FILE
STRUCTURES   Dictin

(WARNING - INPUT PARAMETER FORMAT    Dictin

HAS BEEN CHANGED)
Dictin

*CLOSE ALL FILES BEFORE TERMINATING   Dictin

(SEE, SUBROUTINE ENDIT)
Dictin

*ADDED FORTRAN SAVE OPTION
Dictin

VERSION 96-1
(JANUARY 1996) *COMPLETE RE-WRITE
Dictin

*IMPROVED COMPUTER INDEPENDENCE
Dictin

*ALL DOUBLE PRECISION
Dictin

*ON SCREEN OUTPUT
Dictin

*UNIFORM TREATMENT OF ENDF/B I/O
Dictin

*IMPROVED OUTPUT PRECISION
Dictin

VERSION 99-1
(MARCH 1999)   *CORRECTED
CHARACTER TO FLOATING       Dictin

POINT READ FOR MORE DIGITS
Dictin

*UPDATED TEST FOR ENDF/B FORMAT
Dictin

VERSION BASED ON RECENT FORMAT CHANGE Dictin

*GENERAL
IMPROVEMENTS BASED ON
Dictin

USER FEEDBACK
Dictin

VERS. 2000-1
(FEBRUARY 2000)*GENERAL IMPROVEMENTS BASED ON
Dictin

USER
FEEDBACK
Dictin

VERS. 2002-1
(MAY 2002)
*OPTIONAL INPUT PARAMETERS
Dictin

*RENAMED dictin TO ELIMINATE CONFLICT  Dictin

WITH
UNIX diction COMMAND.
Dictin

*ADDED DOCUMENTATION LINE TO COMMENTS. Dictin

VERS. 2004-1
(JAN. 2004)    *GENERAL
UPDATE BASED ON USER FEEDBACK Dictin

*UP TO 100,000 SECTIONS PER
TAPE.
Dictin

VERS. 2007-1
(JAN. 2007)    *CHECKED
AGAINST ALL ENDF/B-VII.
Dictin

*UP TO 500,000 SECTIONS PER TAPE.      Dictin

Dictin

OWNED,
MAINTAINED AND DISTRIBUTED BY
Dictin

------------------------------------
Dictin

THE NUCLEAR DATA
SECTION
Dictin

INTERNATIONAL
ATOMIC ENERGY AGENCY
Dictin

P.O. BOX 100
Dictin

A-1400, VIENNA, AUSTRIA
Dictin

EUROPE
Dictin

Dictin

ORIGINALLY
WRITTEN BY
Dictin

------------------------------------
Dictin

DERMOTT E.
CULLEN
Dictin

UNIVERSITY OF CALIFORNIA
Dictin

LAWRENCE
LIVERMORE
NATIONAL LABORATORY
Dictin

L-159
Dictin

P.O. BOX 808
Dictin

LIVERMORE, CA
94550
Dictin

U.S.A.
Dictin

TELEPHONE  925-423-7359
Dictin

E. MAIL    [email-masked]
Dictin

WEBSITE
HTTP://WWW.LLNL.GOV/CULLEN1
Dictin

Dictin

AUTHORS
MESSAGE
Dictin

---------------
Dictin

THE COMMENTS
BELOW SHOULD BE CONSIDERED THE LATEST DOCUMENATION    Dictin

FOR THIS PROGRAM
INCLUDING ALL RECENT IMPROVEMENTS. PLEASE READ    Dictin

ALL OF THESE
COMMENTS BEFORE IMPLEMENTATION.
Dictin

Dictin

AT THE PRESENT
TIME WE ARE ATTEMPTING TO DEVELOP A SET OF COMPUTER Dictin

INDEPENDENT
PROGRAMS THAT CAN EASILY BE IMPLEMENTED ON ANY ONE     Dictin

OF A WIDE
VARIETY OF COMPUTERS. IN ORDER TO ASSIST IN THIS PROJECT Dictin

IT WOULD BE
APPECIATED IF YOU WOULD NOTIFY THE AUTHOR OF ANY
Dictin

COMPILER
DIAGNOSTICS, OPERATING PROBLEMS OR SUGGESTIONS ON HOW TO  Dictin

IMPROVE THIS
PROGRAM. HOPEFULLY, IN THIS WAY FUTURE VERSIONS OF    Dictin

THIS PROGRAM
WILL BE COMPLETELY COMPATIBLE FOR USE ON YOUR         Dictin

COMPUTER.
Dictin

Dictin

PURPOSE
Dictin

-------
Dictin

THIS PROGRAM IS
DESIGNED TO CREATE A REACTION INDEX FOR EACH
Dictin

MATERIAL ON AN
ENDF/B FORMATTED TAPE AND TO INSERT THIS REACTION   Dictin

INDEX IN FILE 1,
SECTION 451 OF EACH MATERIAL.
Dictin

Dictin

IN THE
DESCRIPTION THAT FOLLOWS FOR SIMPLICITY THE ENDF/B
Dictin

TERMINOLOGY---ENDF/B
TAPE---WILL BE USED. IN FACT THE ACTUAL
Dictin

MEDIUM MAY BE
TAPE, CARDS, DISK, OR ANY OTHER MEDIUM.
Dictin

Dictin

ENDF/B
FORMAT
Dictin

-------------
Dictin

THIS PROGRAM
ONLY USES THE ENDF/B BCD OR CARD IMAGE FORMAT (AS     Dictin

OPPOSED TO THE
BINARY FORMAT) AND CAN HANDLE DATA IN ANY VERSION   Dictin

OF THE ENDF/B
FORMAT (I.E., ENDF/B-I, II,III, IV, V OR VI FORMAT). Dictin

Dictin

THIS PROGRAM
WILL AUTOMATICALLY DETERMINE WHICH VERSION OF THE     Dictin

ENDF/B FORMAT
EACH MAT IS IN AND WILL THEN PROPERLY REPLACE THE    Dictin

REACTION INDEX
FOR EACH MAT. DIFFERENT MATS ON THE SAME TAPE MAY   Dictin

EVEN BE IN
DIFFERENT VERSIONS OF THE ENDF/B FORMAT.
Dictin

Dictin

IT IS ASSUMED
THAT THE DATA IS CORRECTLY CODED IN THE ENDF/B
Dictin

FORMAT AND NO
ERROR CHECKING IS PERFORMED. IN PARTICULAR IT IS     Dictin

ASSUMED THAT THE
MAT, MF AND MT ON EACH LINE IS CORRECT. SEQUENCE  Dictin

NUMBERS (COLUMNS
76-80) NEED NOT BE PRESENT ON INPUT, BUT WILL BE  Dictin

CORRECTLY OUTPUT
ON ALL LINES.
Dictin

Dictin

ENDF/B FORMAT
VERSION
Dictin

---------------------
Dictin

THE ENDF/B
FORMAT CAN BE DETERMINED FROM THE SECOND LINE OF
Dictin

THE HOLLERITH
SECTION (MF=1, MT=451).
Dictin

ENDF/B-IV = N1 -
LINE COUNT (POSITIVE)
Dictin

ENDFB/-V  = N1 = N2 =0
Dictin

ENDF/B-VI = N1
=0, N2= VERSION NUMBER (6 OR MORE)
Dictin

Dictin

SECTION
SIZE
Dictin

------------
Dictin

SINCE THIS
PROGRAM ONLY READS THE DATA ONE LINE AT A TIME THERE    Dictin

IS NO LIMIT TO
THE SIZE OF ANY GIVEN SECTION, E.G. THE TOTAL
Dictin

CROSS SECTION
MAY BE DESCRIBED BY 200,000 DATA POINTS.
Dictin

Dictin

NUMBER OF
SECTIONS PER TAPE
Dictin

---------------------------
Dictin

IT IS ASSUMED
THAT THE ENDF/B TAPE CONTAINS 100,000 OR FEWER
Dictin

SECTIONS =
100,000 OR FEWER MAT,MF,MT COMBINATIONS. IF THIS LIMIT  Dictin

IS EXCEEDED THIS
PROGRAM WILL TERMINATE EXECUTION. IF NEED BE THIS Dictin

LIMIT CAN EASILY
BE CHANGED BY CHANGING THE DIMENSION STATEMENT    Dictin

BELOW AND
RE-DEFINING THE VARIABLE MAXTAB IN THE BELOW DATA        Dictin

STATEMENT.
ALTERNATIVELY THE ENDF/B TAPE MAY BE DIVIDED INTO A     Dictin

NUMBER SMALLER
TAPES EACH CONTAINING 100,000 OR FEWER SECTIONS.    Dictin

EACH ENDF/B TAPE
CAN THEN RUN THROUGH THIS PROGRAM AND THE OUTPUT  Dictin

FOR EACH ENDF/B
TAPE CAN THEN BE RE-COMBINED (I.E., MERGED BACK    Dictin

TOGETHER).
Dictin

Dictin

HOLLERITH SECTION
Dictin

-----------------
Dictin

IF ANY MATERIAL
DOES NOT INITIALLY CONATIN A SECTION MF=1, MT=451  Dictin

A WARNING
MESSAGE WILL BE PRINTED AND THE MATERIAL WILL BE COPIED. Dictin

Dictin

IF ANY MATERIAL
INITIALLY CONTAINS A SECTION MF=1, MT=451 A NEW    Dictin

REACTION INDEX
WILL BE CREATED AND INSERTED. THE INITIAL SECTION   Dictin

MF=1, MT=451 MAY
OR MAY NOT CONTAIN A REACTION INDEX.
Dictin

Dictin

IF THE MATERIAL
INITIALLY CONTAINS A REACTION INDEX IT WILL BE     Dictin

USED TO DEFINE
THE MOD NUMBER FOR CORRESPONDING SECTIONS IN THE    Dictin

NEW REACTION
INDEX (I.E. IF A SECTION FROM THE ORIGINAL REACTION   Dictin

INDEX HAS THE
SAME MF/MT NUMBERS AS A SECTION IN THE NEW REACTION  Dictin

INDEX THE MOD
NUMBER FROM THE ORIGINAL REACTION INDEX WILL BE USED Dictin

IN THE NEW
REACTION INDEX). OTHERWISE THE MOD NUMBER IN THE NEW    Dictin

REACTION INDEX
WILL BE SET EQUAL TO ZERO.                          Dictin

Dictin

PROGRAM
OPERATION
Dictin

-----------------
Dictin

THE ENTIRE
ENDF/B TAPE IS FIRST READ AND A DICTIONARY ENTRY IS     Dictin

CREATED FOR EACH
SECTION OF THE TAPE. THE ENDF/B TAPE IS THEN      Dictin

REWOUND AND READ
A SECOND TIME. DURING THIS SECOND PASS THE        Dictin

DICTIONARY OF
EACH MAT IS REPLACED. THIS VERSION OF DICTIN
Dictin

DOES NOT USE
SCRATCH FILES AND IS MORE EFFICIENT THAN EARLIER      Dictin

VERSIONS OF
DICTIN.
Dictin

Dictin

INPUT LINES
Dictin

-----------
Dictin

LINE
COLS.  DESCRIPTION
Dictin

----   -----  ------------------------------
Dictin

1   1-60   ENDF/B INPUT DATA FILENAME
Dictin

(STANDARD OPTION = ENDFB.IN)
Dictin

2   1-60   ENDF/B OUTPUT DATA FILENAME
Dictin

(STANDARD OPTION = ENDFB.OUT)
Dictin

Dictin

EXAMPLE INPUT
NO. 1
Dictin

-------------------
Dictin

READ
\ENDFB6\K300\ENDFB.IN AND WRITE \ENDFB\K300\ENDFB.OUT. THE    Dictin

FOLLOWING 2
INPUT LINES ARE REQUIRED,
Dictin

Dictin

\ENDFB6\K300\ENDFB.IN
Dictin

\ENDFB6\K300\ENDFB.OUT
Dictin

Dictin

EXAMPLE INPUT
NO. 2
Dictin

-------------------
Dictin

USE THE DEFAULT
FILENAMES TO READ ENDFB.IN AND WRITE ENDFB.OUT.    Dictin

2 BLANK INPUT
LINES ARE REQUIRED
Dictin

Dictin

INPUT FILES
Dictin

-----------
Dictin

UNIT  DESCRIPTION
Dictin

----  -----------
Dictin

2  INPUT PARAMETERS (BCD - 80
CHARACTERS/RECORD)
Dictin

10  ORIGINAL TAPE OF ENDF/B DATA (BCD - 80
CHARACTERS/RECORD)
Dictin

Dictin

OUTPUT
FILES
Dictin

------------                                                       Dictin

UNIT  DESCRIPTION
Dictin

----  -----------
Dictin

3  OUTPUT REPORT (BCD - 120
CHARACTERS/RECORD)
Dictin

11  FINAL TAPE OF ENDF/B DATA
(BCD - 80 CHARACTERS/RECORD)
Dictin

Dictin

OPTIONAL
STANDARD FILE NAMES (SEE SUBROUTINE FILIO1 AND FILIO2)    Dictin

---------------------------------------------------------------    Dictin

UNIT  FILE NAME
Dictin

----  ----------
Dictin

2   DICTIN.INP
Dictin

3   DICTIN.LST
Dictin

10   ENDFB.IN
Dictin

11   ENDFB.OUT
Dictin

Dictin

=======================================================================
Dictin

=======================================================================
Evalplot

Evalplot

PROGRAM
EVALPLOT
Evalplot

VERSION 75-1 (AUGUST
1975)
Evalplot

VERSION 76-1
(JULY 1976)
Evalplot

VERSION 77-1
(APRIL 1977)
Evalplot

VERSION 78-1
(JULY 1978)
Evalplot

VERSION 79-1
(FEBRUARY 1979)
Evalplot

VERSION 80-1
(JULY 1980)    *IBM
VERSION
Evalplot

VERSION 80-2 (DECEMBER
1980)
Evalplot

VERSION 81-1
(MARCH 1981)
Evalplot

VERSION 81-2
(AUGUST 1981)  *IMPROVED ZOOM
CAPABILITY
Evalplot

VERSION 82-1
(JANUARY 1982) *IMPROVED COMPUTER COMPATIBILITY       Evalplot

VERSION 83-1
(JANUARY 1983) *ELIMINATED COMPUTER DEPENDENT CODING. Evalplot

VERSION 83-2
(OCTOBER 1983) *ADDED PLOTTING OF HISTOGRAM DATA.     Evalplot

VERSION 84-1
(DECEMBER 1984)*ADDED PLOTS OF LEGENDRE COEFFICENTS   Evalplot

AS A FUNCTION OF ENERGY.
Evalplot

*ADDED SMALL PLOTTING MODE.
Evalplot

VERSION 85-1
(AUGUST 1985)  *FORTRAN-77/H VERSION
Evalplot

VERSION 86-1
(JANUARY 1986) *ENDF/B-VI FORMAT
Evalplot

VERSION 88-1
(JULY 1988)    *MAJOR
REVISION TO MAKE CODE EASILY
Evalplot

INTERFACEABLE TO ALMOST ANY PLOTTER.  Evalplot

*WARNING...INPUT PARAMETERS FROM BEEN  Evalplot

CHANGED (SEE, DESCRIPTION BELOW)      Evalplot

*COMPUTER INDEPENDENT SOFTWARE         Evalplot

CHARACTERS.
Evalplot

*COLOR PLOTS.
Evalplot

*MT NUMBER DEFINITIONS FROM DATA FILE  Evalplot

READ BY PROGRAM
Evalplot

*FORTRAN-77 REQUIRED (FORTRAN-H NO     Evalplot

SUPPORTED BY THIS PROGRAM).
Evalplot

*OPTION...INTERNALLY
DEFINE ALL I/O    Evalplot

FILE NAMES (SEE, SUBROUTINE FILEIO    Evalplot

FOR DETAILS).
Evalplot

*IMPROVED
BASED ON USER COMMENTS.      Evalplot

VERSION 89-1
(JANUARY 1989) *PSYCHOANALYZED BY PROGRAM FREUD TO    Evalplot

INSURE PROGRAM WILL NOT DO ANYTHING   Evalplot

CRAZY.
Evalplot

*UPDATED TO USE NEW PROGRAM CONVERT    Evalplot

KEYWORDS.
Evalplot

*ADDED LIVERMORE
CIVIC COMPILER
Evalplot

CONVENTIONS.
Evalplot

*FORTRAN-77/FORTRAN-H COMPATIBLE       Evalplot

*SPECIAL ENDF/B MATERIAL DEFINITIONS   Evalplot

(ZA.LT.1000) FROM DATA FILE READ      Evalplot

BY PROGRAM.
Evalplot

VERSION 89-2
(MARCH 1989)   *ADDED ENDF/B-V
AND VI MT
Evalplot

DEFINITIONS. PROGRAM WILL DETERMINE   Evalplot

ENDF/B FORMAT BASED ON MF=1,
Evalplot

MT=451 AND USE ASPPROPRIATE MT        Evalplot

DEFINITIONS. IF NO MF=1, MT=451       Evalplot

PROGRAM WILL USE ENDF/B-V
Evalplot

MT DEFINITIONS.
Evalplot

VERSION 89-3
(JUNE 1989)    *3
CHARACTER FONTS
Evalplot

VERSION 92-1
(JANUARY 1992) *COMPLETE REWRITE OF CODE
Evalplot

*ADDED PHOTON DATA, MF=23 AND 27       Evalplot

*ADDED
INCIDENT CHARGED PARTICLES      Evalplot

(IDENTIFIED IN PLOT TITLES)
Evalplot

*ADDED FORTRAN SAVE OPTION.
Evalplot

*UPDATED
BASED ON USER COMMENTS        Evalplot

*ADDED RETRIEVAL BY UP TO 100
Evalplot

MAT/MF/MT OR ZA/MF/MT RANGES
Evalplot

*WARNING...INPUT
PARAMETER FORMAT
Evalplot

HAS BEEN CHANGED...SEE DESCRIPTION    Evalplot

BELOW.
Evalplot

VERSION 92-2
(FEBRUARY 1992)*ADDED PHOTON SPECTRA, MF=15.
Evalplot

*ADDED MULTIPLICATION OF DISTRIBUTIONS Evalplot

IN MF=5 AND 15 BY PROBABILITY=YIELD.  Evalplot

*INCREASED PAGE SIZE TO 12000 POINTS   Evalplot

VERSION 92-3
(MAY 1992)
*CORRECTED DESCRIPTION OF INPUT
Evalplot

PARAMETERS AND EXAMPLE PROBLEMS.      Evalplot

*CORRECTED FOR ENDF/B-VI DEFINITION OF Evalplot

TEMPERATURE FROM MF=1/MT=451.
Evalplot

*CORRECTED LOGIC SO THAT EACH REQUEST  Evalplot

IS TREATED SEPARATELY TO CREATE A     Evalplot

PLOT, UNLESS REQUESTS ARE CHAINED     Evalplot

TOGETHER.
Evalplot

*ADDED VARIABLE CHARACTER SIZE INPUT.  Evalplot

VERSION 93-1
(MARCH 1993)   *INCREASED PAGE
SIZE FROM 12000
Evalplot

TO 210000
Evalplot

*INCREASED THE NUMBER OF ENERGIES      Evalplot

VS.
LEGENDRE COEFFICIENTS FROM
Evalplot

167 TO 7000
Evalplot

*UPDATED FOR ON SCREEN GRAPHICS
Evalplot

USING
THE LAHEY FORTRAN COMPILER.     Evalplot

VERSION 94-1
(JANUARY 1994) *VARIABLE ENDF/B DATA FILENAMES
Evalplot

TO ALLOW ACCESS TO FILE STRUCTURES    Evalplot

(WARNING
- INPUT PARAMETER FORMAT
Evalplot

HAS BEEN CHANGED)
Evalplot

*CLOSE ALL FILES BEFORE TERMINATING    Evalplot

(SEE, SUBROUTINE ENDIT)
Evalplot

VERSION 96-1
(JANUARY 1996) *COMPLETE RE-WRITE
Evalplot

*IMPROVED COMPUTER INDEPENDENCE
Evalplot

*ALL DOUBLE PRECISION
Evalplot

*UNIFORM TREATMENT OF ENDF/B I/O       Evalplot

*IMPROVED OUTPUT PRECISION
Evalplot

*DEFINED SCRATCH FILE NAMES
Evalplot

*ALL DOUBLE PRECISION
Evalplot

VERSION 97-1
(APRIL 1997)   *INCREASED PAGE
SIZE FROM 210000       Evalplot

TO 480,000
Evalplot

VERSION 99-1
(MARCH 1999)   *CORRECTED
CHARACTER TO FLOATING       Evalplot

POINT READ FOR MORE DIGITS
Evalplot

*UPDATED TEST FOR ENDF/B FORMAT        Evalplot

VERSION BASED ON RECENT FORMAT CHANGE Evalplot

*GENERAL IMPROVEMENTS BASED ON
Evalplot

USER FEEDBACK
Evalplot

VERS. 2000-1 (FEBRUARY
2000)*ADDED MF=10, ACTIVATION CROSS
Evalplot

SECTION PLOTS.
Evalplot

*INCREASED DIMENSIONS TO HANDLE MORE   Evalplot

SECTIONS
- UP TO 1,000
Evalplot

*GENERAL IMPROVEMENTS BASED ON
Evalplot

USER FEEDBACK
Evalplot

VERS. 2002-1
(Nov. 2002)    *OPTIONAL
INPUT PARAMETERTS
Evalplot

*OPTIONAL BLACK OR WHITE BACKGROUND    Evalplot

*COLOR POSTSCRIPT FILES
Evalplot

VERS. 2004-1
(MARCH 2004)   *ADDED INCLUDE FOR COMMON
Evalplot

*INCREASED PAGE SIZE TO 600,000
Evalplot

*INCREASED THE NUMBER OF ENERGIES      Evalplot

VS. LEGENDRE COEFFICIENTS FROM
Evalplot

7000 TO 20000
Evalplot

VERS. 2007-1
(JAN.  2007)   *CHECKED AGAINST ALL ENDF/B-VII.       Evalplot

*INCREASED PAGE SIZE TO 2,400,000      Evalplot

FROM 600,000.
Evalplot

VS. LEGENDRE COEFFICIENTS TO
Evalplot

80,000 FROM 20,000 (MUST BE 1/30      Evalplot

PAGE SIZE).
Evalplot

*ADDEED (N,REMAINDER) TO FIRST PLOT.   Evalplot

Evalplot

OWNED,
MAINTAINED AND DISTRIBUTED BY
Evalplot

------------------------------------
Evalplot

THE NUCLEAR DATA
SECTION
Evalplot

INTERNATIONAL ATOMIC
ENERGY AGENCY
Evalplot

P.O. BOX 100
Evalplot

A-1400, VIENNA, AUSTRIA
Evalplot

EUROPE
Evalplot

Evalplot

ORIGINALLY
WRITTEN BY
Evalplot

------------------------------------
Evalplot

DERMOTT E.
CULLEN
Evalplot

UNIVERSITY OF CALIFORNIA
Evalplot

LAWRENCE
LIVERMORE
NATIONAL LABORATORY
Evalplot

L-159
Evalplot

P.O. BOX 808
Evalplot

LIVERMORE, CA
94550
Evalplot

U.S.A.
Evalplot

TELEPHONE  925-423-7359
Evalplot

E. MAIL    [email-masked]
Evalplot

WEBSITE
HTTP://WWW.LLNL.GOV/CULLEN1
Evalplot

Evalplot

AUTHORS
MESSAGE
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---------------
Evalplot

THE REPORT
DESCRIBED ABOVE IS THE LATEST PUBLISHED DOCUMENTATION   Evalplot

FOR THIS
PROGRAM. HOWEVER, THE COMMENTS BELOW SHOULD BE CONSIDERED Evalplot

THE LATEST
DOCUMENTATION INCLUDING ALL RECENT IMPROVEMENTS. PLEASE Evalplot

READ ALL OF
THESE COMMENTS BEFORE IMPLEMENTATION, PARTICULARLY     Evalplot

THE COMMENTS
CONCERNING MACHINE DEPENDENT CODING.
Evalplot

Evalplot

AT THE PRESENT
TIME WE ARE ATTEMPTING TO DEVELOP A SET OF COMPUTER Evalplot

INDEPENDENT
PROGRAMS THAT CAN EASILY BE IMPLEMENTED ON ANY ONE     Evalplot

OF A WIDE
VARIETY OF COMPUTERS. IN ORDER TO ASSIST IN THIS PROJECT Evalplot

IT WOULD BE
APPECIATED IF YOU WOULD NOTIFY THE AUTHOR OF ANY       Evalplot

COMPILER
DIAGNOSTICS, OPERATING PROBLEMS OR SUGGESTIONS ON HOW TO  Evalplot

IMPROVE THIS PROGRAM.
HOPEFULLY, IN THIS WAY FUTURE VERSIONS OF    Evalplot

THIS PROGRAM
WILL BE COMPLETELY COMPATIBLE FOR USE ON YOUR
Evalplot

COMPUTER.
Evalplot

Evalplot

PURPOSE
Evalplot

-------
Evalplot

THIS PROGRAM IS
DESIGNED TO READ EVALUATED DATA FROM THE ENDF/B    Evalplot

FORMAT AND TO
PLOT THE DATA. THE USER MAY SELECT CROSS SECTIONS,   Evalplot

PARAMETERS (E.G.
NU-BAR, MU-BAR, ETC.), ANGULAR DISTRIBUTIONS      Evalplot

AND/OR ENERGY
DISTRIBUTIONS TO BE PLOTTED.                         Evalplot

Evalplot

IN THE FOLLOWING
FOR SIMPLICITY THE ENDF/B TERMINOLOGY--ENDF/B     Evalplot

TAPE--WILL BE
USED. IN FACT THE ACTUAL MEDIUM MAY BE TAPE, CARDS,  Evalplot

DISK OR ANY
OTHER MEDIUM.
Evalplot

Evalplot

ON WHAT
COMPUTERS WILL THE PROGRAM RUN
Evalplot

------------------------------------------------------------------
Evalplot

THE PROGRAM HAS
BEEN IMPLEMENTED ON A WIDE VARIETY OF COMPUTERS    Evalplot

FROM THE ONE
EXTREME OF LARGE MAINFRAME CRAY AND IBM COMPUTERS     Evalplot

TO THE OTHER
EXTREME OF SUN TERMINALS AND IBM PERSONAL COMPUTERS.  Evalplot

THE PROGRAM IS
DESIGNED TO RUN ON VIRTUALLY ANY COMPUTER. FOR      Evalplot

SPECIAL
CONSIDERATIONS SEE THE SECTIONS BELOW ON,
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(1) COMPUTER
DEPENDENT CODING
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(2)
PLOTTER/GRAPHICS TERMINAL INTERFACE
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ON WHAT PLOTTERS
WILL THE PROGRAM RUN
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------------------------------------------------------------------
Evalplot

THE PLOTTER MAY
USE UNITS OF INCHES, CENTIMETERS, MILLIMETERS,     Evalplot

VIRTUALLY
ANYTHING. INTERNALLY THE PROGRAM WILL DEFINE PLOTS IN    Evalplot

APPROXIMATELY A4
OR 8-1/2 BY 11 INCH FORMAT. AS PART OF THE
Evalplot

INPUT THE USER
DEFINES THE ACTUAL SIZE OF THE PLOT IN THE UNITS    Evalplot

(I.E., INCHES,
CENTIMETERS, MILLIMETERS, WHATEVER) OF THE REAL     Evalplot

PLOT. THE PLOT
IS TRANSFORMED TO THE SIZE OF THE LOCAL PLOTTER     Evalplot

AND OUTPUT.
USING THIS CONVENTION THIS PROGRAM SHOULD BE EASY      Evalplot

TO INTERFACE TO
VIRTUALLY ANY PLOTTER OR GRAPHICS TERMINAL.
Evalplot

Evalplot

GRAPHICS
INTERFACE
Evalplot

------------------------------------------------------------------
Evalplot

THIS PROGRAM
USES A SIMPLE CALCOMP LIKE GRAPHICS INTERFACE WHICH   Evalplot

REQUIRES ONLY 3
SUBROUTINES...PLOTS, PLOT AND PEN (DESCRIBED IN    Evalplot

DETAIL BELOW).
ALL CHARACTERS AND SYMBOLS ARE DRAWN USING TABLES   Evalplot

OF PEN STROKES
(SUPPLIED WITH THIS PROGRAM). USING THIS METHOD     Evalplot

THE PROGRAM
SHOULD BE SIMPLE TO INTERFACE TO VIRTUALLY ANY PLOTTER Evalplot

OR GRAPHICS
TERMINAL AND THE APPEARANCE AND LAYOUT OF THE PLOTS    Evalplot

SHOULD BE
INDEPENDENT OF WHICH PLOTTER IS USED.
Evalplot

Evalplot

PROGRAM
IDENTIFICATION
Evalplot

----------------------
Evalplot

AS DISTRIBUTED
THE FIRST FRAME OF PLOTTED OUTPUT WILL DOCUMENT     Evalplot

THE PROGRAM
NAME, VERSION AND INSTALLATION. THIS INFORMATION IS    Evalplot

STORED AS DATA
IN THE ARRAY VERSES NEAR THE BEGINNING OF
Evalplot

SUBROUTINE
FRAME1. IF YOU WISH TO CUSTOMIZE THE OUTPUT TO IDENTIFY Evalplot

YOUR
INSTALLATION CHANGE THE LAST TWO LINES OF THE ARRAY VERSES.   Evalplot

Evalplot

SIZE OF
PLOTS
Evalplot

-------------
Evalplot

THE PROGRAM HAS
A BUILT-IN DEFAULT SIZE TO MAKE EACH PLOT 13.50    Evalplot

BY 10.24 INCHES.
THIS SIZE WAS SELECTED ASSUMING THAT THE
Evalplot

RESOLUTION OF
THE PLOTTER IS 1024 RASTER POINTS PER INCH. THE      Evalplot

USER MAY CHANGE
THE SIZE OF THE PLOT BY SPECIFYING ANY REQUIRED    Evalplot

SIZE ON THE
FIRST INPUT LINE. IN PARTICULAR FOR USE ON ANY PLOTTER Evalplot

THAT USES
CENTIMETERS INSTEAD OF INCHES THE USER MAY MERELY
Evalplot

SPECIFY THE
REQUIRED SIZE OF THE PLOT IN CENTIMETERS (E.G., TO     Evalplot

OBTAIN A 13.50
BY 10.24 INCH PLOT, THE USER NEED ONLY SPECIFY      Evalplot

34.3 BY 26 ON
THE FIRST INPUT LINE...ASSUMING 2.54 CENTIMETERS PER Evalplot

INCH, OR 343 BY
260 FOR MILLIMETERS..ASSUMING 25.4 MILLIMETERS     Evalplot

PER INCH).
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CHARACTER
SIZE
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--------------
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THE PLOT HAS A
BUILT-IN CHARACTER SIZE WHICH HAS BEEN DEFINED FOR  Evalplot

COMPATIBILITY
WITH THE BUILT-IN PLOT SIZE. IF THE USER SPECIFIES   Evalplot

BY INPUT A DIFFERENT
PLOT SIZE, THE PROGRAM WILL AUOTMATICALLY     Evalplot

SCALE THE SIZE
OF ALL CHARACTERS BY THE RATIO OF THE Y SIZE OF THE Evalplot

PLOT SPECIFIED
BY THE USER TO THE BUILT-IN Y SIZE OF PLOTS (E.G.,  Evalplot

FOR PLOTS WHICH
ARE ONLY 5.12 HIGH (Y DIRECTION) ALL CHARACTERS    Evalplot

WILL BE SCALED
TO BE ONLY 1/2 THE CHARACTER SIZE ON PLOTS WHICH    Evalplot

ARE 10.24 HIGH
(10.24 = THE BUILT-IN SIZE). NOTE, CHANGES IN THE   Evalplot

X SIZE OF THE PLOT
WILL NOT HAVE ANY EFFECT ON THE CHARACTER SIZE  Evalplot

(E.G., FOR A
LONG PLOT, 30 BY 10.24 THE CHARACTER SIZE WILL BE THE Evalplot

THE SAME AS ON A
13.50 BY 10.24 PLOT).
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PLOT PER
FRAME
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--------------
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BY INPUT THE
USER CAN SPECIFY NOT ONLY THE ACTUAL SIZE OF THE      Evalplot

LOCAL PLOTTER,
BUT ALSO HOW MANY PLOTS SHOULD APPEAR ON EACH       Evalplot

FRAME. THIS IS
DONE BY SPECIFYING THE LAYOUT OF A FRAME IN TERMS   Evalplot

OF THE NUMBER OF
PLOTS IN THE X AND Y DIRECTION. FOR EXAMPLE BY    Evalplot

SPECIFYING THAT
EACH FRAME BE DIVIDED INTO 3 PLOTS IN THE X
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DIRECTION AND 2
PLOTS IN THE Y DIRECTION, EACH FRAME WILL CONTAIN  Evalplot

UP TO 6 PLOTS (3
X 2). INTERNALLY EACH PLOT WILL BE GENERATED TO   Evalplot

STANDARD A4
SIZE, AS DESCRIBED ABOVE, AND THEN ON OUTPUT SCALED    Evalplot

TO THE NUMBER OF
PLOTS PER FRAME SPECIFIED BY THE USER INPUT.      Evalplot

Evalplot

ENDF/B
FORMAT
Evalplot

-------------
Evalplot

THIS PROGRAM
ONLY USES THE ENDF/B BCD OR CARD IMAGE FORMAT (AS     Evalplot

OPPOSED TO THE
BINARY FORMAT) AND CAN HANDLE DATA IN ANY VERSION   Evalplot

OF THE ENDF/B
FORMAT (I.E., ENDF/B-I, II,III, IV, V OR VI FORMAT). Evalplot

Evalplot

IT IS ASSUMED
THAT THE DATA IS CORRECTLY CODED IN THE ENDF/B       Evalplot

FORMAT AND NO
ERROR CHECKING IS PERFORMED. IN PARTICULAR IT IS     Evalplot

ASSUMED THAT THE
MAT, MF AND MT ON EACH LINE IS CORRECT. SEQUENCE  Evalplot

NUMBERS (COLUMNS
76-80) ARE IGNORED. FORMAT OF SECTION MT=452, 455 Evalplot

OF MF=1, AND ALL
SECTIONS OF MF=3, 4 AND 5 MUST BE CORRECT. ALL    Evalplot

OTHER SECTION OF
DATA ARE SKIPPED AND AS SUCH THE OPERATION OF     Evalplot

THIS PROGRAM IS
INSENSITIVE TO THE CORRECTNESS OR INCORRECTNESS    Evalplot

OF ALL OTHER
SECTIONS.
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INTERPOLATION
LAW
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-----------------
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EACH TABLE OF
DATA MAY USE EITHER COMPLETELY HISTOGRAM OR
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COMPLETELY
LINEAR INTERPOLATION LAW (THE TWO INTERPOLATION LAWS    Evalplot

CANNOT BE MIXED
TOGETHER IN ONE TABLE). EITHER OF THESE TWO
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REPRESENTATIONS
WILL BE STORED IN CORE IN LINEARLY INTERPOLABLE    Evalplot

FORM. IF THIS
PROGRAM FINDS ANY DATA THAT USES ANY OTHER
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INTERPOLATION
LAW IT WILL PRINT AN ERROR MESSAGE AND PLOT THE      Evalplot

TABLE AS IF IT
WERE LINEARLY INTERPOLABLE. THE ONLY ERROR THAT     Evalplot

WILL RESULT IN
THE PLOT WILL BE IN THE CURVE FOLLOWED BETWEEN      Evalplot

TABULATED
POINTS. PROGRAM LINEAR (UCRL-50400, VOL. 17, PART A)     Evalplot

MAY BE USED TO
CONVERT CROSS SECTIONS TO LINEARLY INTERPOLABLE     Evalplot

FORM. PROGRAM
LEGEND CAN BE USED FOR ANGULAR DISTRIBUTIONS AND     Evalplot

PROGRAM ENERGY
CAN BE USED FOR SECONDARY ENERGY DISTRIBUTIONS.     Evalplot

Evalplot

REACTION
INDEX
Evalplot

--------------
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THIS PROGRAM
DOES NOT USE THE REACTION INDEX WHICH IS GIVEN IN     Evalplot

SECTION MF=1,
MT=451 OF EACH EVALUATION.
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PAGE SIZE
Evalplot

---------
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ONLY ONE PAGE OF
DATA = 600000 DATA POINTS - IS KEPT IN CORE AT    Evalplot

ANY GIVEN TIME.
IF THERE IS MORE THAN THIS MANY POINTS THEY WILL   Evalplot

BE KEPT ON A
SCRATCH FILE AND LOADED INTO CORE AS NEEDED.
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Evalplot

TO CHANGE THE
PAGE SIZE,
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Evalplot

1) CHANGE  600000 TO THE NEW PAGE SIZE                             Evalplot

2) CHANGE
1200000 TO TWO TIMES THE NEW PAGE SIZE
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Evalplot

SECTION
SIZE
Evalplot

------------
Evalplot

SINCE THIS
PROGRAM USES A LOGICAL PAGING SYSTEM THERE IS NO LIMIT  Evalplot

TO THE NUMBER OF
POINTS IN ANY SECTION, E.G., THE TOTAL CROSS      Evalplot

SECTION MAY BE
REPRESENTED BY 200,000 DATA POINTS.
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Evalplot

THE ONLY
EXCEPTION TO THIS RULE IS THAT EACH TABLE OF DATA WHICH   Evalplot

USES A HISTOGRAM
INTERPOLATION LAW CANNOT EXCEED HALF THE SIZE     Evalplot

OF THE IN CORE
PAGE (PRESENTLY 600000/2=300000) WHICH IS ADEQUATE  Evalplot

FOR ALMOST ALL
HISTOGRAM (E.G. MULTIGROUP) REPRESENTATIONS OF      Evalplot

A SINGLE TABLE
(E.G. REACTION).
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WHAT DATA CAN BE
PLOTTED
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------------------------
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THIS CODE CAN
PLOT VIRTUALLY ANY NEUTRON OR PHOTON CROSS SECTIONS  Evalplot

(MF=3 OR 23) AND
ANY TABULATED ANGULAR OR ENERGY DISTRIBUTIONS OR  Evalplot

LEGENDRE
COEFFICIENTS. WHAT IS ACTUALLY PLOTTED DEPENDS ON WHAT    Evalplot

DATA IS SELECTED
BY THE USER.
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SELECTION OF
DATA
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-----------------
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DATA TO BE
PLOTTED IS SPECIFIED BY INPUTTING UP TO 100 MAT/MF/MT   Evalplot

RANGES OR UP TO
100 ZA/MF/MT RANGES. IN ADDITION FOR EACH RANGE    Evalplot

THE USER MAY
SPECIFY AN X RANGE (USUALLY ENERGY) AND THE TYPE OF   Evalplot

DATA TO BE
PLOTTED (SEE: THE DESCRIPTION OF TYPES, BELOW).
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Evalplot

THE X RANGE FOR
MF = 1, 3, 23 AND 27 AND MF = 4 LEGENDRE
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COEFFICIENTS
WILL BE USED AS THE X LIMITS OF THE PLOTS, E.G.,      Evalplot

PLOT ENERGY
DEPENDENT CROSS SECTIONS BETWEEN 1 AND 20 MEV.         Evalplot

Evalplot

THE X RANGE FOR
MF = 4 AND 5 WILL BE USED TO ONLY SELECT ANGULAR   Evalplot

AND ENERGY
DISTRIBUTION FOR WHICH THE INCIDENT NEUTRON ENERGY      Evalplot

IS IN THE X
RANGE. E.G., ONLY PLOT ANGULAR DISTRIBUTIONS WHERE     Evalplot

THE INCIDENT
NEUTRON ENERGY IS 1 TO 20 MEV.
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INTERACTIVE VS. BATCH
MODE
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--------------------------
Evalplot

VERSION 92-1 AND
LATER VERSIONS OF THIS CODE ONLY USE A BATCH      Evalplot

MODE WHERE ALL
REQUESTS ARE READ AND PROCESSED. EARLIER VERSIONS   Evalplot

OF THIS CODE HAD
BOTH AN INTERACTIVE MODE (WHERE REQUESTS WHERE    Evalplot

READ AND
EXECUTED ONE AT A TIME) AND A BATCH MODE. INTERACTIVE     Evalplot

MODE HAS BEEN
DROPPED AND WILL NOT TO REINTRODUCED UNLESS THE      Evalplot

AUTHOR IS
INFORMED BY USERS THAT THEY WERE USING THE INTERACTIVE   Evalplot

MODE.
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PLOT LAYOUT
Evalplot

-----------
Evalplot

VERSION 92-1 AND
LATER VERSIONS OF THIS CODE WILL PLOT ALL
Evalplot

CURVES ON A
SINGLE PLOT. EARLIER VERSIONS OF THIS CODE ALLOWED     Evalplot

THE OPTION TO
HAVE,
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MULTIPLE PLOTS -
INDIVIDUAL SCALING
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MULTIPLE PLOTS -
COMMON SCALING
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SINGLE PLOT
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MULTILE PLOTS
PER PLOT HAVE BEEN DROPPED AND WILL NOT BE
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REINTRODUCED
UNLESS IT IS DEMONSTRATED TO THE AUTHOR THAT THEY     Evalplot

ARE OF PRACTICAL
USE IN SOME APPLICATION.
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Evalplot

PROCESSING OF
DATA
Evalplot

------------------
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IN THE CASE OF
NEUTRON AND PHOTON CROSS SECTIONS (MF=3 OR 23)      Evalplot

AND PARAMETERS (MF=1 OR
27) ALL DATA IN A FILE (MF) IS READ
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GROUPED TOGETHER
BY TYPE (AS EXPLAINED BELOW) AND PLOTTED.
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Evalplot

IN THE CASE OF
ANGULAR AND ENERGY DISTRIBUTIONS (MF=4 OR 5) ONLY   Evalplot

ONE SECTION OF
DATA AT A TIME IS READ AND PLOTTED.
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TYPES OF DATA (MF=1,
3, 23 AND 27 ONLY)
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---------------------------------------
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THESE DATA ARE
DIVIDED INTO UP TO 18 TYPES AND EACH TYPE OF
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DATA IS GROUPED
TOGETHER AND PLOTTED (IF THE DATA IS ACTUALLY      Evalplot

PRESENT).
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Evalplot

WHAT TYPE OF
DATA IS ACTUALLY PLOTTED CAN BE CONTROLLED BY USER    Evalplot

INPUT EITHER
BASED ON SELECTED MAT/MF/MT OR ZA/MF/MT RANGES OR     Evalplot

BY EXPLICITLY
SELECTING ONLY ONE TYPE OF DATA IS TO BE PLOTTED     Evalplot

(SEE THE
DESCRIPTION OF INPUT BELOW).
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Evalplot

SIMPLE
REQUESTS
Evalplot

---------------
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GENERALLY EACH
MAT/MF/MT OR ZA/MF/MT REQUESTED IS TREATED
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SEPERATELY AND
THE SPECIFIED DATA IS GROUPED BY TYPE AND PLOTTED.  Evalplot

FOR EXAMPLE, THE
USER MAY SPECIFY USING ONE REQUEST THAT ALL       Evalplot

TYPES OF DATA BE
PLOTTED OVER THE ENTIRE
ENERGY RANGE
AND USE
Evalplot

A SECOND REQUEST
TO SPECIFY THAT ONE PARTICULAR TYPE OF DATA       Evalplot

BE PLOTTED OVER
A SPECIFIC ENERGY RANGE.
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Evalplot

CHAINED
REQUESTS
Evalplot

----------------
Evalplot

REQUESTS MAY
ALSO BE CHAINED TOGETHER (SEE, THE DESCRIPTION OF     Evalplot

INPUT BELOW),
WHERE A NUMBER OF REQUESTS MAY BE USED TO SELECT     Evalplot

DATA, BUT ONLY
THE LAST REQUEST IN A CHAIN WILL CAUSE ALL SELECTED Evalplot

DATA TO BE PLOTTED.
CHAINED REQUESTED ARE INDICATED ON INPUT BY    Evalplot

A SERIES OF
REQUESTS FOR DATA TYPE = -1, EXCEPT FOR THE LAST       Evalplot

REQUEST OF THE
CHAIN, WHICH MUST SPECIFY A TYPE DATA = 0 (ALL)     Evalplot

OR A POSITIVE
NUMBER. UNLIKE SIMPLE REQUESTS, WHERE EACH WILL      Evalplot

PRODUCE ONE OR
MORE PLOTS, WITH CHAINED REQUESTS THE ENTIRE
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SERIES OF
CHAINED REQUESTS WILL BE TREATED AS A SINGLE REQUEST     Evalplot

AND WILL PRODUCE
ONE OR MORE PLOTS.
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Evalplot

FOR EXAMPLE,
DATA TYPE = 1 WILL NORMALLY INCLUDE,
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MT =   1 - TOTAL
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=   2 - ELASTIC
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=   4 - TOTAL
INELASTIC
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=   5 -
(N,REMAINDER)
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=  18 - FISSION
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= 102 - CAPTURE
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IF YOU WISH TO
EXCLUDE TOTAL INELASTIC FROM A PLOT YOU NEED ONLY   Evalplot

SPECIFY TWO
CHAINED REQUESTS THE FIRST TO SELECT MT = 1 THROUGH    Evalplot

2 (TO INCLUDE
TOTAL AND ELASTIC) AND A SECOND TO INCLUDE MT = 18   Evalplot

THROUGH 102. THE
FIRST REQUEST SHOULD SPECIFY DATA TYPE = -1 AND   Evalplot

SECOND 1 (THIS
WILL CHAIN THE 2 REQUESTS TOGETHER, SO THAT MT =1   Evalplot

THROUGH 2, AND
MT = 18 THROUGH 102 ALL APPEAR ON THE SAME PLOT).   Evalplot

SINCE MT = 4
(TOTAL INELASTIC) IS NOT REQUESTED IT WILL NOT BE     Evalplot

PLOTTED.
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DEFINITION OF 18
DATA TYPES
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------------------------------------------------------------------
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NEUTRONS (MF =
3)
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-----------------
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(1) TOTAL,
ELASTIC, CAPTURE, FISSION, TOTAL INELASTIC, REMAINDER   Evalplot

(2) (N,2N),
(N,3N) AND (N,N' CHARGED PARTICLE)
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(3) (N,CHARGED
PARTICLE)
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(4) PARTICLE
PRODUCTION (PROTON, DEUTERON, ETC.) AND DAMAGE
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(5) TOTAL,
FIRST, SECOND, ETC. CHANCE FISSION.
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(6) TOTAL
INELASTIC, INELASTIC DISCRETE LEVELS AND CONTINUUM       Evalplot

(7) (N,P) TOTAL
AND LEVELS (ONLY IF LEVELS ARE GIVEN)
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(8) (N,D) TOTAL
AND LEVELS (ONLY IF LEVELS ARE GIVEN)
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(9) (N,T) TOTAL
AND LEVELS (ONLY IF LEVELS ARE GIVEN)
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(10) (N,HE-3)
TOTAL AND LEVELS (ONLY IF LEVELS ARE GIVEN)
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(11) (N,ALPHA)
TOTAL AND LEVELS (ONLY IF LEVELS ARE GIVEN)
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(12) PARAMETERS
MU-BAR, XI AND GAMMA
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(13) NU-BAR -
TOTAL, PROMPT AND DELAYED
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PHOTONS  (MF=23 AND 27)
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-----------------------
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(14) TOTAL,
COHERENT, INCOHERENT, TOTAL PHOTOELECTRIC, TOTAL       Evalplot

PAIR PRODUCTION
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(15) TOTAL AND
SUBSHELL PHOTOELECTRIC
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(16) TOTAL,
NUCLEAR AND ELECTRON PAIR PRODUCTION
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(17) COHERENT
FORM FACTOR AND INCOHERENT SCATTERING FUNCTION       Evalplot

(18) REAL AND
IMAGINARY SCATTERING FACTORS
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IDENTIFICATION
OF DATA
Evalplot

----------------------
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ALL PLOTS
IDENTIFY THE TARGET, E.G., U-238 AND UNITS OF THE X AND  Evalplot

Y AXIS, E.G., X
= ENERGY (MEV) OR COSINE (LAB), ETC., Y = CROSS    Evalplot

SECTION (BARNS)
OR PROBABILITY/COSINE, ETC.
Evalplot

Evalplot

FOR TYPES OF
DATA (MF=1, 3, 23 AND 27) DIFFERENT REACTIONS (MT)    Evalplot

ARE GROUPED
TOGETHER TO APPEAR ON THE SAME PLOT. THE TITLE AT      Evalplot

THE TOP OF THE
PLOT WILL IDENTIFY THE TYPE OF DATA BEING PLOTTED   Evalplot

AND THE LEGEND
BOX WITHIN THE PLOT WILL IDENTIFY EACH REACTION.    Evalplot

Evalplot

FOR ANGULAR AND
ENERGY DISTRIBUTIONS (MF=4 OR 5) EACH PLOT WILL    Evalplot

CONTAIN DATA FOR
A SINGLE REACTION (MT) AND DIFFERENT INCIDENT     Evalplot

NEUTRON
ENERGIES. THE TITLE AT THE TOP OF THE PLOT WILL IDENTIFY   Evalplot

THE REACTION AND
THE LEGEND BOX WITHIN THE PLOT WILL IDENTIFY      Evalplot

THE INCIDENT
ENERGY.
Evalplot

Evalplot

FOR LEGENDRE
COEFFICIENT THE DATA IN ENDF/B FORMAT WILL BE
Evalplot

INVERTED IN
ORDER TO PRESENT EACH LEGENDRE COEFFICIENT VERSUS      Evalplot

INCIDENT ENERGY.
THE TITLE AT THE TOP OF THE PLOT WILL IDENTIFY    Evalplot

THE REACTION AND
THE LEGEND BOX WITHIN THE PLOT WILL IDENTIFY      Evalplot

THE LEGENDRE
ORDER.
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Evalplot

INPUT FILES
Evalplot

-----------
Evalplot

UNIT  DESCRIPTION
Evalplot

----  -----------
Evalplot

2   INPUT LINES (BCD -
80 CHARACTERS/RECORD)
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9   MT DEFINITIONS (BCD
- 80 CHARACTERS/RECORD)
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10   ENDF/B DATA (BCD -
80 CHARACTERS/RECORD)
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12   SOFTWARE CHARACTERS
(BCD - 80 CHARACTERS/RECORD)
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OUTPUT
FILES
Evalplot

------------
Evalplot

UNIT  DESCRIPTION
Evalplot

----  -----------
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3   OUTPUT REPORT (BCD -
120 CHARACTERS/RECORD)
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16   PLOTTING UNIT
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SCRATCH
FILES
Evalplot

-------------
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UNIT  DESCRIPTION
Evalplot

----  -----------
Evalplot

11  SCRATCH FILE (BINARY -
960000 WORDS/RECORD = 2*PAGE SIZE)    Evalplot

Evalplot

OPTIONAL
STANDARD FILE NAMES (SEE SUBROUTINE FILIO1 AND FILIO2)    Evalplot

---------------------------------------------------------------    Evalplot

UNIT  FILE NAME
Evalplot

----  ----------
Evalplot

2   EVALPLOT.INP
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3   EVALPLOT.LST
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9   MT.DAT
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10   ENDFB.IN    (OR AS INPUT PARAMETER)
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11   (SCRATCH)
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12   PLOT.CHR
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16   (PLOTTING UNIT...USUALLY A
DUMMY)
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INPUT
PARAMETERS
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----------------
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LINE COLUMNS
FORMAT  DESCRIPTION
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---- -------
------  -----------
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1   1-11   E11.4  LOWER X LIMIT OF PLOTTER
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12-22   E11.4  UPPER X LIMIT OF PLOTTER
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23-33   E11.4  LOWER Y LIMIT OF PLOTTER
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34-44   E11.4  UPPER Y LIMIT OF PLOTTER
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45-55    I11   NUMBER OF PLOTS PER FRAME IN X DIRECTION      Evalplot

56-66    I11   NUMBER OF PLOTS PER FRAME IN Y DIRECTION      Evalplot

67-70    F4.1  CHARACTER SIZE MULTIPLIER
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= 0 OR 1    - NORMAL CHARACTER SIZE
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= OTHERWISE - CHARACTERS SCALED BY THIS       Evalplot

FACTOR.
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2   1-60    A60   ENDF/B DATA FILENAME
Evalplot

(LEAVE BLANK FOR STANDARD = ENDFB.IN)
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3   1-11    I11   RETRIEVAL CRITERIA
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=
0 - MAT
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= 1 - ZA
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12-22    I11   TYPE OF GRID
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=
0 - TICK MARKS ON BORDER
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= 1 - SOLID AT COARSE INTERVALS
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= 2 - DASHED AT COARSE INTERVALS
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= 3 - SOLID AT FINE INTERVALS
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= 4 - DASHED AT FINE INTERVALS
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= 5 - SOLID COARSE/DASHED FINE GRID
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23-33    I11   SHOULD BORDER BE PLOTTED ON EACH
PLOT
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= 0 - NO
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= 1 - YES
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34-44    I11   LINE THICKNESS                                Evalplot

= 0 -  5 = BORDER/CURVES/CHARACTERS
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=-1 - -5 = BORDER/CURVES (NOT CHARACTERS)     Evalplot

NOTE, THE GRID IS NEVER THICK.     Evalplot

45-55    I11   SHOULD TEMPERATURE BE PLOTTED.
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= 0 - YES
Evalplot

= 1 - NO
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56-66   E11.4  ALLOWABLE RATIO OF PLOT Y RANGE MAXIMUM
TO    Evalplot

MINIMUM - IF THIS RATIO IS EXCEEDED THE Y     Evalplot

RANGE MINIMUM WILL BE CHANGED TO THE Y RANGE  Evalplot

MAXIMUM TIMES THIS RATIO.
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IF THIS RATIO IS NOT POSITIVE, IT IS
Evalplot

INTERPRETED TO MEAN NO LIMIT ON Y RANGE.      Evalplot

67-70    I4    BACKGROUND COLOR
Evalplot

= 0
= BLACK
Evalplot

= OTHERWISE = WHITE
Evalplot

4-N   1- 6    I6    LOWER MAT OR ZA LIMIT
Evalplot

7- 8    I2    LOWER MF LIMIT
Evalplot

9-11    I3    LOWER
MT LIMIT
Evalplot

11-22   E11.4  LOWER X LIMIT (USUALLY ENERGY) - EV
Evalplot

23-28    I6    UPPER MAT OR ZA LIMIT
Evalplot

29-30    I2    UPPER MF LIMIT
Evalplot

31-33    I3    UPPER
MT LIMIT
Evalplot

34-44   E11.4  UPPER X LIMIT (USUALLY ENERGY) - EV
Evalplot

45-55   I11    TYPE OF DATA TO RETRIEVE AND
PLOT
Evalplot

=  -1  - CHAIN THIS REQUEST TO THE NEXT
ONE   Evalplot

=   0  - ALL
Evalplot

= 1-18 - TYPE AS SPECIFIED ABOVE
Evalplot

Evalplot

THERE MAY BE UP
100 MAT/MF/MT OR ZA/MF/MT REQUEST
RANGES. INPUT    Evalplot

MUST BE
TERMINATED BY A BLANK LINE.
Evalplot

Evalplot

IF X LIMITS ARE
NOT SPECIFIED (I.E., LOWER AND UPPER X LIMIT = 0)  Evalplot

THIS WILL BE
INTERPRETED TO MEAN NO LIMIT AND ALL DATA WILL BE     Evalplot

PLOTTED OVER
THEIR ENTIRE ENERGY RANGE,
I.E., YOU NEED NOT
Evalplot

KNOW AND SPECIFY
THE ACTUAL ENERGY LIMITS OF THE DATA.
Evalplot

Evalplot

EXAMPLE
DEFINITION OF PLOTTER
Evalplot

-----------------------------
Evalplot

THE FIRST INPUT
LINE DEFINES THE DIMENSIONS OF THE PLOTTER BEING   Evalplot

USED IN ANY
UNITS (INCHES, CENTIMETERS, MILLIMETERS, ANYTHING)     Evalplot

WHICH APPLY TO
THE PLOTTER. IN ADDITION THE FIRST LINE DEFINES     Evalplot

HOW MANY PLOTS
SHOULD APPEAR ON EACH FRAME. THE PLOTTING AREA      Evalplot

DEFINED ON THE
FIRST INPUT LINE MAY BE SUBDIVIDED INTO ANY NUMBER  Evalplot

OF PLOTS IN THE
X AND Y DIRECTION. FOR EXAMPLE, TO PRODUCE A       Evalplot

SERIES OF FRAMES
EACH CONTAINING 3 PLOTS IN THE X DIRECTION AND    Evalplot

2 PLOTS IN THE Y
DIRECTION (6 PLOTS PER FRAME) COLUMN 45-55 OF     Evalplot

THE FIRST INPUT
LINE SHOULD BE 3 AND COLUMNS 56-66 SHOULD BE 2.    Evalplot

Evalplot

IF THE LOCAL
PLOTTER USES DIMENSIONS OF INCHES IN ORDER TO OBTAIN  Evalplot

10 X 10 INCH
FRAMES WITH 3 X 2 PLOTS PER FRAME THE FIRST INPUT     Evalplot

LINE SHOULD
BE,
Evalplot

Evalplot

0.0
10.0
0.0
10.0
3
2
Evalplot

Evalplot

IF THE LOCAL
PLOTTER USES DIMENSION OF MILLIMETERS THE SAME
Evalplot

PHYSICAL SIZE
PLOT MAY BE OBTAINED IF THE FIRST INPUT LINE IS,     Evalplot

Evalplot

0.0
254.0
0.0    254.0
3
2
Evalplot

Evalplot

FOR SIMPLICITY
THE FOLLOWING EXAMPLE INPUTS WILL NOT DISCUSS THE   Evalplot

PHYSICAL
DIMENSIONS OF THE PLOTTER AND THE FIRST INPUT LINE WILL   Evalplot

IN ALL CASES
INDICATE 10 X 10 INCH PLOTS WITH ONLY 1 PLOT PER      Evalplot

FRAME.
Evalplot

Evalplot

ALL OF THE
FOLLOWING EXAMPLE WILL USE,
Evalplot

1) A DASHED
GRID
(SECOND LINE, COLS. 12-22 = 2)
Evalplot

2) NO
BORDER
(SECOND LINE, COLS. 23-33 = 0)
Evalplot

3) LINE
THICKNESS -2
(SECOND LINE, COLS. 34-44 =-2)
Evalplot

4) TEMPERATURE
ON PLOTS   (SECOND LINE, COLS.
45-55 = 0)
Evalplot

5) NO Y RANGE
LIMIT
(SECOND LINE, COLS. 56-66 = 0.0)
Evalplot

Evalplot

EXAMPLE INPUT
NO. 1
Evalplot

-------------------
Evalplot

FOR ALL THORIUM
AND URANIUM ISOTOPES PLOT NEUTRON CROSS SECTIONS   Evalplot

ENTIRE ENERGY
RANGE. IN ADDITION PLOT
TYPE 1 DATA, MAJOR NEUTRON
Evalplot

CROSS SECTIONS
OVER THE ENERGY RANGE 1 EV TO 1 KEV. USE THE
Evalplot

STANDARD
FILENAME (ENDFB.IN) FOR THE ENDF/B DATA. THE FOLLOWING    Evalplot

6 INPUT LINES
ARE REQUIRED,
Evalplot

Evalplot

0.0       10.0       0.0       10.0
3
2
Evalplot

ENDFB.IN
Evalplot

1
2
0
-2
0 0.0
Evalplot

90000 3  0
90999 3999
0
Evalplot

90000 3  0 1.00000+ 090999
3999 1.00000+ 3
1
Evalplot

(BLANK
LINE MUSE FOLLOW LAST REQUEST)
Evalplot

Evalplot

EXAMPLE INPUT
NO. 2
Evalplot

-------------------
Evalplot

PLOT FE-56
ELASTIC AND INELASTIC ANGULAR DISTRIBUTIONS BETWEEN     Evalplot

1 AND 20 MEV.
THE FOLLOWING 6 INPUT LINES ARE REQUIRED,
Evalplot

Evalplot

0.0       10.0       0.0       10.0
3
2
Evalplot

ENDFB.IN
Evalplot

1          2
0
-2
0 0.0
Evalplot

26056 4  2 1.00000+ 626056
4  2 2.00000+ 7
0
Evalplot

26056 4  4 1.00000+ 626056
4  4 2.00000+ 7
0
Evalplot

(BLANK
LINE MUSE FOLLOW LAST REQUEST)
Evalplot

Evalplot

EXAMPLE INPUT
NO. 3 (CHAINED INPUT)
Evalplot

-----------------------------------
Evalplot

FOR ALL THORIUM
AND URANIUM ISOTOPES PLOT TOTAL, ELASTIC ,CAPTURE  Evalplot

AND FISSION, BUT
NOT INELASTIC CROSS SECTIONS OVER THERE ENTIRE    Evalplot

ENERGY RANGE
AND FROM 1 KEV TO 1 MEV. THE FOLLOWING 8 INPUT
Evalplot

LINES ARE
REQUIRED,
Evalplot

Evalplot

0.0       10.0       0.0       10.0
3          2      Evalplot

ENDFB.IN
Evalplot

1
2
0
-2
0 0.0
Evalplot

90000 3  1
90999 3  2
-1
Evalplot

90000 3 18
90999 3102
1
Evalplot

90000 3  1 1.00000+ 390999
3  2 1.00000+ 6
-1
Evalplot

90000 3 18 1.00000+ 390999 3102 1.00000+ 6
1
Evalplot

(BLANK
LINE MUSE FOLLOW LAST REQUEST)
Evalplot

Evalplot

NOTE, THIS
EXAMPLE INCLUDES 2 CHAINED REQUESTED - INPUT LINES 3    Evalplot

AND 4 SELECTING
DATA AND PRODUCING A PLOT OVER THE ENTIRE ENERGY   Evalplot

RANGE AND INPUT
LINES 5 AND 6 SELECTING THE SAME DATA AND
Evalplot

PRODUCING A PLOT
FROM 1 KEV TO 1 MEV.
Evalplot

Evalplot

ANY NUMBER OF
REQUEST LINES MAY TO CHAINED TOGETHER TO SELECT      Evalplot

DATA. THE CHAIN
ENDS WHERE THE TYPE OF DATA (COLS. 45-55) IS NOT   Evalplot

NEGATIVE AND
THEN THE SELECTED DATA WILL BE PLOTTED.
Evalplot

Evalplot

EXAMPLE INPUT
NO. 4
Evalplot

-------------------
Evalplot

FOR THE SAME
EXAMPLE AS ABOVE, EXCEPT USE A DIFFERENT FILENAME     Evalplot

FOR THE ENDF/B
DATA TO READ FROM A FILE TREE STRUCTURE. THE
Evalplot

FOLLOWING 8
INPUT LINES ARE REQUIRED,                              Evalplot

Evalplot

0.0       10.0       0.0       10.0
3
2
Evalplot

EVALUATION/ENDFB6/THORIUM
Evalplot

1
2
0
-2
0 0.0
Evalplot

90000 3  1
90999 3  2
-1
Evalplot

90000 3 18
90999 3102
1
Evalplot

90000 3  1 1.00000+ 390999
3  2 1.00000+ 6
-1
Evalplot

90000 3 18 1.00000+ 390999 3102 1.00000+ 6
1
Evalplot

(BLANK
LINE MUST FOLLOW LAST REQUEST)
Evalplot

Evalplot

=====
PLOTTER/GRAPHICS TERMINAL INTERFACE ============================= Evalplot

Evalplot

THIS
PROGRAM USES A SIMPLE CALCOMP LIKE INTERFACE INVOLVING       Evalplot

ONLY 6
SUBROUTINES,
Evalplot

Evalplot

STARPLOT  - INITIALIZE
PLOTTER
Evalplot

NEXTPLOT  - CLEAR THE SCREEN
FOR THE NEXT PLOT
Evalplot

ENDPLOTS  - TERMINATE
PLOTTING
Evalplot

Evalplot

PLOT(X,Y,IPEN)        -
DRAW OR MOVE FROM LAST LOCATION TO (X,Y), Evalplot

END OF CURRENT PLOT OR END OF PLOTTING.   Evalplot

IPEN =   2 - DRAW                                           Evalplot

=   3 - MOVE
Evalplot

Evalplot

PEN(IPEN)
- SELECT COLOR.                             Evalplot

IPEN- COLOR = 1 TO N (N = ANY POSITIVE INTEGER)
Evalplot

Evalplot

BOXCOLOR(X,Y,IFILL,IBORDER) - FILL A RECTANGULAR BOX DEFINED      Evalplot

BY THE X AND Y CORNERS - X(1),      Evalplot

X(2), Y(1),Y(2)
Evalplot

IFILL
- COLOR TO FILL BOX WITH              Evalplot

IBORDER  - COLOR OF BOX
BORDER
Evalplot

Evalplot

IN ORDER TO
INTERFACE THIS PROGRAM FOR USE ON ANY PLOTTER WHICH    Evalplot

DOES NOT USE THE
ABOVE CONVENTIONS IT IS MERELY NECESSARY FOR THE  Evalplot

THE USER TO
WRITE 6 SUBROUTINES WITH THE NAMES PLOTS, PLOT AND PEN Evalplot

WITH THE
SUBROUTINE ARGUMENTS DESCRIBED ABOVE AND TO THEN CALL THE Evalplot

LOCAL EQUIVALENT ROUTINES.
Evalplot

Evalplot

COLOR PLOTS
Evalplot

------------------------------------------------------------------
Evalplot

TO SELECT
PLOTTING COLORS SUBROUTINE PEN (DESCRIBED ABOVE) IS USED Evalplot

TO SELECT ONE OF
THE AVAILABLE COLORS. IF YOU HAVE COLOR ON YOUR   Evalplot

PLOTTER YOU
SHOULD PROVIDE A SUBROUTINE PEN TO SELECT COLORS.      Evalplot

Evalplot

BLACK AND WHITE
PLOTS
Evalplot

------------------------------------------------------------------
Evalplot

WHEN PRODUCING
BLACK AND WHITE PLOTS SUBROUTINE PEN NEED MERELY    Evalplot

BE A DUMMY
SUBROUTINE TO IGNORE ANY ATTEMPT TO CHANGE COLORS,      Evalplot

Evalplot

SUBROUTINE
PEN(IPEN)
Evalplot

RETURN
Evalplot

END
Evalplot

Evalplot

SIMILAR BOXCOLOR
CAN BE A DUMMY
Evalplot

Evalplot

SUBROUTINE
BOXCOLOR(X,Y,IFILL,IBORDER)
Evalplot

RETURN
Evalplot

END
Evalplot

Evalplot

CHARACTER
SET
Evalplot

------------------------------------------------------------------
Evalplot

THIS PROGRAM USES COMPUTER
AND PLOTTER DEVICE INDEPENDENT SOFTWARE Evalplot

CHARACTERS. THIS
PROGRAM COMES WITH A FILE THAT DEFINES THE PEN    Evalplot

STROKES REQUIRED
TO DRAW ALL CHARACTERS ON AN IBM KEYBOARD (UPPER  Evalplot

AND LOWER CASE
CHARACTERS, NUMBERS, ETC.) PLUS AN ALTERNATE SET OF Evalplot

ALL UPPER AND
LOWER CASE GREEK CHARACTERS AND ADDITIONAL SPECIAL   Evalplot

SYMBOLS.
Evalplot

Evalplot

THE SOFTWARE
CHARACTER TABLE CONTAINS X AND Y AND PEN POSITIONS TO Evalplot

DRAW EACH
CHARACTER. IF YOU WISH TO DRAW ANY ADDITIONAL CHARACTERS Evalplot

OR TO MODIFY THE
FONT OF THE EXISTING CHARACTERS YOU NEED ONLY     Evalplot

MODIFY THIS
TABLE.
Evalplot

Evalplot

ADDITIONAL
FONTS
Evalplot

----------------
Evalplot

THIS PROGRAM
COMES WITH 3 COMPLETE SETS OF THE SAME CHARACTERS     Evalplot

USING DIFFERENT
FONTS. FOR SPEED IN PLOTTING IT IS RECOMMENDED     Evalplot

THAT YOU USE THE
SIMPLEX FONT. FOR FINISHED PLOTS SUITABLE FOR     Evalplot

PUBLICATION, BUT
REQUIRING MORE TIME TO GENERATE A PLOT, IT IS     Evalplot

RECOMMENDED THAT
YOU USE THE DUPLEX OR COMPLEX FONT - YOU CAN      Evalplot

EXPERIMENT WITH
ANY OF THE 3 FONTS TO DETERMINE WHICH BEST MEETS   Evalplot

YOUR NEEDS.
Evalplot

Evalplot

TO USE ANY ONE
OF THE FONTS MERELY BY SURE THAT IT IS DEFINED AS   Evalplot

UNIT 12 FOR
INPUT (IF USING STANDARD FILENAMES IT SHOULD BE
Evalplot

NAMED PLOT.CHR).
SO THAT SWITCHING FONTS CAN BE SIMPLY DONE
Evalplot

MERELY BY
COPYING THE FONT THAT YOU WANT TO THE UNIT 12 THAT       Evalplot

YOU ARE USING
FOR INPUT.
Evalplot

Evalplot

CONTROL
CHARACTERS
Evalplot

------------------------------------------------------------------
Evalplot

IN THE SOFTWARE
CHARACTER TABLE ALL CHARACTERS TO BE PLOTTED WILL  Evalplot

HAVE PEN POSITION
= 2 (DRAW) OR = 3 (MOVE). IN ADDITION THE TABLE  Evalplot

CURRENTLY
CONTAINS 4 CONTROL CHARACTERS,
Evalplot

Evalplot

PEN POSITION =
0
Evalplot

----------------
Evalplot

SHIFT THE NEXT
PRINTED CHARACTER BY X AND Y. 3 CONTROL CHARACTERS  Evalplot

ARE PRESENTLY
INCLUDED IN THE SOFTWARE CHARACTER TABLE TO ALLOW    Evalplot

SHIFTING.
Evalplot

Evalplot

{   = SHIFT UP (FOR
SUPERSCRIPTS..............X= 0.0, Y= 0.5)      Evalplot

}   = SHIFT DOWN (FOR
SUBSCRIPTS..............X= 0.0, Y=-0.5)      Evalplot

\   = SHIFT LEFT 1 CHARACTER (FOR
BACKSPACE...X=-1.0, Y= 0.0)      Evalplot

Evalplot

PEN POSITION
=-1
Evalplot

----------------
Evalplot

SELECT THE NEXT
PRINTED CHARACTER FROM THE ALTERNATE CHARACTER     Evalplot

SET. AT PRESENT
THIS CONTROL CHARACTER IS,
Evalplot

Evalplot

|   = SWITCH TO ALTERNATE CHARACTER
SET
Evalplot

Evalplot

THESE 4 CONTROL
CHARACTERS ARE ONLY DEFINED BY THE VALUE OF THE    Evalplot

PEN POSITION IN
THE SOFTWARE CHARACTER TABLE (I.E., THEY ARE NOT   Evalplot

HARD WIRED INTO
THIS PROGRAM). AS SUCH BY MODIFYING THE SOFTWARE   Evalplot

CHARACTER TABLE
THE USER HAS THE OPTION OF DEFINING ANY CONTROL    Evalplot

CHARACTERS TO
MEET SPECIFIC NEEDS.
Evalplot

Evalplot

THESE CHARACTERS
MAY BE USED IN CHARACTER STRINGS TO PRODUCE       Evalplot

SPECIAL EFFECTS.
FOR EXAMPLE, TO PLOT SUBSCRIPT 5, B, SUPERSCRIPT  Evalplot

10 USE THE
STRING,                                                 Evalplot

Evalplot

}5B{1{0
Evalplot

Evalplot

TO PLOT B,
SUBSCRIPT 5 AND SUPERSCRIPT 10 WITH THE 5 DIRECTLY      Evalplot

BELOW THE 1 OF
THE 10 WE CAN USE THE BACKSPACE CHARACTER TO
Evalplot

POSITION THE 1
DIRECTLY ABOVE THE 5 USING THE STRING,
Evalplot

Evalplot

B}5\{1{0
Evalplot

Evalplot

TO PLOT UPPER
CASE GREEK GAMMA FOLLOWED BY THE WORD TOTAL (I.E.,   Evalplot

RESONANCE TOTAL
WIDTH) USE THE STRING.
Evalplot

Evalplot

|G TOTAL
Evalplot

Evalplot

NOTE, WHEN THESE
CONTROL CHARACTERS ARE USED THEY ONLY EFFECT THE  Evalplot

NEXT 1 PRINTED
CHARACTER (SEE, ABOVE EXAMPLE OF PLOTTING SUPER-    Evalplot

SCRIPT 10 WHERE
THE SHIFT UP CONTROL CHARACTER WAS USED BEFORE THE Evalplot

1 AND THEN AGAIN
BEFORE THE 0 AND THE BACKSPACE AND SHIFT UP       Evalplot

CONTROL
CHARACTERS WERE USED IN COMBINATION).
Evalplot

Evalplot

IF THESE 4
CONTROL CHARACTERS ARE NOT AVAILABLE ON YOUR COMPUTER   Evalplot

YOU CAN MODIFY
THE SOFTWARE CHARACTER TABLE TO USE ANY OTHER 4     Evalplot

CHARACTERS THAT
YOU DO NOT NORMALLY USE IN CHARACTER STRINGS (FOR  Evalplot

DETAILS SEE THE
SOFTWARE CHARACTER TABLE).
Evalplot

Evalplot

STANDARD/ALTERNATE CHARACTER SETS
Evalplot

------------------------------------------------------------------
Evalplot

THE SOFTWARE
CHARACTER TABLE CONTAINS 2 SETS OF CHARACTERS WHICH   Evalplot

ARE A STANDARD
SET (ALL CHARACTERS ON AN IBM KEYBOARD) AND AN      Evalplot

ALTERNATE SET
(UPPER AND LOWER CASE GREEK CHARACTERS AND SPECIAL   Evalplot

CHARACTERS). TO
DRAW A CHARACTER FROM THE ALTERNATE CHARACTER SET  Evalplot

PUT A RIGHT
BRACKET CHARACTER (|) BEFORE A CHARACTER (SEE THE      Evalplot

ABOVE EXAMPLE
AND THE SOFTWARE CHARACTER TABLE FOR DETAILS). THIS  Evalplot

CONTROL
CHARACTER WILL ONLY EFFECT THE NEXT 1 PLOTTED CHARACTER.   Evalplot

Evalplot

SUB AND SUPER
SCRIPTS
Evalplot

------------------------------------------------------------------
Evalplot

TO DRAW
SUBSCRIPT PRECEED A CHARACTER BY }. TO DRAW SUPERSCRIPT    Evalplot

PRECEED A
CHARACTER BY { (SEE THE ABOVE EXAMPLE AND THE SOFTWARE   Evalplot

CHARACTER TABLE
FOR DETAILS). THESE CONTROL CHARACTER WILL ONLY    Evalplot

EFFECT THE NEXT
1 PLOTTED CHARACTER.
Evalplot

Evalplot

BACKSPACING
Evalplot

------------------------------------------------------------------
Evalplot

TO BACKSPACE ONE
CHARACTER PRECEED A CHARACTER BY \ (SEE, THE      Evalplot

ABOVE EXAMPLE
AND THE SOFTWARE CHARACTER TABLE FOR DETAILS). THIS  Evalplot

CONTROL CHARACTER
WILL PERFORM A TRUE BACKSPACE AND WILL EFFECT    Evalplot

ALL FOLLOWING
CHARACTERS IN THE SAME CHARACTER STRING.
Evalplot

Evalplot

PLOT
DIMENSIONS                                                    Evalplot

---------------
Evalplot

ARE DEFINED BY
USER INPUT. INTERNALLY THE PROGRAM WILL CREATE A    Evalplot

PLOT IN
APPROXIMATELY A4 OR 8-1/2 BY 11 INCH FORMAT. DURING
Evalplot

OUTPUT THE PLOT
IS TRANSFORMED TO THE UNITS (INCHES, CENTIMETERS,  Evalplot

MILLIMETERS,
WHATEVER) OF THE PLOTTER BEING USED AND OUTPUT.       Evalplot

Evalplot

=====
PLOTTER/GRAPHICS TERMINAL INTERFACE ============================= Evalplot

=======================================================================
Evalplot

=======================================================================
Fixup

Fixup

PROGRAM
FIXUP
Fixup

VERSION 84-1
(NOVEMBER 1984)
Fixup

VERSION 86-1
(JANUARY 1986) *IMPROVED BASED ON USER COMMENTS       Fixup

*FORTRAN-77/H VERSION
Fixup

VERSION 86-2
(JUNE 1986)    *ALLOW
CREATION OF SECTIONS OF CROSS
Fixup

SECTIONS WHICH ARE NOT PRESENT IN     Fixup

THE ORIGINAL EVALUATION
Fixup

VERSION 88-1
(JULY 1988)
*OPTION...INTERNALLY DEFINE ALL I/O    Fixup

FILE
NAMES (SEE, SUBROUTINE FILEIO
Fixup

FOR DETAILS).
Fixup

*IMPROVED BASED ON USER COMMENTS.      Fixup

VERSION 89-1
(JANUARY 1989) *PSYCHOANALYZED BY PROGRAM FREUD TO    Fixup

INSURE PROGRAM WILL NOT DO ANYTHING   Fixup

CRAZY.
Fixup

*UPDATED
TO USE NEW PROGRAM CONVERT
Fixup

KEYWORDS.
Fixup

*ADDED LIVERMORE
CIVIC COMPILER
Fixup

CONVENTIONS.
Fixup

VERSION 89-2
(MARCH 1989)   *ADDED ENDF/B-VI
SUMMATION RULES AND   Fixup

DEFINED MF AND MT NUMBERS. PROGRAM    Fixup

WILL NOW USE MF=1, MT=451 TO DEFINE   Fixup

THE ENDF/B FORMAT OF THE DATA (E.G.,  Fixup

ENDF/B-VI OR EARLIER) AND USE THE     Fixup

CORRECT SUMMATION RULES FOR EACH      Fixup

VERSION OF THE ENDF/B FORMAT. IF      Fixup

MF=1, MT=451 IS NOT PRESENT PROGRAM   Fixup

WILL USE ENDF/B-VI SUMMATION
Fixup

CONVENTIONS AS A DEFAULT.
Fixup

VERSION 90-1
(JUNE 1990)    *UPDATED
BASED ON USER COMMENTS
Fixup

*ADDED PHOTON INTERACTION, MF=23       Fixup

VERSION 91-1
(JUNE 1991)    *ADDED
FORTRAN SAVE OPTION
Fixup

*NEW MORE CONSISTENT ENERGY OUTPUT     Fixup

ROUTINE
Fixup

VERSION 92-1 (JANUARY
1992) *ADDED OPTION TO CALCULATE RATIOS,     Fixup

E.G., CAPTURE/FISSION AND PRODUCTS,   Fixup

NU-BAR*FISSION - AND OUTPUT THE       Fixup

RESULTS
IN THE ENDF/B FORMAT (SEE,
Fixup

BELOW - CREATING RATIOS AND PRODUCTS) Fixup

*ALLOW TOTAL NU-BAR (MF=1, MT=452) TO  Fixup

BE
USED IN DEFINING RATIOS OR
Fixup

PRODUCTS.
Fixup

*ALLOW ALL CROSS SECTIONS TO BE PUT    Fixup

ON A
UNIFORM ENERGY GRID.
Fixup

*NOTE, CHANGE IN INPUT FORMAT FOR      Fixup

RANGES OF MT NUMBERS
Fixup

*COMPLETELY CONSISTENT I/O ROUTINES -  Fixup

TO MINIMIZE COMPUTER DEPENDENCE.      Fixup

VERSION 93-1
(JULY 1993)    *CORRECTED
ALGORITHM TO CREATE UNIFORM Fixup

ENERGY GRID.                          Fixup

VERSION 94-1
(JANUARY 1993) *VARIABLE ENDF/B DATA FILENAMES
Fixup

TO ALLOW ACCESS TO FILE STRUCTURES    Fixup

(WARNING - INPUT PARAMETER FORMAT     Fixup

HAS BEEN CHANGED)
Fixup

*INCREASED PAGE SIZE FROM 1002 TO      Fixup

12000 DATA POINTS.
Fixup

*CLOSE ALL FILES BEFORE TERMINATING    Fixup

(SEE, SUBROUTINE ENDIT)
Fixup

VERSION 96-1
(JANUARY 1996) *COMPLETE RE-WRITE
Fixup

*IMPROVED COMPUTER INDEPENDENCE
Fixup

*ALL DOUBLE PRECISION
Fixup

*ON SCREEN OUTPUT
Fixup

*UNIFORM
TREATMENT OF ENDF/B I/O       Fixup

*IMPROVED OUTPUT PRECISION
Fixup

*DEFINED SCRATCH FILE NAMES
Fixup

*INCREASED
PAGE SIZE FROM 12000 TO
Fixup

36000 DATA POINTS.
Fixup

VERSION 99-1
(MARCH 1999)   *CORRECTED
CHARACTER TO FLOATING       Fixup

POINT READ
FOR MORE DIGITS
Fixup

*UPDATED TEST FOR ENDF/B FORMAT
Fixup

VERSION BASED ON RECENT FORMAT CHANGE Fixup

*GENERAL IMPROVEMENTS BASED ON
Fixup

USER FEEDBACK
Fixup

VERSION 99-2
(JUNE 1999)    *ASSUME
ENDF/B-VI, NOT V, IF MISSING
Fixup

MF=1, MT-451.                         Fixup

*FIXED CREATION OF SECTIONS
Fixup

VERS. 2000-1
(FEBRUARY 2000)*GENERAL IMPROVEMENTS BASED ON
Fixup

USER FEEDBACK
Fixup

VERS. 2002-1
(MAY 2002)
*OPTIONAL INPUT PARAMETERS
Fixup

*SUMMATION RULES ARE DEFINED BASED     Fixup

ON CONTENTS OF TABLES.
Fixup

VERS. 2004-1
(JAN. 2004)    *GENERAL
UPDATE BASED ON USER FEEDBACK Fixup

*INCREASED PAGE SIZE FROM 36000 TO     Fixup

60000 DATA POINTS.
Fixup

VERS. 2005-1
(JAN. 2005)    *UPDATED MT
CREATION TO ALLOW MAT =0
Fixup

INDICATING CREATE FOR ALL MATS.       Fixup

VERS. 2007-1
(JAN. 2007)    *CHECKED
AGAINST ALL ENDF/B-VII
Fixup

*INCREASED
PAGE SIZE FROM 60,000 TO
Fixup

600,000 DATA POINTS.
Fixup

Fixup

OWNED, MAINTAINED
AND DISTRIBUTED BY
Fixup

------------------------------------
Fixup

THE NUCLEAR DATA
SECTION
Fixup

INTERNATIONAL
ATOMIC ENERGY AGENCY
Fixup

P.O. BOX 100
Fixup

A-1400, VIENNA, AUSTRIA
Fixup

EUROPE
Fixup

Fixup

ORIGINALLY
WRITTEN BY
Fixup

------------------------------------                               Fixup

DERMOTT E.
CULLEN
Fixup

UNIVERSITY OF CALIFORNIA
Fixup

LAWRENCE
LIVERMORE
NATIONAL LABORATORY
Fixup

L-159
Fixup

P.O. BOX 808
Fixup

LIVERMORE, CA
94550
Fixup

U.S.A.
Fixup

TELEPHONE  925-423-7359
Fixup

E. MAIL    [email-masked]
Fixup

WEBSITE
HTTP://WWW.LLNL.GOV/CULLEN1
Fixup

Fixup

PURPOSE
Fixup

=======
Fixup

THIS PROGRAM IS
DESIGNED TO READ EVALUATED DATA IN THE ENDF/B      Fixup

FORMAT, PERFORM
CORRECTIONS AND OUTPUT THE RESULT IN THE ENDF/B    Fixup

FORMAT. TWO
TYPES OF CORRECTIONS ARE POSSIBLE (1) AUTOMATIC AND    Fixup

(2) OPTIONAL
(BASED ON USER INPUT) CORRECTIONS.
Fixup

Fixup

ONE OF THE MOST
IMPORTANT FUNCTIONS OF THIS PROGRAM IS TO
Fixup

RE-DEFINE ALL
REDUNDANT CROSS SECTIONS (E.G. TOTAL) TO BE EXACTLY  Fixup

EQUAL TO THE SUM
OF ITS PARTS. THIS PROCEDURE ELIMINATES THE       Fixup

PROBLEM WITH
MANY ENDF/B EVALUATIONS, WHERE DUE TO THE USE OF      Fixup

NON-LINEAR
INTERPOLATION LAWS THE TOTAL MAY BE EQUAL TO THE SUM    Fixup

OF ITS PARTS AT
ALL TABULATED ENERGIES, BUT BASED ON THE
Fixup

INTERPOLATION
LAWS IT CAN BE QUITE DIFFERENT AT ENERGIES BETWEEN   Fixup

TABULATED
ENERGIES.
Fixup

Fixup

AUTOMATIC
CHECKS/CORRECTIONS
Fixup

============================
Fixup

(1) CHECK THAT
MAT/MF/MT DOES NOT CHANGE UNLESS A MEND/FEND/SEND   Fixup

LINE IS READ. IF MAT/MF/MT CHANGES A WARNING MESSAGE IS
Fixup

PRINTED BUT NO CORRECTIVE ACTION IS TAKEN.
Fixup

(2) ALL LINES
WITHIN A GIVEN MAT WILL BE SEQUENTIALLY NUMBERED     Fixup

ON OUTPUT.
Fixup

Fixup

OPTIONAL
CHECKS/CORRECTIONS
Fixup

===========================
Fixup

THE FOLLOWING NUMBERS
CORRESPOND TO THE INPUT DATA OPTION COLUMNS  Fixup

(SEE THE
DESCRIPTION OF THE INPUT BELOW)
Fixup

Fixup

(1) CORRECT ZA
AND AWR IN ALL SECTIONS. CHECK TO INSURE THAT THE   Fixup

C1 AND C2 VALUES (ZA AND AWR) ARE THE SAME IN ALL SECTIONS.    Fixup

THE C1 AND C2 OF THE FIRST SECTION READ ARE ASSUMED TO BE      Fixup

CORRECT AND ARE USED FOR COMPARISON. IF THE C1 AND/OR C2 OF    Fixup

THE FIRST SECTION ARE NOT POSITIVE AN ERROR MESSAGE IS OUTPUT  Fixup

AND THE MATERIAL IS COPIED WITHOUT CHANGE.
Fixup

NOTE....TO CHANGE THE ZA AND/OR AWR OF ANY MATERIAL IT IS      Fixup

MERELY NECESSARY TO CHANGE THE ZA AND/OR AWR IN THE FIRST      Fixup

SECTION OF THE MATERIAL AND USE THIS OPTION TO AUTOMATICALLY   Fixup

CHANGE ALL OTHER SECTIONS.                                     Fixup

(2) CORRECT
CROSS SECTION (MF=3) THRESHOLDS. THE Q-VALUE AND AWR   Fixup

ARE USED TO DERIVE THE REACTION THRESHOLD USING THE RELATION,  Fixup

Fixup

E-THRESHOLD = -(Q-VALUE)*(AWRE+1.0)/AWRE
Fixup

Fixup

IF THE THRESHOLD IS POSITIVE THE CROSS SECTION IS CHECKED TO   Fixup

INSURE THAT THE FIRST TABULATED POINT IS AT THE THRESHOLD AND  Fixup

HAS A ZERO CROSS SECTION. IF NOT, THE CROSS SECTION WILL BE    Fixup

CHANGED.
Fixup

(A) IF THE FIRST TABULATED POINT IS ABOVE THE THRESHOLD AND    Fixup

HAS A ZERO CROSS SECTION, THE POINT IS DELETED AND A POINT Fixup

IS INSERTED AT THE THRESHOLD.
Fixup

(B) IF THE FIRST TABULATED POINT IS ABOVE THE THRESHOLD AND    Fixup

HAS A NON-ZERO CROSS SECTION, A POINT WITH ZERO CROSS      Fixup

SECTION IS INSERTED AT THE THRESHOLD.
Fixup

(C) IF THE FIRST TABULATED POINT IS BELOW THE THRESHOLD AND    Fixup

HAS A NON-ZERO CROSS SECTION, ALL POINTS BELOW THE
Fixup

THRESHOLD ARE DELETED AND A POINT WITH ZERO CROSS SECTION  Fixup

IS INSERTED AT THE THRESHOLD.
Fixup

(3) EXTEND ALL
CROSS SECTIONS (MF=3) TO 20 MEV. IF THE TABULATED   Fixup

CROSS SECTION ENDS BELOW 20 MEV IT WILL BE EXTENDED TO 20 MEV  Fixup

AS EITHER ZERO (IMOPS(3)=1) OR CONSTANT (IMOPS(3)=2) EQUAL     Fixup

TO THE LAST TABULATED VALUE.
Fixup

(4) ALLOW
REACTION (MF=3, ANY MT) DELETION. ALL SPECIFIED
Fixup

REACTIONS WILL BE DELETED WHEN THE DATA IS READ FROM THE       Fixup

INPUT ENDF/B DATA FILE AND WILL NOT BE IN THE OUTPUT ENDF/B    Fixup

DATA FILE. WARNING DELETED REACTIONS MAY NOT BE USED TO DEFINE
Fixup

ANY RECONSTRUCTED REACTIONS (I.E. REACTIONS DEFINED BY SUMMING
Fixup

OTHER REACTIONS). SINCE DELETED REACTIONS ARE DELETED DURING   Fixup

READING IT IS AS IF THEY NEVER EXISTED AND IF ANY DELETED      Fixup

REACTION IS REQUIRED LATER TO DEFINE ANY SUM AN ERROR WILL     Fixup

RESULT. THE USER MAY SPECIFY THAT THE DELETION RULES ARE TO BE
Fixup

READ FROM INPUT (IMOPS(4)=1) OR THAT THE BUILT IN SUMMATION    Fixup

RULES ARE TO BE USED (MOPS(4)=2). AT THE PRESENT TIME THE      Fixup

BUILT-IN DELETION RULES ARE THAT NO SECTIONS SHOULD BE DELETED
Fixup

(THE USER MAY OVERRIDE THIS CONVENTION BY INPUT).
Fixup

(5) ALLOW
REACTION (MF=3, ANY MT) RECONSTRUCTION BY SUMMING OTHER  Fixup

REACTIONS. IN ORDER TO OPTIMIZE THE RUNNING TIME OF THIS       Fixup

PROGRAM CARE SHOULD BE EXERCISED TO MINIMIZE THE NUMBER OF     Fixup

TIMES THAT EACH CONTRIBUTING CROSS SECTION MUST BE USED.       Fixup

THE USED MAY SPECIFY THAT
THE SUMMATION RULES ARE TO BE READ
Fixup

AS INPUT (IMOPS(5)=1) OR THAT THE BUILT IN SUMMATION RULES     Fixup

ARE TO BE USED (IMOPS(5)=2). THE BUILT IN SUMMATION RULES ARE  Fixup

DESIGNED TO USE ENDF/B CONVENTIONS AND TO MINIMIZE THE NUMBER  Fixup

OF TIMES THAT EACH CROSS SECTION IS USED.
Fixup

(6) INSURE THAT
ALL CROSS SECTIONS ARE NON-NEGATIVE (I.E. ARE      Fixup

ZERO OR POSITIVE). DURING READING ALL NEGATIVE CROSS SECTIONS  Fixup

WILL BE SET EQUAL TO ZERO AND TREATED AS SUCH DURING ALL       Fixup

SUBSEQUENT SUMMATIONS AND ENDF/B OUTPUT.
Fixup

NOTE...THIS OPTION SHOULD NEVER BE USED WITH DATA CONTAINING   Fixup

BACKGROUND CROSS SECTIONS WHICH MAY BE NEGATIVE. ONLY AFTER    Fixup

THE RESONANCE CONTRIBUTION HAS BEEN ADDED TO THE BACKGROUND    Fixup

TO DEFINE THE ACTUAL CROSS SECTION IS IT VALID TO ELIMINATE    Fixup

NEGATIVE CROSS SECTIONS.
Fixup

NOTE...THIS OPTION MAY BE USED TO DELETE NEGATIVE ELASTIC      Fixup

CROSS SECTIONS THAT MAY RESULT FROM RECONSTRUCTING CROSS       Fixup

SECTIONS FROM SINGLE LEVEL BREIT-WIGNER PARAMETERS. IF THE     Fixup

TOTAL CROSS SECTION IS THEN RECONSTRUCTED USING THE CORRECTED  Fixup

ELASTIC CROSS SECTION THE TOTAL WILL BE POSITIVE DUE TO THE    Fixup

CONTRIBUTIONS OF CAPTURE AND FISSION (THUS AVOIDING NUMERICAL  Fixup

INSTABILITY PROBLEMS DURING SELF-SHIELDING CALCULATIONS).      Fixup

(7) WITHIN EACH
SECTION OF CROSS SECTIONS DELETE ENERGIES THAT     Fixup

ARE NOT IN ASCENDING ENERGY ORDER (ENERGY REPETITION IS O.K.)  Fixup

(8) WITHIN EACH
SECTION OF CROSS SECTIONS ELIMINATE DUPLICATE      Fixup

POINTS (SUCCESSIVE POINTS WITH THE SAME ENERGY-CROSS SECTION).
Fixup

(9) TEST THAT
ALL SECTIONS ARE IN ASCENDING MAT/MF/MT ORDER.       Fixup

IF NOT, NO CORRECTIVE ACTION WILL BE TAKEN, ONLY AN ERROR      Fixup

MESSAGE WILL BE OUTPUT.
Fixup

(10) CHECK MF/MT FOR
EACH SECTION TO INSURE THAT THEY ARE DEFINED   Fixup

IN THE ENDF/B FORMAR MANUAL. IF THEY ARE NOT DEFINED AN ERROR  Fixup

MESSAGE IS PRINTED, BUT NO CORRECTIVE ACTION IS TAKEN.
Fixup

(11) ALLOW SECTIONS WHICH
ARE NOT PRESENT IN THE ORIGINAL (INPUT)   Fixup

EVALUATION TO BE CREATED. NORMALLY THIS PROGRAM WILL ONLY      Fixup

RECONSTRUCT AND OUTPUT SECTIONS IF THE SECTION IS PRESENT      Fixup

IN THE ORIGINAL EVALUATION. THIS PROCEDURE IS FOLLOWED BECAUSE
Fixup

NORMALLY THE PROGRAM DOES NOT KNOW HOW TO DEFINE THE CONTENTS  Fixup

OF THE FIRST TWO LINES OF THE SECTION (E.G., Q-VALUE,
Fixup

TEMPERATURE, INITIAL AND FINAL
STATES). THIS OPTION MAY
BE     Fixup

USED TO ALLOW THE PROGRAM TO READ AND SAVE A TABLE DEFINING    Fixup

THE CONTENTS OF THE FIRST TWO LINES OF EACH SECTION TO BE      Fixup

CREATED.
Fixup

NOTE...IF A SECTION IS PRESENT ANY COMMAND TO CREATE IT WILL   Fixup

BE IGNORED.
Fixup

(12)ALLOW ENERGY
POINTS TO BE INSERTED. THE PROGRAM CAN READ UP    Fixup

TO 50, ENERGIES, MAT, MT AND USE LINEAR INTERPOLATION TO       Fixup

INSERT ENERGY POINTS INTO TABLES AS THEY ARE READ, E.G.,       Fixup

INSERT AN ENERGY POINT AT THERMAL ENERGY (0.0253 EV). IF       Fixup

AN MAT AND/OR MT IS ZERO THIS IMPLIES = ALL - INSERT THE       Fixup

ENERGY IN ALL TABLES.
Fixup

(13)PUT ALLOW
CROSS SECTIONS ON A UNIFORM ENERGY GRID = EACH       Fixup

SECTION
(MT) OF CROSS SECTIONS WILL INCLUDE ALL ENERGIES       Fixup

WHICH APPEAR IN AT LEAST ONE SECTION OF DATA. PARAMETERS       Fixup

(MT=251 THROUGH 255) ARE NOT INCLUDED IN THE UNIFORM ENERGY    Fixup

GRID.
Fixup

(14)DELETE
SECTION IF CROSS SECTION = 0 AT ALL ENERGIES. THIS      Fixup

SOUNDS LIKE AN ABSURD OPTION, BUT IS REQUIRED BECAUSE SUCH     Fixup

SECTIONS EXIST IN ENDF/B-VI.
Fixup

Fixup

CREATING RATIOS
AND PRODUCTS
Fixup

============================
Fixup

IN ORDER TO
CREATE RATIOS AND PRODUCTS = NEW MT NUMBERS, YOU MUST  Fixup

DO TWO
THINGS,
Fixup

Fixup

1) DEFINE EACH
NEW MT NUMBER AS A RATIO OR PRODUCT OF TWO MT       Fixup

NUMBERS.
Fixup

Fixup

2) USE THE
CREATE MT NUMBER OPTION AND INPUT THE FIRST TWO LINES   Fixup

OF THE SECTION
Fixup

Fixup

WARNING - UNLESS
YOU DO BOTH OF THESE YOU WILL NOT OBTAIN OUTPUT   Fixup

IN THE ENDF/B
FORMAT.
Fixup

Fixup

TWO SPECIAL MT
NUMBERS HAVE BEEN DEFINED BY CSEWG INVOLVING
Fixup

RATIOS AND
PRODUCTS,
Fixup

Fixup

ALPHA (MT=254)= CAPTURE
(MT=102)/FISSION (MT=18)
Fixup

Fixup

ETA
(MT=255)  = NU-BAR (MT=452)*FISSION
(MT=18)/ABSORPTION (MT=27) Fixup

Fixup

ABSORPTION
(MT=27) = FISSION (MT=18) + SUM (MT=102 THROUGH 116)    Fixup

Fixup

AS YET THERE IS NO
STANDARD DEFINITION OF MT NUMBERS FOR RATIO     Fixup

OR PRODUCT DATA.
YOU ARE FREE TO USE ANY MT NUMBERS NORMALLY NOT   Fixup

USED IN THE
ENDF/B. HOWEVER, IT WILL THEN BE YOUR RESPONSIBILITY   Fixup

TO PROPERLY
INTERPRET THE RESULTS, I.E., NOBODY ELSE WILL HAVE     Fixup

ANY IDEA HOW TO
INTERPRET A TABLE OF DATA ASSOCIATED WITH THE MT   Fixup

NUMBERS YOU HAVE
USED.
Fixup

Fixup

THIS PROGRAM CAN
BE ONLY DIRECTLY DEFINE RATIOS AND PRODUCTS       Fixup

USING TWO MT
NUMBERS = BINARY OPERATIONS, E.G., DEFINE THE CAPTURE Fixup

TO FISSION
RATIO, OR DEFINE THE PRODUCT NU-BAR*FISSION.
Fixup

Fixup

THIS PROGRAM
CANNOT DIRECTLY DEFINE RATIO OR PRODUCT OF A SUM OF   Fixup

SECTIONS TO THE
SUM OF ANOTHER SET OF SECTIONS. HOWEVER, THIS CAN  Fixup

BE DONE
INDIRECTLY BY FIRST DEFINING A DUMMY MT NUMBER (ANY MT     Fixup

NUMBER NOT
NORMALLY USED IN ENDF/B) TO BE A SUM OF SECTIONS AND    Fixup

A SECOND DUMMY
MT NUMBER TO BE A SECOND SUM OF SECTIONS. YOU CAN   Fixup

THEN DEFINE
RATIO OR PRODUCT YOU REQUIRE TO BE THE RATIO OF THESE  Fixup

TWO DUMMY MT
NUMBERS.
Fixup

Fixup

FOR EXAMPLE, TO
DEFINE ETA,
Fixup

1) FIRST DEFINE
(MT=27) = (MT=27) + (SUM OF MT=102 THROUGH 116)    Fixup

2) NEXT DEFINE
(MT=333) = (MT=452)*(MT=18)
Fixup

3) LAST DEFINE
(MT=255) = (MT=333)/(MT=27)
Fixup

DO NOT FORGET TO
TURN ON THE CREATE SECTION OPTION (ON THE FIRST   Fixup

INPUT LINE) AND
INPUT THE FIRST TWO LINES OF SECTION MT=255 -      Fixup

OTHERWISE YOU WILL
NOT GET ANY ENDF/B FORMATTED OUTPUT.
Fixup

Fixup

THE ONLY SPECIAL
CONVENTIONS USED BY THIS PROGRAM IN CALCULATING   Fixup

RATIOS ARE WHEN
THE DENOMINATOR OF THE RATIO IS ZERO. IN THIS      Fixup

CASE IF THE
NUMERATOR IS ALSO ZERO THE RATIO IS DEFINED TO BE ONE. Fixup

IN THIS CASE IF
THE NUMERATOR IS NOT ZERO THE RATIO IS DEFINED     Fixup

TO BE ZERO.
Fixup

Fixup

ENDF/B
FORMAT
Fixup

=============
Fixup

THIS PROGRAM MAY
BE USED WITH DATA IN ANY VERSION OF THE ENDF/B    Fixup

FORMAT (I.E.
ENDF/B-I, II, III, IV, V OR VI FORMAT). SINCE A       Fixup

PAGING SYSTEM IS
USED STORE CROSS SECTION TABLES ON SCRATCH FILES  Fixup

THERE IS NO
LIMIT TO THE SIZE OF TABLES (E.G. THE TOTAL CROSS      Fixup

SECTION MAY BE
REPRESENTED BY 200,000 TABULATED POINTS).
Fixup

Fixup

WARNING
Fixup

=======
Fixup

(1) FOR EACH
SECTION OF CROSS SECTIONS (I.E. EACH MT, MF=3) IN     Fixup

THE ORIGINAL EVALUATION (I.E. ENDF/B DATA READ) ONE SECTION    Fixup

OF DATA WILL BE OUTPUT, UNLESS THE SECTION HAS BEEN DELETED.   Fixup

THIS INCLUDES ANY SECTIONS WHICH ARE NOT PRESENT IN THE
Fixup

ORIGINAL EVALUATION, BUT THE USER
INDICATES (BY INPUT) SHOULD
Fixup

BE CREATED.
Fixup

Fixup

THE PROGRAM WILL NOT OUTPUT ANY SECTION RECONSTRUCTED BY       Fixup

SUMMATION UNLESS THE CORRESPONDING SECTION (MT NUMBER) IS      Fixup

PRESENT IN THE ORIGINAL EVALUATION OR USER INPUT INDICATES     Fixup

SHOULD BE CREATED AND OUTPUT. THIS IS (A) BECAUSE THE
Fixup

PROGRAM CANNOT DEFINE THE PARAMETERS TO APPEAR ON THE FIRST    Fixup

TWO LINES OF THE SECTION, (B) TO AVOID OUTPUTTING TOO MUCH     Fixup

DATA WHICH THE USER MAY NOT BE INTERESTED IN.
Fixup

Fixup

(2) FOR ANY
SECTIONS THAT DO NOT APPEAR IN THE ORIGINAL DATA THE   Fixup

USER MAY SPECIFY THAT THEY BE DEFINED BY SUMMATION. ANY SUCH   Fixup

SECTION MAY BE USED BE DEFINE SUBSEQUENT SUMS, BUT THE SECTION
Fixup

ITSELF WILL NOT BE OUTPUT (E.G. GENERALLY MT=27 AND 101 ARE    Fixup

NOT PRESENT IN EVALUATIONS. HOWEVER, THE BUILT-IN SUMMATION    Fixup

RULES OF THIS PROGRAM USES THE ENDF/B SUMMATION RULES TO       Fixup

DEFINE MT=27 AND 101, WHICH IN TURN ARE USED TO DEFINE THE     Fixup

NON-ELASTIC CROSS SECTION, MT=3. SECTIONS MT=27 AND 101 ARE    Fixup

NOT OUTPUT).
Fixup

Fixup

(3) ALL DATA IN
FILE 3 AND 23 MUST BE LINEARLY INTERPOLABLE. IF    Fixup

THE DATA IS NOT LINEARLY INTERPOLABLE THIS PROGRAM WILL
Fixup

TERMINATE.
Fixup

Fixup

PROGRAM
OPERATION
Fixup

=================
Fixup

ALL MAT NUMBER
ON AN ENDF/B TAPE ARE PROCESSED. EACH MAT IS
Fixup

TREATED SEPARATELY.
WITHIN EACH MAT, EACH SECTION BEFORE MF=3      Fixup

IS READ,
CHECKED/CORRECTED (BASED ON INPUT OPTIONS) AND OUTPUT.    Fixup

WHEN MF=3 IS
LOCATED ALL CROSS SECTIONS ARE READ, SECTIONS TO BE   Fixup

DELETED ARE
DELETED, SECTIONS WHICH ARE NOT PRESENTED AND USER     Fixup

INPUT INDICATES
SHOULD BE CREATED ARE CREATE, SECTIONS TO BE KEPT  Fixup

ARE
CHECKED/CORRECTED (BASED ON INPUT OPTIONS) AND WRITTEN TO A    Fixup

SCRATCH FILE.
NEXT, IF THE USER SPECIFIES THAT THEY SHOULD,
Fixup

SECTIONS ARE
RECONSTRUCTED. FINALLY ALL CROSS SECTIONS (OLD AND    Fixup

NEW) ARE OUTPUT.
WITHIN THE SAME MAT, EACH SECTION AFTER MF=3 IS   Fixup

READ,
CHECKED/CORRECTED (BASED ON INPUT OPTIONS) AND OUTPUT.       Fixup

Fixup

MF=3
Fixup

====
Fixup

THE TREATMENT OF
THE CROSS SECTIONS REQUIRES UP TO 4 PASSES FOR    Fixup

CROSS SECTIONS.
IN THE PROGRAM THEY CORRESPOND TO SUBROUTINES      Fixup

PASS1, PASS2,
PASS3 AND PASS4. THE ORIGINAL AND FINAL ENDF/B DATA  Fixup

FILES, 5 SCRATCH
FILES AND 3 IN CORE ARRAYS ARE USED. OPERATIONS   Fixup

PERFORMED DURING
EACH PASS ARE,
Fixup

Fixup

PASS1
Fixup

=====
Fixup

READ ALL CROSS
SECTIONS FROM ITAPE. DELETED ANY SECTIONS. CREATE   Fixup

ANY SECTIONS.
CHECK/CORRECT THEM AND WRITE THEM TO SCRATCH FILE.   Fixup

DATA IS READ
INTO ARRAY A, TRANSFERRED TO ARRAY C (AFTER EDITING)  Fixup

AND OUTPUT TO
ISCRC FROM ARRAY C.
Fixup

ITAPE  - UNIT ORIGINAL ENDF/B DATA IS READ
FROM.
Fixup

ISCRC  - SCRATCH UNIT THAT EDITED DATA IS
WRITTEN ON.
Fixup

TABA   - ARRAY INTO WHICH ORIGINAL DATA
IS READ.
Fixup

TABC   - ARRAY INTO WHICH EDITED DATA IS
TRANSFERRED TO AND
Fixup

FROM WHICH IT IS WRITTEN TO ISCRC.
Fixup

Fixup

PASS2
Fixup

=====
Fixup

IF A UNIFORM
ENERGY GRID IS REQUESTED IT IS CREATED DURING THIS    Fixup

PASS. FIRST ALL
OF THE CROSS SECTIONS FROM PASS1 ARE READ AND A    Fixup

UNIFORM ENERGY
GRID IS CREATED = ALL ENERGIES THAT ARE INCLUDED    Fixup

IN AT LEAST ONE
SECTION (MT) OF CROSS SECTIONS.
Fixup

ISCRA  - SCRATCH UNIT CONTAINING UNIFORM ENERGY
GRID.
Fixup

ISCRB  - SCRATCH UNIT CONTAINING UNIFORM ENERGY
GRID.
Fixup

ISCRC  - SCRATCH UNIT THAT EDITED DATA IS READ
FROM.
Fixup

TABA   - ARRAY CONTAINING UNIFORM ENERGY
GRID.
Fixup

TABB   - ARRAY CONTAINING UNIFORM ENERGY
GRID.
Fixup

TABC   - ARRAY CONTAINING EDITED
DATA.
Fixup

Fixup

THE UNIFORM
ENERGY GRID ENDS UP ON ISCRB. NEXT EACH SECTION OF     Fixup

CROSS SECTIONS
FROM PASS1 IS READ FROM ISCRC, INTERPOLATED TO      Fixup

THE UNIFORM
ENERGY GRID AND OUTPUT TO ISCRA. FINALLY ISCRA AND     Fixup

ISCRC ARE SWITCH, SO
THAT AT THE END OF THIS PASS THE DATA WILL    Fixup

AGAIN BE ON
ISCRC (EXACTLY AS AT THE END OF PASS1), WITH UPDATED   Fixup

POINT
COUNTS.
Fixup

ISCRA  - SCRATCH UNIT THAT UNIFORM ENERGY GRID
DATA IS WRITTEN ON. Fixup

ISCRB  - SCRATCH UNIT CONTAINING UNIFORM ENERGY
GRID.
Fixup

ISCRC  - SCRATCH UNIT THAT EDITED DATA IS READ
FROM.
Fixup

TABA   - ARRAY CONTAINING UNIFORM ENERGY
GRID DATA.
Fixup

TABB   - ARRAY CONTAINING UNIFORM ENERGY
GRID.
Fixup

TABC   - ARRAY CONTAINING EDITED
DATA.
Fixup

Fixup

PASS3
Fixup

=====
Fixup

SUMMATION CROSS
SECTIONS ARE DEFINED BY READING DATA FROM ISCRC    Fixup

AND MERGING THEM
ONTO ISCRA. THE FIRST SECTION THAT CONTRIBUTES    Fixup

TO A SUM IS
MERELY COPIED FROM C TO A. IF MORE SECTIONS WILL       Fixup

CONTRIBUTE TO
THE SUM THE DATA IN A IS TRANSFERRED TO B, A
Fixup

SECTION OF DATA
FROM C IS ADDED TO THE DATA IN B AND STORED IN     Fixup

A. THE CYLE OF
ADDED C AND B TO A, FOLLOWED BY MOVING A TO B       Fixup

IS CONTINUED
UNTIL ALL CONTRIBUTING SECTIONS HAVE BEEN ADDED.      Fixup

THE SUM IS THEN
COPIED FROM A TO D. IF NEWLY CONSTRUCTED SECTION   Fixup

IS REQUIRED FOR
ANY LATER SUMMUATIONS IT IS ALSO COPIED TO E.      Fixup

THE CYCLE OF
ADDED SECTIONS FROM C AND B TO A IS REPEATED FOR      Fixup

EACH REQUIRED
SUMMATION REACTION. IN ADDITION TO SECTIONS FROM     Fixup

C, AFTER THE
FIRST SUMMATION SECTIONS MAY ALSO BE ADDED TO A       Fixup

FROM E (THE
CONTRIBUTION OF NEW RECONSTRUCTED CROSS SECTIONS).     Fixup

WHEN ALL
REQUIRED SECTIONS HAVE BEEN RECONSTRUCTED THE NEW
Fixup

SECTIONS WILL BE
ON E AND THE ORIGINAL SECTIONS ON C.
Fixup

ISCRC  - SCRATCH FILE FROM WHICH ORIGINAL DATA
IS READ.
Fixup

ISCRA  - SCRATCH FILE ONTO WHICH SUM FOR ONE
SECTION IS WRITTEN.
Fixup

ISCRD  - SCRATCH FILE ONTO WHICH ALL SUM CROSS
SECTIONS ARE        Fixup

WRITTEN.
Fixup

ISCRE  - SCRATCH FILE ONTO WHICH ALL SUM CROSS
SECTIONS WHICH
Fixup

ARE REQUIRED FOR LATER SUMS ARE WRITTEN.
Fixup

ISCRB  - UTILITY SCRATCH FILE USED TO CREATE
SUM CROSS SECTIONS.   Fixup

TABA   - ARRAY INTO WHICH SUMS ARE
WRITTEN.
Fixup

TABB   - ARRAY INTO WHICH PARTIAL SUMS
ARE WRITTEN.
Fixup

TABC   - ARRAY INTO WHICH ORIGINAL DATA
IS READ.
Fixup

Fixup

PASS4
Fixup

=====
Fixup

CROSS SECTIONS
ARE READ FROM ISCRC (ORIGINAL) AND ISCRD (NEW)      Fixup

AND ARE WRITTEN
IN THE ENDF/B FORMAT ON OTAPE. THE BEGINNING OF    Fixup

EACH SECTION OF
ORIGINAL DATA IS READ FROM ISCRC (TO DEFINE
Fixup

SECTION HEADER
INFORMATION). IF THIS MT HAS NOT BEEN RECOSTRUCTED  Fixup

ON ISCRD THE
ORIGINAL SECTION IS OUTPUT. IF THE SECTION HAS BEEN   Fixup

RECONSTRUCTED
THE ORIGINAL SECTION IS SKIPPED AND THE NEW SECTION  Fixup

IS OUTPUT.
Fixup

OTAPE  - OUTPUT DATA IN THE ENDF/B FORMAT.
Fixup

ISCRC  - SCRATCH FILE FROM WHICH ORIGINAL DATA
IS READ.
Fixup

ISCRD  - SCRATCH FILE FROM WHICH NEW DATA IS
READ.
Fixup

TABC   - ARRAY INTO WHICH CROSS SECTIONS
ARE READ FROM SCRATCH
Fixup

AND WRITTEN TO OTAPE
Fixup

Fixup

I/O FILE
DEFINITIONS
Fixup

====================
Fixup

UNIT   DESCRIPTION
Fixup

====   ===========
Fixup

2    INPUT
PARAMETERS.
Fixup

3    OUTPUT
REPORT.
Fixup

10    ORIGINAL DATA IN THE ENDF/B
FORMAT.
Fixup

11    FINAL DATA IN THE ENDF/B
FORMAT.
Fixup

12    SCRATCH FILE
Fixup

14    SCRATCH FILE
Fixup

15    SCRATCH FILE
Fixup

16    SCRATCH FILE
Fixup

17    SCRATCH FILE
Fixup

Fixup

OPTIONAL
STANDARD FILE NAMES (SEE SUBROUTINE FILIO1 AND FILIO2)    Fixup

===============================================================    Fixup

UNIT  FILE NAME   FORMAT
Fixup

====  ==========  ======
Fixup

2   FIXUP.INP    BCD
Fixup

3   FIXUP.LST    BCD
Fixup

10   ENDFB.IN     BCD
Fixup

11   ENDFB.OUT    BCD
Fixup

12-17  (SCRATCH)   BINARY
Fixup

Fixup

INPUT LINES
Fixup

===========
Fixup

LINE  COLUMNS  FORMAT  DESCRIPTION
Fixup

====  =======  ======  ===========
Fixup

1    1-14     14I1   INPUT OPTIONS AS DESCRIBED
ABOVE.
Fixup

EACH COLUMN OF THE INPUT LINE CONTROLS      Fixup

ONE OF THE TESTS/CORRECTIONS DESCRIBED      Fixup

ABOVE.
TESTS/CORRECTION 1-14 (NOT ALL       Fixup

IMPLEMENTED YET) CORRESPOND TO COLUMNS      Fixup

1-14 OF THIS INPUT LINE AND ARE TREATED     Fixup

AS FOLLOWS,
Fixup

= 0 - DO NOT PERFORM TEST/CORRECTION.       Fixup

= 1 - PERFORM TEST/CORRECTION.
Fixup

FOR MT EXCLUSION FROM THRESHOLD TESTS       Fixup

(COLUMN 2), DELETION (COLUMN 4), OR
Fixup

SUMMATION (COLUMN 5) THE INPUT OPTION       Fixup

MAY BE,
Fixup

= 1 - READ RULES FROM INPUT
Fixup

= 2 - USE BUILT-IN RULES
Fixup

2    1-60      A60   ENDF/B INPUT DATA FILENAME
Fixup

(STANDARD OPTION = ENDFB.IN)
Fixup

3    1-60      A60   ENDF/B OUTPUT DATA FILENAME
Fixup

(STANDARD OPTION = ENDFB.OUT)
Fixup

4-M    1-5      FREE   CHARACTER (S,D,T,R,*) FOLLOWED BY
BLANK OR  Fixup

FORM   MT NUMBER
Fixup

- THE ALLOWED CHARACTERS ARE,
Fixup

-
S OR BLANK = SUM (OR DIFFERENCES)
Fixup

- D = DELETE
Fixup

- T = NO THRESHOLD ENERGY CORRECTIONS       Fixup

-
R = RATIO
Fixup

- * = PRODUCT
Fixup

6-72
FREE   UP TO 10 LOWER
AND UPPER MT RANGES WHICH    Fixup

FORM   WILL BE USED TO
DEFINE THE RECONSTRUCTED
Fixup

CROSS SECTION OR TO DEFINE MT RANGES WHICH  Fixup

ARE EXCLUDED FROM THRESHOLD TESTS.
Fixup

Fixup

EACH MT NUMBER IS DEFINED BY A CONTINUOUS   Fixup

STRING OF DIGITS, POSSIBILITY PRECEEDED BY  Fixup

A - (MINUS SIGN). EACH MT NUMBER MUST BE    Fixup

BLANK OR OTHERWISE (NOT A DIGIT) DELIMITED. Fixup

Fixup

COLUMNS 6-72 MAY CONTAIN STRINGS OF DIGITS  Fixup

THE FIRST DIGIT STRING OF EACH PAIR MAY BE  Fixup

PRECEEDED BY A - (MINUS SIGN).
Fixup

Fixup

EACH LINE WILL BE INTERPRETED AS FOLLOWS,   Fixup

Fixup

*SUMMATION (OR DIFFERENCES)
Fixup

--------------------------
Fixup

COLUMNS 1-5 = S OR BLANK FOLLOWED BY
THE    Fixup

MT NUMBER TO BE DEFINED BY SUMMATION
Fixup

Fixup

COLUMNS 6-72 = UP TO 10 MT RANGE (PAIRS OF  Fixup

MT NUMBERS) TO BE USED TO DEFINED THE SUM.  Fixup

IF
THE FIRST MT NUMBER OF A PAIR IS
Fixup

NEGATIVE THE RANGE
OF MT NUMBERS IS
Fixup

SUBTRACTED - AT LEAST ONE RANGE MUST BE     Fixup

SPECIFIED.
Fixup

Fixup

*DELETIONS
Fixup

---------
Fixup

COLUMNS 1-5 = D FOLLOWED BY BLANKS
Fixup

Fixup

COLUMNS 6-72 CONTAIN UP TO 10 MT RANGE      Fixup

(PAIRS OF MT NUMBERS), EACH RANGE DEFINING  Fixup

A RANGE OF
MT NUMBERS TO BE DELETED
- AT    Fixup

LEAST ONE RANGE MUST BE SPECIFIED.
Fixup

Fixup

*EXCLUSION FROM THRESHOLD TESTS
Fixup

------------------------------
Fixup

COLUMNS 1=5 = T FOLLOWED BY BLANKS
Fixup

Fixup

COLUMNS 6-72 CONTAIN UP TO 10 MT RANGE      Fixup

(PAIRS OF MT NUMBERS), EACH RANGE DEFINING  Fixup

A RANGE OF
MT NUMBERS WHOSE
THRESHOLD
Fixup

ENERGY WILL NOT BE CHECKED - AT LEAST ONE   Fixup

RANGE MUST BE SPECIFIED.
Fixup

Fixup

*RATIO
Fixup

-----
Fixup

COLUMNS 1-5 = R FOLLOWED BY THE MT NUMBER   Fixup

TO BE DEFINED BY A RATIO
Fixup

Fixup

COLUMNS 6-72 CONTAINS 2 MT NUMBERS TO BE    Fixup

USED TO DEFINE THE RATIO.
Fixup

Fixup

*PRODUCT
Fixup

-----
Fixup

COLUMNS 1-5 = * FOLLOWED BY THE MT NUMBER   Fixup

TO BE DEFINED BY A PRODUCT
Fixup

Fixup

COLUMNS 6-72 CONTAINS 2 MT NUMBERS TO BE    Fixup

USED TO DEFINE THE PRODUCT.
Fixup

Fixup

CONVENTIONS
Fixup

-----------
Fixup

*UP TO 20 DELETIONS AND 20 SUMMATIONS OR     Fixup

RATIOS OR PRODUCTS MAY BE SPECIFIED.        Fixup

*ONLY 1 EXCLUSION FROM THRESHOLD TESTS       Fixup

MAY BE SPECIFIED (THE 1 LINE MAY CONTAIN    Fixup

UP TO 10 MT RANGES TO EXCLUDE FROM TESTS).  Fixup

*INPUT IS TERMINATED BY INPUTTNG 0 OR
Fixup

BLANK IN COLUMNS 1-72 (I.E. THE LAST
Fixup

INPUT LINE MUST BE BLANK).
Fixup

*THE
UPPER LIMIT OF EACH RANGE MUST BE AT    Fixup

LEAST AS BIG AS THE LOWER LIMIT (IN
Fixup

ABSOLUTE VALUE).
Fixup

*FOR
RECONSTRUCTION POSITIVE MT RANGES WILL
Fixup

BE ADDED TO THE SUM AND NEGATIVE MT RANGES  Fixup

WILL BE SUBTRACTED.
Fixup

*IF INPUT OPTION 2 (FIRST
INPUT LINE) IS
Fixup

0 THRESHOLD EXCLUSION IS NOT ALLOWED.       Fixup

*IF INPUT OPTION 4 (FIRST INPUT LINE) IS     Fixup

0 DELETIONS ARE NOT ALLOWED.
Fixup

*IF INPUT OPTION 5 (FIRST INPUT LINE) IS     Fixup

0 SUMMATIONS AND RATIOS ARE NOT ALLOWED.    Fixup

N-K
IF THE USER SPECIFIES THAT SECTIONS WHICH   Fixup

ARE NOT PRESENT IN THE ORIGINAL EVALUATION  Fixup

MAY BE CREATED, TWO LINES MUST BE INPUT FOR Fixup

EACH SECTION TO BE CREATED. THE TWO LINES   Fixup

DEFINE (C1, C2, L1 AND L2) FOR EACH OF THE  Fixup

FIRST TWO LINES OF THE SECTION TO BE
Fixup

CREATED. THE FIRST LINE ALSO DEFINES (MAT   Fixup

AND MT). (N1, N2) ARE ALWAYS ZERO ON THE    Fixup

FIRST LINE AND WILL BE CALCULATED BY THE    Fixup

PROGRAM FOR THE SECOND LINE.
Fixup

FIRST    1-11     E11.4  ZA OF SECTION TO BE CREATED
Fixup

LINE    12-22     E11.4  AWRE OF SECTION TO BE CREATED
Fixup

23-33
I11   L1 OF SECTION TO
BE CREATED
Fixup

34-44      I11   L2 OF SECTION TO BE CREATED
Fixup

45-48
I4    MAT OF
SECTION TO BE CREATED
Fixup

49-51
I3    MT OF SECTION
TO BE CREATED
Fixup

SECOND    1-11     E11.4  C1 OF SECTION TO BE CREATED
Fixup

LINE    12-22     E11.4  C2 OF SECTION TO BE CREATED
Fixup

23-33
I11   L1 OF SECTION TO
BE CREATED
Fixup

34-44
I11   L2 OF SECTION TO
BE CREATED
Fixup

*PAIRS OF LINES MAY BE IN ANY MAT/MT ORDER   Fixup

(E.G., THEY NEED NOT BE IN ASCENDING
Fixup

MAT/MT ORDER).
Fixup

*UP TO 50 PAIRS OF LINES MAY BE USED TO      Fixup

DEFINE SECTIONS TO BE CREATED. THE LIST     Fixup

IS TERMINATED WHEN THE FIRST LINE OF A      Fixup

PAIR CONTAINS A ZERO (OR BLANK) MAT AND/OR  Fixup

MT.
Fixup

M-N
IF THE USER SPECIFIES THAT ENERGIES WHICH   Fixup

ARE NOT PRESENT IN THE ORIGINAL EVALUATION  Fixup

MAY BE INSERTED, ONE LINE MUST BE INPUT FOR Fixup

EACH ENERGY TO BE INSERTED.
Fixup

1-11    E11.4   ENERGY TO BE INSERTED
Fixup

12-15
I4     MAT IN
WHICH TO INSERT ENERGY = 0 = ALL     Fixup

16-18
I3     MT IN
WHICH TO INSERT ENERGY = 0 = ALL      Fixup

*UP TO 50 (ENERGY, MAT, MT) LINES MAY BE     Fixup

USED. THE LIST IS TERMINATED BY A BLANK     Fixup

LINE.
Fixup

*INPUT
MAY BE IN ANY (ENERGY, MAT, MT)       Fixup

ORDER.
Fixup

*ENERGY POINTS CAN ONLY BE INSERTED WITHIN   Fixup

THE
ORIGINAL ENERGY RANGE
OF A SECTION -
Fixup

THIS OPTION CANNOT BE USED TO EXTEND THE    Fixup

CROSS SECTION EITHER BELOW OR ABOVE THE     Fixup

ORIGINAL
TABULATED ENERGY RANGE.
Fixup

Fixup

EXAMPLE INPUT
NO. 1
Fixup

===================                                                Fixup

(1) USE OPTIONS
1-11 (ALL OPTIONS, EXCEPT INSERT ENERGY POINTS)    Fixup

(2) DELETE
MT=900 (FOR EXAMPLE PURPOSES ONLY)
Fixup

(3) DEFINE THE
FOLLOWING MT NUMBERS TO BE RECONSTRUCTED,
Fixup

(MT=  4) = THE SUM OF MT= 51
THROUGH  91
Fixup

(MT=103) = THE SUM OF MT=700 THROUGH 718 (NOT 719)
Fixup

(MT=104) = THE SUM OF MT=720 THROUGH 738 (NOT 739)
Fixup

(MT=105) = THE SUM OF MT=740 THROUGH 758 (NOT 759)
Fixup

(MT=106) = THE SUM OF MT=760 THROUGH 778 (NOT 779)
Fixup

(MT=107) = THE SUM OF MT=780 THROUGH 798 (NOT 799)             Fixup

(MT=101) = THE SUM OF MT=102 THROUGH 114
Fixup

(MT= 18) = (MT=19) + (MT=20 AND 21) + (MT=38)
Fixup

(IF TOTAL FISSION, MT=18, IS NOT PRESENT, DEFINE    Fixup

IT BY SUMMING FIRST, SECOND, ETC. CHANCE - NOTE     Fixup

THAT THIS MUST BE DONE IN THIS ORDER, SINCE THE     Fixup

NEXT SUM INVOLVES USING MT=18.
Fixup

(MT= 27) = THE SUM OF MT= 18 AND 101
Fixup

(MT=101 RECONSTRUCTED ABOVE USED IN SUM).
Fixup

(MT=  3) = THE SUM OF
(MT=4)+(MT=6-9)+(MT=16-17)+(MT=22-37)+   Fixup

(MT=41-45)
Fixup

(MT=4 AND 27 RECONSTRUCTED ABOVE USED IN SUM).      Fixup

(MT= 19) = (MT=18) - (MT=20 AND 21) - (MT=38)
Fixup

(DEFINE FIRST CHANGE FISSION BY SUBTRACTION TO      Fixup

ALLOW RESONANCE CONTRIBUTION FROM MT=18 TO BE       Fixup

INCLUDED IN MT=19).
Fixup

(MT=  1) = THE SUM OF MT=2
AND 3
Fixup

(MT=3 RECONSTRUCTED ABOVE USED IN SUM).
Fixup

(4) THRESHOLD ENERGIES
OF THE FOLLOWING MT NUMBERS WILL NOT BE      Fixup

TESTED OR CORRECTED.
Fixup

MT=1, 4, 18, 19, 91, 103 THROUGH 114.
Fixup

(5) DEFINE MT=254 TO
BE THE CAPTURE TO FISSION RATIO (MT=102/18)    Fixup

(6) CREATE
MAT=1300/MT=254 - NOTE, THIS IS NECESSARY IN ORDER TO    Fixup

HAVE THE CAPTURE TO FISSION RATIO OUTPUT IN THE ENDF/B FORMAT   Fixup

Fixup

NOTE, ON THE
FOLLOWING INPUT LINES THE CHARACTERS = ( ) + , HAVE   Fixup

BEEN USED ONLY
TO MAKE THE INPUT MORE READABLE - THESE CHARACTERS  Fixup

WILL BE SKIPPED
BY THE PROGRAM IN READING
INPUT - THE RESULTS      Fixup

WOULD BE THE
SAME IF THESE CHARACTERS WERE OMITTED, AS LONG AS     Fixup

ALL OF THE MT
NUMBERS ARE DELIMITED, I.E., THERE IS AT LEAST ONE   Fixup

NON-DIGITAL
CHARACTER BETWEEN MT NUMBERS. NOTE, THAT - (MINUS      Fixup

SIGN) IS
IMPORTANT AND IS USED DURING INPUT TO DEFINE MT RANGES    Fixup

WHICH SHOULD BE
SUBTRACTED, E.,G., SEE THE DEFINITION OF MT=19.    Fixup

Fixup

READ FILE
/ENDFB6/K300/LEAD.IN AND WRITE /ENDFB6/K300/LEAD.OUT     Fixup

Fixup

THE FOLLOWING 21
INPUT LINES ARE REQUIRED.
Fixup

Fixup

11111111111                                                        Fixup

/ENDFB6/K300/LEAD.IN
Fixup

/ENDFB6/K300/LEAD.OUT
Fixup

D900
Fixup

4=( 51, 91)
Fixup

103=(700,718)
Fixup

104=(720,738)
Fixup

105=(740,758)
Fixup

106=(760,778)
Fixup

107=(780,798)
Fixup

101=(102,114)
Fixup

18=(
19, 19)+( 20, 21)+( 38, 38)
Fixup

27=(
18, 18)+(101,101)
Fixup

3=(  4,  4)+(  6,
9)+( 16, 17)+( 22, 37)+( 41, 45)
Fixup

19=(
18, 18)-( 20, 21)-( 38, 38)
Fixup

1=(  2,  3)
Fixup

T    (  1,
1) (  4,  4) ( 18, 19) ( 91, 91) (103,114)
Fixup

R254=(102/
18)
Fixup

(BLANK LINE TO TERMINATE SUMMATION/DELETION RULES)    Fixup

2.00400+ 3
0.00000+ 0
0
01300254
Fixup

0.00000+ 0
0.00000+ 0
0
0
Fixup

(BLANK LINE TO TERMINATE SECTION CREATION RULES)      Fixup

Fixup

NOTE, THE
DELETION AND THRESHOLD EXCLUSION LINES MAY APPEAR IN     Fixup

IN ANY ORDER.
HOWEVER, SUMMATION AND RATIO RULES MUST APPEAR IN    Fixup

THE ORDER IN
WHICH YOU WANT THEM TO BE EXECUTED - E.G., THE
Fixup

ABOVE INPUT WILL
FIRST RECONSTRUCT MT=4, WHICH CAN THEN BE USED    Fixup

TO CONTRIBUTE TO
THE FOLLOWING SUM TO DEFINE MT=3, WHICH IN TURN   Fixup

CAN THEN BE USED
TO CONTRIBUTE TO THE FOLLOWING SUM TO DEFINE      Fixup

MT=1. IF THE
ORDER OF THE INPUT LINES IS CHANGED SUCH THAT MT=3    Fixup

IS RECONSTRUCTED
BEFORE MT=4, THE ORIGINAL MT=4 WILL BE USED IN    Fixup

THE SUMMATION TO
DEFINE MT=3. THE SAME RULES APPLY TO CALCULATING  Fixup

RATIOS, IF
EITHER THE NUMERATOR OR DENOMINATOR IS TO BE DEFINED    Fixup

BY SUMMATION,
THIS SHOULD BE DONE BEFORE DEFINING THE RATIO BY     Fixup

INPUT
PARAMETERS.
Fixup

Fixup

EXAMPLE INPUT
NO. 2
Fixup

===================
Fixup

(1) USE OPTIONS
1-11 (ALL OPTIONS, EXCEPT INSERT ENERGY POINTS)    Fixup

(2) USE BUILT-IN
TABLES FOR SUMMATION/DELETION/THRESHOLD EXCLUSION Fixup

(THIS ONLY REQUIRES COLUMNS 2, 4 AND 5 TO BE SET =2 ON THE     Fixup

FIRST INPUT LINE. THE BUILT-IN RULES EXACTLY CORRESPOND TO     Fixup

THE INPUT ABOVE UNDER EXAMPLE NO. 1, EXCEPT THAT NO MT NUMBERS
Fixup

WILL BE DELETED.
Fixup

(3) IF NOT
PRESENT, CREATE MAT=1300/MT=1
Fixup

Fixup

USE THE STANDARD
FILE NAMES ENDFB.IN AND ENDFB.OUT (THIS CAN BE    Fixup

DONE BY LEAVING THE SECOND AND THIRD
INPUT LINES BLANK).
Fixup

Fixup

THE FOLLOWING 6
INPUT LINES ARE REQUIRED.
Fixup

Fixup

12122111111
Fixup

Fixup

Fixup

2.00400+ 3
0.00000+ 0
0
01300  1
Fixup

0.00000+ 0
0.00000+ 0
0
0
Fixup

(BLANK LINE TO TERMINATE SECTION CREATION RULES)      Fixup

Fixup

EXAMPLE INPUT
NO. 3
Fixup

===================
Fixup

(1) USE OPTIONS
1-10 (ALL OPTIONS PRESENTLY IMPLEMENTED, EXCEPT    Fixup

DO NOT ALLOW SECTION CREATION AND INSERT ENERGY POINTS).       Fixup

(2) USE BUILT-IN
TABLES FOR SUMMATION/DELETION/THRESHOLD EXCLUSION Fixup

(THIS ONLY REQUIRES COLUMNS 2, 4 AND 5 TO BE SET =2 ON THE     Fixup

FIRST INPUT LINE. THE BUILT-IN RULES EXACTLY CORRESPOND TO     Fixup

THE INPUT ABOVE UNDER EXAMPLE NO. 1, EXCEPT THAT NO MT NUMBERS
Fixup

WILL BE DELETED.
Fixup

(3) DO NOT
CREATE ANY SECTIONS.
Fixup

Fixup

READ FILE
/ENDFB6/K300/LEAD.IN AND WRITE /ENDFB6/K300/LEAD.OUT     Fixup

Fixup

THE FOLLOWING 3
INPUT LINES ARE REQUIRED.
Fixup

Fixup

1212211111
Fixup

/ENDFB6/K300/LEAD.IN
Fixup

/ENDFB6/K300/LEAD.OUT
Fixup

Fixup

EXAMPLE INPUT
NO. 4
Fixup

===================
Fixup

SAME AS EXAMPLE
NO. 3, ABOVE, EXCEPT INSERT AN ENERGY POINT AT     Fixup

THERMAL FOR ALL
REACTIONS WHICH SPAN THE THERMAL
ENERGY RANGE.     Fixup

Fixup

USE THE STANDARD
FILE NAMES ENDFB.IN AND ENDFB.OUT (THIS CAN BE    Fixup

DONE BY LEAVING
THE SECOND AND THIRD INPUT LINES BLANK).
Fixup

Fixup

THE FOLLOWING 5
INPUT LINES ARE REQUIRED.
Fixup

Fixup

121221111101
Fixup

Fixup

Fixup

2.53000-
2   0  0
Fixup

(BLANK LINE TO TERMINATE ENERGY INSERTS)
Fixup

Fixup

WARNING
Fixup

=======
Fixup

ALTHOUGH THIS
PROGRAM IS DESIGNED TO ALLOW REACTIONS TO BE DEFINED Fixup

BY ADDING OR
SUBTRACTING REACTIONS THE USER SHOULD ALWAYS TRY TO   Fixup

DEFINE REACTIONS
BY SUMMING TO AVOID NEGATIVE CROSS SECTIONS. FOR  Fixup

EXAMPLE, IT IS
POSSIBLE TO CALCULATE MT=3 AND DEFINE MT=1 AS THE   Fixup

SUM OF MT=2 AND
3 (THE RECOMMENDED APPROACH AS USED IN THE ABOVE   Fixup

INPUT).
ALTERATIVELY IT IS POSSIBLE TO CALCULATE MT=1 AND DEFINE   Fixup

MT=3 AS MT=1
MINUS MT=2 (THIS APPROACH IS NOT RECOMMENDED).
Fixup

Fixup

THE ONLY BUILT-IN
SUMMATION RULE THAT USES SUBTRACTION IS THE      Fixup

CALCULATION OF
THE FIRST CHANGE FISSION (MT=19) AS THE TOTAL       Fixup

FISSION (MT=18)
MINUS THE SECOND, THIRD AND FOURTH CHANGE FISSION  Fixup

(MT=20, 21, 38).
THIS HAS BEEN DONE TO ALLOW THE RESONANCE
Fixup

CONTRIBUTION,
CALCULATED BY MANY CODES AND INCLUDED IN MT=18,      Fixup

TO BE
CONSISTENTLY INCLUDED IN THE FIRST CHANCE FISSION.
Fixup

Fixup

=======================================================================
Fixup

=======================================================================
Groupie

Groupie

PROGRAM
GROUPIE
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VERSION 76-1
(NOVEMBER 1976)
Groupie

VERSION 79-1
(OCTOBER 1979) CDC-7600 AND CRAY-1 VERSION.           Groupie

VERSION 80-1
(MAY 1980) IBM, CDC AND CRAY VERSION
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VERSION 81-1
(JANUARY 1981) EXTENSION TO 3000 GROUPS
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VERSION 81-2
(MARCH 1981) IMPROVED SPEED
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VERSION 81-3
(AUGUST 1981) BUILT-IN 1/E WEIGHTING SPECTRUM
Groupie

VERSION 82-1
(JANUARY 1982) IMPROVED COMPUTER COMPATIBILITY
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VERSION 83-1
(JANUARY 1983)*MAJOR RE-DESIGN.
Groupie

*ELIMINATED COMPUTER DEPENDENT CODING.  Groupie

*NEW, MORE COMPATIBLE I/O UNIT NUMBERS. Groupie

*NEW MULTI-BAND LIBRARY BINARY FORMAT.  Groupie

VERSION 83-2
(OCTOBER 1983) ADDED OPTION TO ALLOW SIGMA-0 TO BE    Groupie

DEFINED EITHER AS MULTIPLES OF
Groupie

UNSHIELDED TOTAL CROSS SECTION IN EACH Groupie

GROUP,
OR POWERS OF 10 IN ALL GROUPS.
Groupie

VERSION 84-1
(APRIL 1984)   ADDED MORE BUILT
IN MULTIGROUP ENERGY  Groupie

STRUCTURES.
Groupie

VERSION 85-1
(APRIL 1985)  *UPDATED FOR ENDF/B-VI
FORMATS.
Groupie

*SPECIAL I/O ROUTINES TO GUARANTEE      Groupie

ACCURACY OF ENERGY.
Groupie

*DOUBLE PRECISION TREATMENT OF ENERGY   Groupie

(REQUIRED FOR NARROW RESONANCES).      Groupie

*MINIMUM TOTAL CROSS SECTION TREATMENT  Groupie

VERSION 85-2
(AUGUST 1985) *FORTRAN-77/H VERSION
Groupie

VERSION 86-1
(JANUARY 1986)*ENDF/B-VI FORMAT
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VERSION 86-2
(JUNE 1986)   *BUILT-IN
MAXWELLIAN, 1/E AND FISSION
Groupie

WEIGHTING SPECTRUM.                    Groupie

VERSION 88-1
(JULY 1988)
*OPTION...INTERNALLY DEFINE ALL I/O     Groupie

FILE NAMES (SEE, SUBROUTINES FILIO1    Groupie

FILIO2 FOR DETAILS).
Groupie

*IMPROVED BASED ON USER COMMENTS.       Groupie

VERSION 89-1
(JANUARY 1989)*PSYCHOANALYZED BY PROGRAM FREUD TO     Groupie

INSURE PROGRAM WILL NOT DO ANYTHING    Groupie

CRAZY.
Groupie

*UPDATED TO USE NEW PROGRAM CONVERT     Groupie

KEYWORDS.
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*ADDED
LIVERMORE CIVIC
COMPILER
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CONVENTIONS.
Groupie

VERSION 91-1
(JUNE 1991)   *INCREASED PAGE
SIZE FROM 1002 TO 5010  Groupie

POINTS
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*UPDATED BASED ON USER COMMENTS
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*ADDED FORTRAN SAVE OPTION
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*COMPLETELY CONSISTENT
ROUTINE TO READ  Groupie

FLOATING POINT NUMBERS.
Groupie

VERSION 92-1
(JANUARY 1992)*ADDED RESONANCE INTEGRAL CALCULATION - Groupie

UNSHIELDED AND/OR SHIELDED - FOR       Groupie

DETAILS SEE BELOW
Groupie

*INCREASED NUMBER OF ENERGY POINTS      Groupie

IN BUILT-IN SPECTRA - TO IMPROVE       Groupie

ACCURACY.
Groupie

*ALLOW SELECTION OF ZA/MF/MT OR
Groupie

MAT/MF/MT RANGES - ALL DATA NOT
Groupie

SELECTED IS SKIPPED ON INPUT AND       Groupie

NOT WRITTEN AS OUTPUT.
Groupie

*COMPLETELY CONSISTENT I/O ROUTINES -   Groupie

TO MINIMIZE COMPUTER DEPENDENCE.       Groupie

*NOTE, CHANGES IN INPUT PARAMETER       Groupie

FORMAT - FOR ZA/MF/MT OR MAT/MF/MT     Groupie

RANGES.
Groupie

VERSION 92-2
(JUNE 1992)   *MULTIBAND
PARAMETERS OUTOUT AS
Groupie

CHARACTER (RATHER THAN BINARY) FILE.   Groupie

VERSION 93-1
(APRIL 1993)  *INCREASED PAGE SIZE
FROM 5010 TO
Groupie

30000 POINTS
Groupie

*ELIMINATED COMPUTER DEPENDENCE.
Groupie

VERSION 94-1
(JANUARY 1994)*VARIABLE ENDF/B DATA FILENAMES
Groupie

TO ALLOW ACCESS TO FILE STRUCTURES     Groupie

(WARNING - INPUT PARAMETER FORMAT      Groupie

HAS
BEEN CHANGED)
Groupie

*CLOSE ALL FILES BEFORE TERMINATING     Groupie

(SEE, SUBROUTINE ENDIT)
Groupie

VERSION 95-1
(JANUARY 1994)*CORRECTED MAXWELLIAN WEIGHTING
Groupie

*CHANGING WEIGHTING SPECTRUM FROM       Groupie

0.1 TO 0.001 % UNCERTAINTY
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VERSION 96-1
(JANUARY 1996) *COMPLETE RE-WRITE
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*IMPROVED COMPUTER INDEPENDENCE
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*ALL DOUBLE PRECISION
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*ON SCREEN OUTPUT                      Groupie

*UNIFORM TREATMENT OF ENDF/B I/O       Groupie

*IMPROVED OUTPUT PRECISION
Groupie

*DEFINED SCRATCH FILE NAMES            Groupie

*UP TO 1000 GROUP MULTI-BAND
Groupie

CALCULATION (PREVIOUSLY 175)
Groupie

*MAXIMUM NUMBER OF GROUPS REDUCED      Groupie

FROM 3,000 TO 1,000
Groupie

*UP TO 1000 MATERIALS
Groupie

(PREVIOUSLY 100)
Groupie

*CORRECTED
USE OF MAXWELLIAN +
Groupie

1/E + FISSION SPECTRUM
Groupie

*ONLY 2 BAND VERSION DISTRIBUTED       Groupie

(CONTACT
AUTHOR FOR DETAILS)
Groupie

*DEFINED SCRATCH FILE NAMES
Groupie

VERSION 99-1
(MARCH 1999)   *CORRECTED
CHARACTER TO FLOATING       Groupie

POINT
READ FOR MORE DIGITS
Groupie

*UPDATED TEST FOR ENDF/B FORMAT
Groupie

VERSION BASED ON RECENT FORMAT CHANGE Groupie

*GENERAL IMPROVEMENTS BASED ON
Groupie

USER FEEDBACK
Groupie

VERSION 99-2
(JUNE 1999)    *ASSUME
ENDF/B-VI, NOT V, IF MISSING
Groupie

MF=1, MT-451.
Groupie

VERS. 2000-1
(FEBRUARY 2000)*ADDED MF=10, ACTIVATION CROSS SECTION Groupie

PROCESSING.
Groupie

*GENERAL IMPROVEMENTS BASED ON
Groupie

USER FEEDBACK
Groupie

VERS. 2002-1
(FEBRUARY 2002)*ADDED TART 700 GROUP STRUCTURE
Groupie

*ADDED VARIABLE SIGMA0 INPUT OPTION    Groupie

(MAY 2002)
*OPTIONAL INPUT PARAMETERS
Groupie

(NOV. 2002)
*ADDED SAND-II EXTENDED DOWN TO
Groupie

1.0E-5 EV.
Groupie

(JUNE 2003)
*CORRECTED SAND-II 620 AND 640 GROUP   Groupie

ENERGY BOUNDARIES DEFINITIONS.
Groupie

VERS. 2004-1
(SEPT. 2004)  *INCREASED PAGE SIZE
FROM 30000 TO
Groupie

120000
POINTS
Groupie

*ADDED "OTHER" AS ADDITIONAL REACTION   Groupie

TO IMPROVE MULTI-BAND FITTING
Groupie

*ADDED
ITERATION FOR "BEST" PARTIAL     Groupie

PARAMETERS.
Groupie

*DO NOT SKIP LOW TOTAL ENERGY RANGES    Groupie

WHEN
DEFINING AVERAGE CROSS SECTIONS - Groupie

THIS MAKES OUTPUT COMPATIBLE WITH      Groupie

ANY STANDARD AVERAGING PROCEDURE       Groupie

VERS. 2005-1
(JAN. 2005)   *ADDED OPTION TO
CHANGE TEMPERATURE OF  Groupie

BUILT-IN STANDARD SPECTRUM.
Groupie

VERS. 2007-1
(JAN. 2007)   *CHECKED AGAINST
ALL ENDF/B-VII.    OF  Groupie

*INCREASED PAGE SIZE FROM 120,000 TO    Groupie

600,000 POINTS
Groupie

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OWNED,
MAINTAINED AND DISTRIBUTED BY
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------------------------------------
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THE NUCLEAR DATA
SECTION
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INTERNATIONAL
ATOMIC ENERGY AGENCY
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P.O. BOX
100
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A-1400, VIENNA,
AUSTRIA
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EUROPE
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ORIGINALLY
WRITTEN BY
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------------------------------------
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DERMOTT E. CULLEN
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UNIVERSITY OF
CALIFORNIA
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LAWRENCE
LIVERMORE NATIONAL LABORATORY
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L-159
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P.O. BOX
808
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LIVERMORE, CA
94550
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U.S.A.
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TELEPHONE  925-423-7359
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E. MAIL    [email-masked]
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WEBSITE    HTTP://WWW.LLNL.GOV/CULLEN1
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AUTHORS
MESSAGE
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---------------
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THE REPORT
DESCRIBED ABOVE IS THE LATEST PUBLISHED DOCUMENTATION   Groupie

FOR THIS
PROGRAM. HOWEVER, THE COMMENTS BELOW SHOULD BE CONSIDERED Groupie

THE LATEST
DOCUMENTATION INCLUDING ALL RECENT IMPROVEMENTS. PLEASE Groupie

READ ALL OF
THESE COMMENTS BEFORE IMPLEMENTATION, PARTICULARLY     Groupie

THE COMMENTS
CONCERNING MACHINE DEPENDENT CODING.
Groupie

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AT THE PRESENT
TIME WE ARE ATTEMPTING TO DEVELOP A SET OF COMPUTER Groupie

INDEPENDENT
PROGRAMS THAT CAN EASILY BE IMPLEMENTED ON ANY ONE     Groupie

OF A WIDE
VARIETY OF COMPUTERS. IN ORDER TO ASSIST IN THIS PROJECT Groupie

IT WOULD BE
APPECIATED IF YOU WOULD NOTIFY THE AUTHOR OF ANY       Groupie

COMPILER
DIAGNOSTICS, OPERATING PROBLEMS OR SUGGESTIONS ON HOW TO  Groupie

IMPROVE THIS
PROGRAM. HOPEFULLY, IN THIS WAY FUTURE VERSIONS OF    Groupie

THIS PROGRAM
WILL BE COMPLETELY COMPATIBLE FOR USE ON YOUR
Groupie

COMPUTER.
Groupie

Groupie

PURPOSE
Groupie

-------
Groupie

THIS PROGRAM IS
DESIGNED TO CALCULATE ANY COMBINATION OF
Groupie

THE FOLLOWING
QUANTITIES FROM LINEARLY INTERPOLABLE TABULATED      Groupie

CROSS SECTIONS
IN THE ENDF/B FORMAT
Groupie

Groupie

(1) UNSHIELDED
GROUP AVERAGED CROSS SECTIONS
Groupie

(2) BONDARENKO
SELF-SHIELDED GROUP AVERAGED CROSS SECTIONS
Groupie

(3) MULTI-BAND
PARAMETERS
Groupie

Groupie

IN THE FOLLOWING
FOR SIMPLICITY THE ENDF/B TERMINOLOGY--ENDF/B     Groupie

TAPE--WILL BE
USED. IN FACT THE ACTUAL MEDIUM MAY BE TAPE, CARDS,  Groupie

DISK OR ANY
OTHER MEDIUM.
Groupie

Groupie

ENDF/B
FORMAT
Groupie

-------------
Groupie

THIS PROGRAM
ONLY USES THE ENDF/B BCD OR CARD IMAGE FORMAT (AS     Groupie

OPPOSED TO THE
BINARY FORMAT) AND CAN HANDLE DATA IN ANY VERSION   Groupie

OF THE ENDF/B
FORMAT (I.E., ENDF/B-I, II,III, IV OR V FORMAT).     Groupie

Groupie

IT IS ASSUMED
THAT THE DATA IS CORRECTLY CODED IN THE ENDF/B       Groupie

FORMAT AND NO
ERROR CHECKING IS PERFORMED. IN PARTICULAR IT IS     Groupie

ASSUMED THAT THE
MAT, MF AND MT ON EACH CARD IS CORRECT. SEQUENCE  Groupie

NUMBERS (COLUMNS
76-80) ARE IGNORED ON INPUT, BUT WILL BE
Groupie

CORRECTLY OUTPUT
ON ALL CARDS. THE FORMAT OF SECTION MF=1, MT=451  Groupie

AND ALL SECTIONS
OF MF= 3 MUST BE CORRECT. THE PROGRAM COPIES ALL  Groupie

OTHER SECTION OF
DATA AS HOLLERITH AND AS SUCH IS INSENSITIVE TO   Groupie

THE CORRECTNESS
OR INCORRECTNESS OF ALL OTHER SECTIONS.
Groupie

Groupie

ALL FILE 3 CROSS
SECTIONS THAT ARE USED BY THIS PROGRAM MUST BE    Groupie

LINEARLY
INTERPOLABLE IN ENERGY AND CROSS SECTION (ENDF/B
Groupie

INTERPOLATION
LAW 2). FILE 3 BACKGROUND CROSS SECTIONS MAY BE MADE Groupie

LINEARLY
INTERPOLABLE USING PROGRAM LINEAR (UCRL-50400, VOL. 17,   Groupie

PART A). THE
RESONANCE CONTRIBUTION MAY BE ADDED TO THE BACKGROUND Groupie

CROSS SECTIONS
USING PROGRAM RECENT (UCRL-50400, VOL. 17, PART B). Groupie

IF THIS PROGRAM
FINDS THAT THE FILE 3 CROSS SECTIONS ARE NOT       Groupie

LINEARLY
INTERPOLABLE THIS PROGRAM WILL TERMINATE EXECUTION.       Groupie

Groupie

CONTENTS OF
OUTPUT
Groupie

------------------
Groupie

IF ENDF/B
FORMATTED OUTPUT IS REQUESTED ENTIRE EVALUATIONS ARE     Groupie

OUTPUT, NOT JUST
THE MULTI-GROUPED FILE 3 CROSS SECTIONS, E.G.     Groupie

ANGULAR AND
ENERGY DISTRIBUTIONS ARE ALSO INCLUDED.
Groupie

Groupie

DOCUMENTATION
Groupie

-------------
Groupie

THE FACT THAT
THIS PROGRAM HAS OPERATED ON THE DATA IS DOCUMENTED  Groupie

BY THE ADDITION
OF THREE COMMENT CARDS AT THE END OF EACH
Groupie

HOLLERITH
SECTION TO DESCRIBE THE GROUP STRUCTURE AND WEIGHTING    Groupie

SPECTRUM,
E.G.
Groupie

Groupie

********************** PROGRAM GROUPIE (2007-1) ***************    Groupie

UNSHIELDED GROUP
AVERAGES USING   69 GROUPS
(WIMS)
Groupie

MAXWELLIAN, 1/E
AND FISSION WEIGHTING SPECTRUM
Groupie

Groupie

THE ORDER OF ALL
SIMILAR COMMENTS (FROM LINEAR, RECENT AND SIGMA1) Groupie

REPRESENTS A
COMPLETE HISTORY OF ALL OPERATIONS PERFORMED ON       Groupie

THE DATA.
Groupie

Groupie

THESE COMMENT
CARDS ARE ONLY ADDED TO EXISTING HOLLERITH SECTIONS, Groupie

I.E., THIS
PROGRAM WILL NOT CREATE A HOLLERITH SECTION. THE FORMAT Groupie

OF THE HOLLERITH
SECTION IN ENDF/B-V DIFFERS FROM THE THAT OF      Groupie

EARLIER VERSIONS
OF ENDF/B. BY READING AN EXISTING MF=1, MT=451    Groupie

IT IS POSSIBLE
FOR THIS PROGRAM TO DETERMINE WHICH VERSION OF      Groupie

THE ENDF/B
FORMAT THE DATA IS IN. WITHOUT HAVING A SECTION OF      Groupie

MF=1, MT=451
PRESENT IT IS IMPOSSIBLE FOR THIS PROGRAM TO
Groupie

DETERMINE WHICH
VERSION OF THE ENDF/B FORMAT THE DATA IS IN, AND   Groupie

AS SUCH IT IS
IMPOSSIBLE FOR THE PROGRAM TO DETERMINE WHAT FORMAT  Groupie

SHOULD BE USED
TO CREATE A HOLLERITH SECTION.
Groupie

Groupie

REACTION
INDEX
Groupie

--------------
Groupie

THIS PROGRAM
DOES NOT USE THE REACTION INDEX WHICH IS GIVEN IN     Groupie

SECTION MF=1,
MT=451 OF EACH EVALUATION.
Groupie

Groupie

THIS PROGRAM DOES NOT
UPDATE THE REACTION INDEX IN MF=1, MT=451.   Groupie

THIS CONVENTION
HAS BEEN ADOPTED BECAUSE MOST USERS DO NOT
Groupie

REQUIRE A
CORRECT REACTION INDEX FOR THEIR APPLICATIONS AND IT WAS Groupie

NOT CONSIDERED
WORTHWHILE TO INCLUDE THE OVERHEAD OF CONSTRUCTING  Groupie

A CORRECT
REACTION INDEX IN THIS PROGRAM. HOWEVER, IF YOU REQUIRE  Groupie

A REACTION INDEX
FOR YOUR APPLICATIONS, AFTER RUNNING THIS PROGRAM Groupie

YOU MAY USE PROGRAM
DICTIN TO CREATE A CORRECT REACTION INDEX.     Groupie

Groupie

SECTION
SIZE
Groupie

------------
Groupie

SINCE THIS
PROGRAM USES A LOGICAL PAGING SYSTEM THERE IS NO LIMIT  Groupie

TO THE NUMBER OF
POINTS IN ANY SECTION, E.G., THE TOTAL CROSS      Groupie

SECTION MAY BE
REPRESENTED BY 200,000 DATA POINTS.
Groupie

Groupie

SELECTION OF
DATA
Groupie

-----------------
Groupie

THE PROGRAM
SELECTS MATERIALS TO BE PROCESSED BASED EITHER ON      Groupie

MAT (ENDF/B MAT
NO.) OR ZA. THE PROGRAM ALLOWS UP TO 100 MAT OR    Groupie

ZA RANGES TO BE
SPECIFIED. THE PROGRAM WILL ASSUME THAT THE
Groupie

ENDF/B TAPE IS
IN EITHER MAT OR ZA ORDER, WHICHEVER CRITERIA IS    Groupie

USED TO SELECT
MATERIALS, AND WILL TERMINATE WHEN A MAT OR ZA      Groupie

IS FOUND THAT IS
ABOVE THE RANGE OF ALL REQUESTS.
Groupie

Groupie

ENERGY ORDER AND
UNITS
Groupie

----------------------
Groupie

ALL ENERGIES
(FOR CROSS SECTIONS, WEIGHTING SPECTRUM OR GROUP      Groupie

BOUNDARIES) MUST
BE IN UNITS OF EV AND MUST BE IN ASCENDING
Groupie

NUMERICAL
ORDER.
Groupie

Groupie

ENERGY GRID
Groupie

-----------
Groupie

ALTHOUGH ALL REACTIONS
MUST TO LINEARLY INTERPOLABLE, THEY DO NOT
Groupie

ALL HAVE TO USE
THE SAME ENERGY GRID. EACH REACTION CAN BE GIVEN   Groupie

BY AN
INDEPENDENT ENERGY GRID. THIS PROGRAM WILL PROCEED FROM      Groupie

THE LOWEST TO
HIGHEST ENERGY SELECTING EACH ENERGY INTERVAL OVER   Groupie

WHICH ALL DATA,
FOR ANY GIVEN CALCULATION, ARE ALL LINEARLY
Groupie

INTERPOLABLE.
Groupie

Groupie

GROUP
STRUCTURE
Groupie

---------------
Groupie

THIS PROGRAM IS
DESIGNED TO USE AN ARBITRARY ENERGY GROUP
Groupie

STRUCTURE WHERE
THE ENERGIES ARE IN EV AND ARE IN INCREASING       Groupie

ENERGY ORDER.
THE MAXIMUM NUMBER OF GROUPS IS 1000.
Groupie

Groupie

THE USER MAY
INPUT AN ARBITRARY GROUP STRUCTURE OR THE USER MAY    Groupie

USE USE ONE OF
THE SEVEN BUILT-IN GROUP STRUCTURES.
Groupie

(0) 175 GROUP
(TART STRUCTURE)
Groupie

(1)  50 GROUP (ORNL STRUCTURE)
Groupie

(2) 126 GROUP
(ORNL STRUCTURE)
Groupie

(3) 171 GROUP
(ORNL STRUCTURE)
Groupie

(4) 620 GROUP
(SAND-II STRUCTURE, UP TO 18 MEV)
Groupie

(5) 640 GROUP
(SAND-II STRUCTURE, UP TO 20 MEV)
Groupie

(6)  69 GROUP (WIMS STRUCTURE)
Groupie

(7)  68 GROUP (GAM-I STRUCTURE)
Groupie

(8)  99 GROUP (GAM-II STRUCTURE)
Groupie

(9)  54 GROUP (MUFT STRUCTURE)
Groupie

(10)  28 GROUP (ABBN STRUCTURE)
Groupie

(11) 650 GROUP (TART
STRUCTURE)
Groupie

(12) 700 GROUP (TART
STRUCTURE)
Groupie

(13) 665 GROUP
(SAND-II STRUCTURE, 1.0e-5 eV, UP TO 18 MEV)
Groupie

(14) 685 GROUP
(SAND-II STRUCTURE, 1.0e-5 eV, UP TO 20 MEV)
Groupie

Groupie

GROUP
AVERAGES
Groupie

--------------
Groupie

THIS PROGRAM
DEFINES GROUP AVERAGED CROSS SECTIONS AS...
Groupie

Groupie

(INTEGRAL E1 TO E2) (SIGMA(E)*S(E)*WT(E)*DE)
Groupie

AVERAGE =
-----------------------------------------
Groupie

(INTEGRAL E1 TO E2) (S(E)*WT(E)*DE)                      Groupie

WHERE...
Groupie

Groupie

AVERAGE  = GROUP AVERAGED CROSS SECTION
Groupie

E1, E2   = ENERGY LIMITS OF THE GROUP
Groupie

SIGMA(E) =
ENERGY DEPENDENT CROSS SECTION FOR ANY GIVEN REACTION   Groupie

S(E)     = ENERGY DEPENDENT
WEIGHTING SPECTRUM
Groupie

WT(E)    = ENERGY DEPENDENT
SELF-SHIELDING FACTOR.
Groupie

Groupie

ENERGY DEPENDENT
WEIGHTING SPECTRUM
Groupie

-----------------------------------
Groupie

THE ENERGY
DEPENDENT WEIGHTING SPECTRUM IS GIVEN BY AN ARBITRARY   Groupie

TABULATED
LINERLY INTERPOLABLE FUNCTION WHICH CAN BE DESCRIBED     Groupie

BY AN ARBITRARY
NUMBER OF POINTS. THIS ALLOWS THE USER TO
Groupie

SPECIFY ANY
DESIRED WEIGHTING SPECTRUM TO ANY GIVEN DEGREE OF      Groupie

ACCURACY.
REMEMBER THAT THE PROGRAM WILL ASSUME THAT THE SPECTRUM  Groupie

IS LINEARLY
INTERPOLABLE BETWEEN TABULATED POINTS. THEREFORE THE   Groupie

USER SHOULD USE
ENOUGH POINTS TO INSURE AN ADEQUATE REPRESENTATION Groupie

OF THE SPECTRUM
BETWEEN TABULATED DATA POINTS.
Groupie

Groupie

THE PRESENT
VERSION OF THE CODE HAS THREE BULIT-IN WEIGHTING       Groupie

SPECTRA,
Groupie

Groupie

(1)
CONSTANT
Groupie

(2) 1/E
Groupie

(3) MAXWELLIAN =
E*EXP(-E/KT)/KT
(0.0 TO 4*KT)      Groupie

1/E        =
C1/E
(4*KT TO 67 KEV)
Groupie

FISSION    =
C2*EXP(-E/WA)*SINH(SQRT(E*WB)) (ABOVE 67 KEV)     Groupie

Groupie

KT     = 0.253
EV (293 KELVIN)
Groupie

WA     =
9.65E+5
Groupie

WB     =
2.29E-6
Groupie

C1, C2 = DEFINED TO MAKE SPECTRUM CONTINUOUS
Groupie

Groupie

FISSION SPECTRUM CONSTANTS FROM
Groupie

A.F.HENRY,
NUCLEAR REACTOR ANALYSIS, P. 11, MIT PRESS (1975)   Groupie

Groupie

UNSHIELDED GROUP
AVERAGES
Groupie

-------------------------
Groupie

FOR UNSHIELDED
AVERAGES THE SELF-SHIELDING FACTOR (WT(E)) IS SET   Groupie

TO UNITY. THIS
PROGRAM ALLOWS UP TO 1000 GROUPS.
Groupie

Groupie

SELF-SHIELDED
GROUP AVERAGES
Groupie

----------------------------
Groupie

IF SELF-SHIELDED
AVERAGES AND/OR MULTI-BAND PARAMETERS ARE
Groupie

CALCULATED THIS
PROGRAM ALLOWS UP TO 1000 GROUPS. SELF-SHIELDED    Groupie

AVERAGES AND/OR
MULTI-BAND PARAMETERS ARE CALCULATED FOR THE       Groupie

TOTAL, ELASTIC,
CAPTURE AND FISSION.                               Groupie

Groupie

FOR THE TOTAL,
ELASTIC, CAPTURE AND FISSION THE PROGRAM USES A     Groupie

WEIGHTING
FUNCTION THAT IS A PRODUCT OF THE ENERGY DEPENDENT       Groupie

WEIGHTING
SPECTRUM TIMES A BONDERENKO TYPE SELF-SHIELDING FACTOR.  Groupie

Groupie

WT(E) =
S(E)/(TOTAL(E)+SIGMA0)**N
Groupie

Groupie

WHERE...
Groupie

Groupie

S(E)     - ENERGY DEPENDENT
WEIGHTING SPECTRUM (DEFINED BY
Groupie

TABULATED VALUES AND LINEAR INTERPOLATION BETWEEN       Groupie

TABULATED VALUES).
Groupie

TOTAL(E) - ENERGY
DEPENDENT TOTAL CROSS SECTION FOR ONE MATERIAL   Groupie

(DEFINED BY TABULATED VALUES AND LINEAR INTERPOLATION   Groupie

BETWEEN TABULATED VALUES).
Groupie

SIGMA0   - CROSS SECTION TO REPRESENT THE
EFFECT OF ALL OTHER      Groupie

MATERIALS AND LEAKAGE (DEFINED WITHIN EACH GROUP TO BE  Groupie

A MULTIPLE OF THE UNSHIELDED TOTAL CROSS SECTION WITHIN Groupie

THAT GROUP OR POWERS OF 10 - INPUT OPTION).
Groupie

N        - A
POSITIVE INTEGER (0, 1, 2 OR 3).
Groupie

Groupie

THE PROGRAM WILL
USE ONE ENERGY DEPENDENT WEIGHTING SPECTRUM S(E)  Groupie

AND 25 DIFFERENT
BONDERENKO TYPE SELF-SHIELDING FACTORS (25 SIGMA0 Groupie

AND N
COMBINATIONS) TO DEFINE 25 DIFFERENT AVERAGE CROSS SECTIONS, Groupie

FOR EACH
REACTION, WITHIN EACH GROUP.
Groupie

Groupie

THE 25 WEIGHTING
FUNCTIONS USED ARE....
Groupie

(1)   - UNSHIELDED CROSS SECTIONS
(N=0)
Groupie

(2-22)-
PARTIALLY SHIELDED CROSS SECTIONS (N=1 ,VARIOUS SIGMA0)    Groupie

THE VALUES OF SIGMA0 USED WILL BE EITHER,
Groupie

(A) THE VALUES OF SIGMA0 THAT ARE USED VARY FROM 1024      Groupie

TIMES THE UNSHIELDED TOTAL CROSS SECTIONS IN STEPS OF 1/2  Groupie

DOWN TO 1/1024 TIMES THE UNSHIELDED TOTAL CROSS SECTION    Groupie

(A RANGE OF OVER 1 MILLION, CENTERED ON THE UNSHIELDED     Groupie

TOTAL CROSS SECTION WITHIN EACH GROUP).
Groupie

(B) THE SAME CONSTANT VALUES OF SIGMA0 IN EACH GROUP. THE  Groupie

VALUES OF SIGMA0 USED INCLUDE 40000, 20000, 10000, 7000,   Groupie

4000, 2000, 1000, 700, 400, 200, 100, 70, 40, 20, 10, 7,   Groupie

4, 2, 1, 0.7, 0.4 (A RANGE OF 100,000 SPANNING MORE THAN   Groupie

THE RANGE OF SIGMA0 VALUES THAT MAY BE ENCOUNTERED IN      Groupie

ACTUAL
APPLICATIONS)
Groupie

(23)  - TOTALLY SHIELDED FLUX WEIGHTED CROSS
SECTION
Groupie

(N=1, SIGMA0=0)
Groupie

(24)  - TOTALLY SHIELDED CURRENT WEIGHTED
CROSS SECTION
Groupie

(N=2, SIGMA0=0)
Groupie

(25)  - TOTALLY SHIELDED COSINE SQUARED
WEIGHTED CROSS SECTION
Groupie

(N=3, SIGMA0=0)                                            Groupie

Groupie

FOR ALL OTHER
REACTIONS (EXCEPT TOTAL, ELASTIC, CAPTURE AND
Groupie

FISSION) THE
PROGRAM WILL USE THE ENERGY DEPENDENT WEIGHTING       Groupie

SPECTRUM S(E) TO
DEFINE THE UNSHIELDED (BONDERENKO N=0)
Groupie

AVERAGED CROSS
SECTION WITHIN EACH GROUP.
Groupie

Groupie

CALCULATION OF
RESONANCE INTEGRALS
Groupie

----------------------------------
Groupie

IN A PURE
ELASTIC ISOTROPICALLY SCATTERING MATERIAL WITH A
Groupie

CONSTANT CROSS
SECTION THE SPECTRUM WILL BE 1/E AND THERE WILL     Groupie

BE NO
SELF-SHIELDING.
Groupie

Groupie

IN THIS CASE IF
THE CROSS SECTION VARIES WITH ENERGY THE
Groupie

SPECTRUM WILL
STILL BE 1/E AND THE SELF-SHIELDING FACTOR WILL      Groupie

BE EXACTLY
1/SIG-TOT(E) - WHERE SIG-TOT(E) = SIG-EL(E), SINCE      Groupie

THERE IS ONLY
SCATTERING.
Groupie

Groupie

IF WE HAVE AN
INFINITELY DILUTE AMOUNT OF A MATERIAL UNIFORMLY     Groupie

MIXED WITH A
PURE ELASTIC ISOTROPICALLY SCATTERING MATERIAL WITH   Groupie

A CONSTANT CROSS
SECTION THE STANDARD DEFINITION OF THE RESONANCE  Groupie

INTEGRAL CAN BE
USED TO DEFINE REACTION RATES FOR EACH REACTION.   Groupie

Groupie

THE RESONANCE
INTEGRAL IS DEFINED AS,
Groupie

Groupie

RI      = (INTEGRAL E1
TO E2) (SIGMA(E)*S(E)*WT(E)*DE)
Groupie

Groupie

WHERE
NORMALLY,
Groupie

S(E)    = 1/E
Groupie

WT(E)   = 1    - NO SELF-SHIELDING
Groupie

Groupie

FROM THE ABOVE
DEFINITION OF GROUP AVERAGED CROSS SECTIONS THE     Groupie

RESONANCE
INTEGRAL IS,
Groupie

Groupie

RI      = AVERAGE *
(INTEGRAL E1 TO E2) (S(E)*WT(E)*DE)
Groupie

Groupie

FOR A 1/E
SPECTRUM AND NO SELF-SHIELDING THIS REDUCES TO,
Groupie

Groupie

RI      = AVERAGE*
LOG(E2/E1)
Groupie

Groupie

IN ANY OTHER
SITUATION, INCLUDING ABSORPTION AND/OR ENERGY
Groupie

DEPENDENT CROSS
SECTIONS, THE SPECTRUM WILL NOT BE 1/E -
Groupie

ABSORPTION WILL
TEND TO DECREASE THE SPECTRUM PROGRESSIVELY
Groupie

MORE AT LOWER
ENERGIES - ENERGY DEPENDENCE OF THE CROSS SECTION    Groupie

WILL LEAD TO
SELF-SHIELDING.
Groupie

Groupie

HERE WE WILL NOT
ATTEMPT TO PERFORM A DETAILED SPECTRUM
Groupie

CALCULATION TO
ACCOUNT FOR ABSORPTION.
Groupie

Groupie

HOWEVER, WE WILL
EXTEND THE DEFINITION OF THE RESONANCE INTEGRAL   Groupie

TO ACCOUNT FOR
SELF-SHIELDING EFFECTS BY ALLOWING FOR INCLUSION    Groupie

OF
SELF-SHIELDING EFFECTS IN THE DEFINITION OF GROUP AVERAGES      Groupie

AND THEN
DEFINING THE RESONANCE INTEGRAL AS,
Groupie

Groupie

RI      = AVERAGE*
LOG(E2/E1)
Groupie

Groupie

IN ORDER TO
CALCULATE RESONANCE INTEGRALS YOU MUST FOLLOW THESE    Groupie

STEPS,
Groupie

Groupie

1) SELECT A 1/E
SPECTRUM - ON FIRST LINE OF INPUT PARAMETERS.      Groupie

2) SELECT THE
ENERGY BOUNDARIES - NORMALLY ONLY 1 GROUP FROM       Groupie

0.5 EV UP TO 20 MEV - HOWEVER, YOU ARE FREE TO SELECT ANY       Groupie

ENERGY RANGE THAT YOU WISH - YOU MAY EVEN SELECT MORE THAN      Groupie

1 GROUP MERELY BY SPECIFYING MORE THAN 1 GROUP AS INPUT -       Groupie

THIS CAN BE USED TO DEFINE THE CONTRIBUTIONS TO THE RESONANCE   Groupie

INTEGRAL FROM INDIVIDUAL ENERGY RANGES.
Groupie

3) SELECT THIS
OPTION FOR THE UNSHIELDED AND/OR SHIELDED OUTPUT    Groupie

LISTING - ON THE SECOND LINE OF INPUT PARAMETERS.
Groupie

Groupie

WHEN THIS OPTION IS
USED THE PROGRAM WILL CALCULATE GROUP AVERAGED Groupie

CROSS SECTIONS -
AS DEFINED ABOVE - PRIOR TO OUTPUT THE RESULTS    Groupie

WILL MERELY BE
MULTIPLIED BY THE WIDTH OF THE GROUP ASSUMING YOU   Groupie

HAVE SELECTED A
1/E SPECTRUM - THERE IS NO CHECK ON THIS - THE     Groupie

PROGRAM MERELY
MULTIPLIES THE GROUP AVERAGED CROSS SECTIONS BY,    Groupie

Groupie

LOG(E2/E1) -
WHERE E2 AND E1 ARE THE GROUP ENERGY BOUNDARIES.      Groupie

Groupie

WARNING - IT IS
UP TO YOU TO INSURE THAT YOU FOLLOW EXACTLY THE    Groupie

STEPS OUTLINED ABOVE IF YOU WISH TO OBTAIN MEANINGFUL    Groupie

RESULTS.
Groupie

Groupie

NOTE - OUTPUT IN
THE ENDF/B FORMAT IS ALWAYS GROUP AVERAGED CROSS  Groupie

SECTIONS, REGARDLESS OF WHETHER YOU ASK FOR AVERAGED CROSS  Groupie

SECTIONS OR RESONANCE INTEGRALS - THIS IS BECAUSE DATA IN   Groupie

THE ENDF/B FORMAT IS EXPLICITLY DEFINED TO BE CROSS
Groupie

SECTIONS.
Groupie

Groupie

RESONANCE INTEGRAL OUTPUT CAN ONLY BE OBTAINED IN THE       Groupie

LISTING FORMATS.
Groupie

Groupie

MINIMUM TOTAL
CROSS SECTION TREATMENT
Groupie

-------------------------------------
Groupie

SINCE THE
BONDARENKO SELF-SHIELDING DEPENDS ON 1/TOTAL CROSS       Groupie

SECTION, THE
ALGORITHM WILL BECOME NUMERICALLY UNSTABLE IF THE     Groupie

TOTAL CROSS SECTION IS
NEGATIVE (AS OCCURS IN MANY ENDF/B
Groupie

EVALUATIONS). IF
THE TOTAL IS LESS THAN SOME MINIMUM ALLOWABLE     Groupie

VALUE (DEFINE BY
OKMIN, PRESENTLY 1 MILLI-BARN) AN ERROR MESSAGE   Groupie

WILL BE PRINTED
AND FOR THE SELF-SHIELDING CALCULATION ALL ENERGY  Groupie

INTERVALS IN
WHICH THE TOTAL IS LESS THAN THE MINIMUM WILL BE      Groupie

IGNORED.
Groupie

Groupie

NOTE, FOR THE
UNSHIELDED CALCULATIONS ALL CROSS SECTIONS WILL BE   Groupie

CONSIDERED
WHETHER THEY ARE POSITIVE OR NEGATIVE. THEREFORE IF     Groupie

THE TOTAL CROSS
SECTION IS NEGATIVE OR LESS THAN THE MINIMUM       Groupie

VALUE THERE MAY
BE AN INCONSISTENCY BETWEEN THE UNSHIELDED AND     Groupie

THE
SELF-SHIELDED CROSS SECTIONS. IF THE TOTAL CROSS SECTION IS    Groupie

NEGATIVE AND
SELF-SHIELDED CROSS SECTIONS ARE CALCULATED THE       Groupie

PROGRAM WILL
PRINT AN ERROR MESSAGE INDICATING THAT THE SELF-      Groupie

SHIELDED RESULTS
ARE UNRELIABLE AND SHOULD NOT BE USED. THEREFORE  Groupie

IN THIS CASE THE
PROGRAM WILL NOT ATTEMPT TO MODIFY THE UNSHIELDED Groupie

RESULTS TO
ELIMINATE THE EFFECT OF NEGATIVE CROSS SECTIONS, SINCE  Groupie

THE UNSHIELDED
RESULTS ARE THE ONLY ONES WHICH TRULY REFLECT THE   Groupie

ACTUAL
INPUT.
Groupie

Groupie

RESOLVED
RESONANCE REGION
Groupie

-------------------------
Groupie

IN THE RESOLVED
RESONANCE REGION (ACTUALLY EVERYWHERE BUT IN THE   Groupie

UNRESOLVED
RESONANCE REGION) THE CROSS SECTIONS OUTPUT BY LINEAR-  Groupie

RECENT-SIGMA1
WILL BE ACTUAL ENERGY DEPENDENT CROSS SECTIONS AND   Groupie

THE CALCULATIONS
BY THIS PROGRAM WILL YIELD ACTUAL SHIELDED AND    Groupie

UNSHIELDED CROSS
SECTIONS.
Groupie

Groupie

UNRESOLVED
RESONANCE REGION
Groupie

---------------------------
Groupie

IN THE
UNRESOLVED RESONANCE REGION PROGRAM RECENT USES THE
Groupie

UNRESOLVED RESONANCE
PARAMETERS TO CALCULATE INFINITELY DILUTE     Groupie

AVERAGE CROSS
SECTIONS. THIS PROGRAM WILL MERELY READ THIS
Groupie

INFINITELY
DILUTE DATA AS IF IT WERE ENERGY DEPENDENT DATA AND     Groupie

GROUP AVERAGE
IT. AS SUCH THIS PROGRAM WILL PRODUCE THE CORRECT    Groupie

UNSHIELDED CROSS
SECTION IN THE UNRESOLVED RESONANCE REGION, BUT   Groupie

IT WILL NOT
PRODUCE THE CORRECT SELF-SHIELDING EFFECTS.
Groupie

Groupie

ACCURACY OF
RESULTS
Groupie

-------------------
Groupie

ALL INTEGRALS
ARE PERFORMED ANALYTICALLY. THEREFORE NO ERROR IS    Groupie

INTRODUCED DUE
TO THE USE OF TRAPAZOIDAL OR OTHER INTEGRATION      Groupie

SCHEME. THE
TOTAL ERROR THAT CAN BE ASSIGNED TO THE RESULTING      Groupie

AVERAGES IS JUST
THAT DUE TO THE ERROR IN THE CROSS SECTIONS       Groupie

AND ENERGY
DEPENDENT WEIGHTING SPECTRUM. GENERALLY SINCE THE       Groupie

THE ENERGY
DEPENDENT WEIGHTING SPECTRUM APPEARS IN BOTH THE
Groupie

NUMERATOR AND
THE DENOMINATOR THE AVERAGES RAPIDLY BECOME          Groupie

INSENSITIVE TO
THE WEIGHTING SPECTRUM AS MORE GROUPS ARE USED.     Groupie

SINCE THE
WEIGHTING SPECTRUM IS LOADED IN THE PAGING SYSTEM THE    Groupie

USER CAN
DESCRIBE THE SPECTRUM TO ANY REQUIRED ACCURACY USING      Groupie

ANY NUMBER OF
ENERGY VS. SPECTRUM PAIRS.
Groupie

Groupie

MULTI-BAND
PARAMETERS
Groupie

---------------------
Groupie

MULTI-BAND
PARAMETERS ARE CALCULATED FOR THE TOTAL, ELASTIC,       Groupie

CAPTURE AND
FISSION REACTIONS. WITH THE NUMBER OF GROUPS THAT      Groupie

ARE NORMALLY
USED (SEE BUILT IN GROUP STRUCTURES) ALL OTHER
Groupie

REACTIONS RESULT
IN A NEGLIGABLE AMOUNT OF SELF-SHIELDING. AS      Groupie

SUCH THEIR
EQUIVALENT BAND CROSS SECTION WILL MERELY BE THEIR      Groupie

UNSHIELDED VALUE
WITHIN EACH BAND.
Groupie

Groupie

FOR ANY GIVEN
EVALUATION, WITHIN ANY GIVEN GROUP THIS PROGRAM      Groupie

WILL GENERATE
THE MINIMUM NUMBER OF BANDS REQUIRED WITHIN THAT     Groupie

GROUP. AS OUTPUT
TO THE COMPUTER READABLE DISK FILE THE BAND       Groupie

PARAMETERS FOR
EACH EVALUATION WILL BE FORMATTED TO HAVE THE       Groupie

SAME NUMBER OF
BANDS IN ALL GROUPS (WITH ZERO WEIGHT FOR SOME      Groupie

BANDS WITHIN ANY
GROUP). THE USER MAY DECIDE TO HAVE OUTPUT
Groupie

EITHER WITH THE
MINIMUM NUMBER OF BANDS REQUIRED FOR EACH
Groupie

EVALUATION (E.G.
2 BANDS FOR HYDROGEN AND 4 BANDS FOR U-233) OR    Groupie

THE SAME NUMBER
OF BANDS FOR ALL EVALUATIONS (E.G. 4 BANDS FOR     Groupie

BOTH HYDROGEN
AND U-233).
Groupie

Groupie

FOR 2 OR FEWER
BANDS THE PROGRAM USES AN ANALYTIC EXPRESSION       Groupie

TO DEFINE ALL
MULTI-BAND PARAMETERS. FOR MORE THAN 2 BANDS THE     Groupie

PROGRAM PERFORMS
A NON-LINEAR FIT TO SELECT THE MULTI-BAND
Groupie

PARAMETERS THAT
MINIMIZE THE MAXIMUM FRACTIONAL ERROR AT ANY       Groupie

POINT ALONG THE
ENTIRE SELF-SHIELDING CURVE. THE NUMBER OF BANDS   Groupie

REQUIRED WITHIN
ANY GIVEN GROUP IS DEFINED BY INSURING THAT THE    Groupie

MULTI-BAND PARAMETERS CAN BE USED TO
ACCURATELY DEFINE SELF-       Groupie

SHIELDED CROSS
SECTIONS ALONG THE ENTIRE SELF-SHIELDING CURVE      Groupie

FROM SIGMA0 = 0
TO INFINITY. THE USER MAY DEFINE THE ACCURACY      Groupie

REQUIRED.
Groupie

Groupie

ENDF/B FORMATTED
UNSHIELDED AVERAGES
Groupie

------------------------------------
Groupie

UNSHIELDED
MULTI-GROUP AVERAGED CROSS SECTIONS FOR ALL REACTIONS   Groupie

MAY BE OBTAINED
IN THE ENDF/B FORTRAN IN EITHER HISTOGRAM
Groupie

(INTERPOLATION
LAW 1) OR LINEARLY INTERPOLABLE (INTERPOLATION      Groupie

LAW 2) FORM. SEE
INPUT BELOW FOR DETAILS.
Groupie

Groupie

MIXTURES OF
MATERIALS AND RESONANCE OVERLAP
Groupie

-------------------------------------------
Groupie

THE
SELF-SHIELDED CROSS SECTIONS FOR THE INDIVIDUAL CONSTITUENTS   Groupie

OF ANY MIXTURE
CAN BE CALCULATED BY THIS PROGRAM BY REALIZING THAT Groupie

THIS PROGRAM
ESSENTIALLY ONLY USES THE TOTAL CROSS SECTION AS A    Groupie

WEIGHTING
FUNCTION TO ACCOUNT FOR SELF-SHIELDING EFFECTS. FOR A    Groupie

MIXTURE IT IS
THEREFORE ONLY NECESSARY TO USE THE TOTAL CROSS      Groupie

SECTION FOR THE
MIXTURE IN PLACE OF THE ACTUAL TOTAL CROSS SECTION Groupie

FOR EACH
CONSTITUENT AND TO RUN THIS PROGRAM. THIS CAN BE DONE BY  Groupie

FIRST RUNNING
PROGRAM MIXER TO CALCULATE THE ENERGY DEPENDENT      Groupie

TOTAL CROSS
SECTION FOR ANY COMPOSITE MIXTURE. NEXT, SUBSTITUTE    Groupie

THIS COMPOSITE
TOTAL CROSS SECTION FOR THE ACTUAL TOTAL CROSS      Groupie

SECTION OF EACH
CONSTITUENT (IN EACH ENDF/B FORMATTED EVALUATION). Groupie

FINALLY, RUN THIS PROGRAM TO
CALCULATE THE SELF-SHIELDED CROSS     Groupie

SECTION FOR EACH
CONSTITUENT, PROPERLY ACCOUNTING FOR RESONANCE    Groupie

OVERLAP BETWEEN
THE RESONANCES OF ALL OF THE CONSTITUENTS OF THE   Groupie

MIXTURE. DURING
THE SAME RUN THESE SELF-SHIELDED CROSS SECTIONS    Groupie

CAN IN TURN BE
USED TO CALCULATE FULLY CORRELATED MULT-BAND
Groupie

Groupie

MULTI-BAND
PARAMETER OUTPUT FORMAT
Groupie

----------------------------------
Groupie

FOR VERSIONS
92-2 AND LATER VERSIONS THE MULTI-BAND PARAMETERS     Groupie

ARE OUTPUT IN A
SIMPLE CHARACTER FORMAT, THAT CAN BE TRANSFERRED   Groupie

AND USED ON
VIRTUALLY ANY COMPUTER.
Groupie

Groupie

THE BINARY
FORMAT USED IN EARLIER VERSIONS OF THIS CODE IS NO      Groupie

LONGER
USED.
Groupie

Groupie

CONTACT THE
AUTHOR IF YOU WOULD LIKE TO RECEIVE A SIMPLE PROGRAM   Groupie

TO READ THE
CHARACTER FORMATTED MULTI-BAND PARAMETER FILE AND      Groupie

CREATE A BINARY,
RANDOM ACCESS FILE FOR USE ON VIRTUALLY ANY       Groupie

COMPUTER.
Groupie

Groupie

THE FORMAT OF
THE CHARACTER FILE IS,
Groupie

Groupie

RECORD   COLUMNS   FORMAT   DESCRIPTION
Groupie

1
1-72     18A4    LIBRARY DESCRIPTION (AS
READ)
Groupie

2
1-11
I11    MATERIAL
ZA
Groupie

12-22
I11    NUMBER
GROUPS
Groupie

23-33
I11    NUMBER OF
BANDS
Groupie

34-44
D11.4   TEMPERATURE
(KELVIN)
Groupie

45-55    1X,10A1  HOLLERITH DESCRIPTION OF ZA
Groupie

3
1-11     D11.4   ENERGY (EV) - GROUP BOUNDARY.
Groupie

12-22
D11.4   TOTAL      (FIRST
BAND)
Groupie

23-33
D11.4   ELASTIC
Groupie

34-44
D11.4   CAPTURE
Groupie

35-55
D11.4   FISSION
Groupie

4
1-11     -----   BLANK
Groupie

12-22
D11.4   TOTAL      (SECOND
BAND)
Groupie

23-33
D11.4   ELASTIC
Groupie

34-44
D11.4   CAPTURE
Groupie

35-55
D11.4   FISSION
Groupie

Groupie

LINES 3 AND 4
ARE REPEATED FOR EACH GROUP. THE LAST LINE FOR EACH  Groupie

MATERIAL (ZA)
IS,
Groupie

Groupie

N
1-11     D11.4   ENERGY (EV) - UPPER ENERGY LIMIT
OF    Groupie

LAST GROUP.
Groupie

Groupie

FOR EXAMPLE, A
175 GROUP, 2 BAND FILE, FOR EACH MATERIAL WILL      Groupie

CONTAIN 352
LINES = 1 HEADER LINE, 175 * 2 LINES OF PARAMETERS,    Groupie

AND 1 FINAL LINE WITH THE UPPER ENERGY LIMIT   Groupie

OF THE LAST GROUP.
Groupie

Groupie

INPUT FILES
Groupie

-----------
Groupie

UNIT  DESCRIPTION
Groupie

----  -----------
Groupie

2   INPUT DATA (BCD - 80
CHARACTERS/RECORD)
Groupie

10   ORIGINAL ENDF/B DATA (BCD - 80
CHARACTERS/RECORD)
Groupie

Groupie

OUTPUT
FILES
Groupie

------------
Groupie

UNIT  DESCRIPTION
Groupie

----  -----------
Groupie

31   MULTI-BAND PARAMETERS CHARACTER
FILE - OPTIONAL
Groupie

(BCD - 80 CHARACTERS/RECORD)
Groupie

32   SELF-SHIELDED CROSS SECTION
LISTING - OPTIONAL
Groupie

(BCD - 120 CHARACTERS/RECORD)                                Groupie

33   MULTI-BAND PARAMETER LISTING -
OPTIONAL
Groupie

(BCD - 120 CHARACTERS/RECORD)
Groupie

34   UNSHIELDED CROSS SECTION LISTING -
OPTION                    Groupie

(BCD - 120 CHARACTERS/RECORD)
Groupie

3   OUTPUT REPORT (BCD -
80 CHARACTERS/RECORD)
Groupie

11   MULTI-GROUP ENDF/B DATA -
OPTIONAL
Groupie

(BCD - 80 CHARACTERS/RECORD)
Groupie

Groupie

SCRATCH
FILES
Groupie

-------------
Groupie

UNIT  FILENAME  DESCRIPTION
Groupie

----  --------  -----------
Groupie

8   ENERGY DEPENDENT WEIGHTING
SPECTRUM
Groupie

(BINARY - 40080 WORDS/BLOCK)
Groupie

9   TOTAL CROSS
SECTION
Groupie

(BINARY - 40080 WORDS/BLOCK)
Groupie

12   ELASTIC CROSS SECTION - ONLY FOR
SELF-SHIELDING CALCULATION  Groupie

(BINARY - 40080 WORDS/BLOCK)
Groupie

13   CAPTURE CROSS SECTION - ONLY FOR
SELF-SHIELDING CALCULATION  Groupie

(BINARY - 40080 WORDS/BLOCK)
Groupie

14   FISSION CROSS SECTION - ONLY FOR
SELF-SHIELDING CALCULATION  Groupie

(BINARY - 40080 WORDS/BLOCK)
Groupie

Groupie

OPTIONAL
STANDARD FILE NAMES (SEE SUBROUTINES FILIO1 AND FILIO2)   Groupie

----------------------------------------------------------------   Groupie

UNIT  FILE NAME
Groupie

----  ----------
Groupie

2   GROUPIE.INP
Groupie

3   GROUPIE.LST
Groupie

8   (SCRATCH)
Groupie

9   (SCRATCH)
Groupie

10   ENDFB.IN
Groupie

11   ENDFB.OUT
Groupie

12   (SCRATCH)
Groupie

13   (SCRATCH)
Groupie

14   (SCRATCH)
Groupie

31   MULTBAND.TAB
Groupie

32   SHIELD.LST
Groupie

33   MULTBAND.LST
Groupie

34   UNSHIELD.LST
Groupie

Groupie

I/O UNITS
USED
Groupie

--------------
Groupie

UNITS 2, 3
8, 9 AND 10 WILL ALWAYS BE USED.
Groupie

UNITS 31
THROUGH 34 AND 11 ARE OPTIONALLY USED DEPENDING ON THE   Groupie

OUTPUT
REQUESTED.
Groupie

UNITS 12,
13 AND 14 WILL ONLY BE USED IF SELF-SHIELDED OR
Groupie

MULTIBAND
OUTPUT IS REQUESTED.
Groupie

Groupie

INPUT CARDS
Groupie

-----------
Groupie

CARD  COLS.  FORMAT  DESCRIPTION
Groupie

----  -----  ------  -----------
Groupie

1    1-11    I11   SELECTION CRITERIA (0=MAT,
1=ZA)
Groupie

1   12-22    I11   NUMBER OF GROUPS.
Groupie

=.GT.0 - ARBITRARY GROUP BOUNDARIES ARE READ  Groupie

FROM INPUT FILE (N GROUPS REQUIRE    Groupie

N+1 GROUP BOUNDARIES). CURRENT       Groupie

PROGRAM MAXIMUM IS 1000 GROUPS.      Groupie

BUILT-IN OPTIONS INCLUDE....
Groupie

=  0   - TART    175 GROUPS
Groupie

= -1   - ORNL     50 GROUPS
Groupie

=
-2   - ORNL    126 GROUPS
Groupie

= -3   - ORNL    171 GROUPS
Groupie

= -4   - SAND-II 620
(665) GROUPS TO 18 MEV
Groupie

=
-5   - SAND-II 640 (685) GROUPS
TO 20 MEV   Groupie

= -6   - WIMS     69 GROUPS
Groupie

= -7   - GAM-I    68 GROUPS
Groupie

=
-8   - GAM-II   99 GROUPS
Groupie

= -9   - MUFT     54 GROUPS
Groupie

=-10   - ABBN     28 GROUPS
Groupie

=-11   - TART    650 GROUPS
Groupie

=-12   - TART    700 GROUPS
Groupie

=-13   - SAND-II 665
GROUPS TO 18 MEV
Groupie

=-14   - SAND-II 685
GROUPS TO 20 MEV
Groupie

1   23-33    I11   MULTI-BAND SELECTOR
Groupie

=  0 - NO MULTI-BAND
CALCULATIONS
Groupie

=  1 - 2 BAND. CONSERVE AV(TOT),
AV(1/TOT)    Groupie

AND AV(1/TOT**2)
Groupie

=  2 - 2 BAND. CONSERVE
AV(TOT), AV(1/TOT)
Groupie

AND AV(1/(TOT+SIGMA0)) WHERE
Groupie

SIGMA0 = AV(TOT) IN EACH GROUP
Groupie

= 3-5- MULTI-BAND FIT. CONSERVE AV(TOT) AND   Groupie

MINIMIZE FRACTIONAL ERROR FOR ENTIRE   Groupie

SELF-SHIELDING CURVE (SIGMA0 = 0 TO    Groupie

INFINITY)
Groupie

IF THE SELECTOR IS POSITIVE (1 TO 5) THE      Groupie

MINIMUM NUMBER OF BANDS WILL BE OUTPUT FOR    Groupie

EACH ISOTOPE INDEPENDENTLY. IF THE SELECTOR   Groupie

IS NEGATIVE (-1 TO -5) THE SAME NUMBER OF     Groupie

BANDS
(ABS(SELECTOR)) WILL BE OUTPUT FOR      Groupie

ALL ISOTOPES.
Groupie

1   34-44    I11   NUMBER OF POINTS USED TO DESCRIBE
ENERGY
Groupie

DEPENDENT
WEIGHTING SPECTRUM S(E).
Groupie

= -2    -
MAXWELLIAN - UP TO 0.1 EV
Groupie

1/E        -
0.1 EV TO 67 KEV       Groupie

FISSION    - ABOVE 67 KEV
Groupie

05/01/20-----------------ADDED OPTION TO ALLOW TEMPERATURE OF THE      Groupie

MAXWELLIAN TO BE CHANGED - SEE INPUT LINE 4,  Groupie

COLUMNS 55 - 66.
Groupie

= -1    - 1/E
Groupie

= 0 OR 1- ENERGY INDEPENDENT (SO CALLED FLAT  Groupie

WEIGHTING SPECTRUM).
Groupie

= .GT.1 - READ THIS MANY POINTS FROM INPUT    Groupie

TO DESCRIBE WEIGHTING SPECTRUM.     Groupie

NO LIMIT TO THE NUMBER OF POINTS    Groupie

USED TO DESCRIBE WEIGHTING.
Groupie

1   45-55   D11.4  MULTI-BAND CONVERGENCE CRITERIA.
Groupie

ONLY USED FOR 3 OR MORE BANDS. THE NUMBER OF  Groupie

BANDS IN EACH GROUPS IS SELECTED TO INSURE    Groupie

THAT THE ENTIRE SELF-SHIELDING CURVE CAN BE   Groupie

REPRODUCED TO WITHIN THIS FRACTIONAL ERROR.   Groupie

= .LT. 0.0001 - USE STANDARD 0.001
Groupie

(0.1 PER-CENT)
Groupie

= .GE. 0.0001 - USE AS CONVERGENCE CRITERIA   Groupie

1   56-66    I11   SIGMA-0 DEFINITION SELECTOR.
Groupie

< 0 - 21 VALUES OF SIGMA0 ARE READ INPUT AND  Groupie

INTERPRETED AS FIXED VALUES = SAME AS   Groupie

=
1 DESCRIPTION BELOW
Groupie

INPUT VALUES MUST ALL BE,
Groupie

1) GREATER THAN 0
Groupie

2)
IN DESCENDING VALUE ORDER
Groupie

= 0 - SIGMA-0 WILL BE DEFINED AS A MULTIPLE   Groupie

OF THE UNSHIELDED TOTAL CROSS SECTION   Groupie

IN EACH GROUP (VALUES OF 1/1024 TO      Groupie

1024 IN STEPS OF A FACTOR OF 2 WILL     Groupie

BE USED AS THE MULTIPLIER).
Groupie

= 1 - SIGMA-0 WILL BE DEFINED AS THE SAME     Groupie

NUMBER OF BARNS IN EACH GROUP (VALUES   Groupie

40000 TO 0.4 BARNS WILL BE USED. WITHIN Groupie

EACH DECADE VALUES OF 10, 7, 4, 2, 1    Groupie

BARNS WILL BE USED).
Groupie

2-4    1-66 6D11.4   IF SIGMA-0 DEFINITION SELECTOR
< 0, THE NEXT  Groupie

4 LINES OF INPUT ARE THE 22 VALUES OF SIGMA0, Groupie

6 PER LINE.
Groupie

2    1-60    A60   ENDF/B INPUT DATA FILENAME
Groupie

(STANDARD OPTION = ENDFB.IN)
Groupie

3    1-60    A60   ENDF/B OUTPUT DATA FILENAME
Groupie

(STANDARD OPTION = ENDFB.OUT)
Groupie

Groupie

THE FOURTH INPUT
CARD IS USED TO SELECT ALL DESIRED OUTPUT MODES.  Groupie

EACH OUTPUT
DEVICE MAY BE TURNED OFF (0) OR ON (1). THEREFORE      Groupie

THEREFORE EACH
OF THE FOLLOWING INPUT PARAMETERS MAY BE EITHER     Groupie

ZERO TO INDICATE
NO OUTPUT OR NON-ZERO TO INDICATE OUTPUT.
Groupie

Groupie

4
1-11   I11   SELF-SHIELDED CROSS SECTION
LISTING
Groupie

= 1 - CROSS SECTIONS
Groupie

= 2 - RESONANCE INTEGRALS
Groupie

4    12-22   I11   MULTI-BAND PARAMETER LISTING
Groupie

4    23-33   I11   MULTI-BAND PARAMETERS COMPUTER
READABLE
Groupie

4    34-44   I11   UNSHIELDED CROSS SECTIONS IN
ENDF/B FORMAT    Groupie

= 1 - HISTOGRAM FORMAT (INTERPOLATION LAW 1)  Groupie

= 2 - LINEAR-LINEAR (INTERPOLATION LAW 2)     Groupie

4    45-55   I11   UNSHIELDED CROSS SECTIONS
LISTING
Groupie

= 1 - CROSS SECTIONS
Groupie

= 2 - RESONANCE INTEGRALS                     Groupie

05/01/20 - ADDED THE BELOW OPTION
Groupie

4    56-66   D11.4 IF THE STANDARD BUILT-IN
SPECTRA IS USED,
Groupie

INPUT LINE 1, COLUMNS 34-44 = 2, THIS FIELD   Groupie

CAN BE USED TO OPTIONALLY CHANGE TEMPERATURE  Groupie

OF THE MAXWELLIAN.
Groupie

INPUT IS IN EV (0.0253 EV = ROOM TEMPERATURE) Groupie

= 0 - USE DEFAULT 0.0253 EV, ROOM TEMPERATURE Groupie

> 0 - USE THIS AS THE TEMPERATURE
Groupie

RESTRICTION - TEMPERATURE CANNOT EXCEED       Groupie

1000
EV.
Groupie

Groupie

5
1-80   18A4  LIBRARY IDENTIFICATION. ANY TEXT THAT
THE     Groupie

USER
WISHES TO IDENTIFY THE MULTI-BAND
Groupie

PARAMETERS. THIS LIBRARY IDENTIFICATION IS    Groupie

WRITTEN INTO THE COMPUTER READABLE MULTI-BAND Groupie

DATA FILE.
Groupie

Groupie

6-N    1- 6    I6   LOWER MAT OR ZA LIMIT
Groupie

7- 8    I2   LOWER MF LIMIT
Groupie

9-11    I3   LOWER MT LIMIT
Groupie

12-17   I11   UPPER MAT OR ZA LIMIT
Groupie

18-19    I2   UPPER MF LIMIT                                Groupie

20-22    I3   UPPER MT LIMIT
Groupie

UP TO 100 RANGES MAY BE SPECIFIED, ONE RANGE  Groupie

PER LINE. THE LIST OF RANGES IS TERMINATED    Groupie

BY A BLANK CARD. IF THE UPPER MAT OR ZA       Groupie

LIMIT IS LESS THAN THE LOWER LIMIT THE UPPER  Groupie

IS SET EQUAL TO THE LOWER LIMIT. IF THE UPPER Groupie

MF OR MT LIMIT IS ZERO IT WILL BE SET EQUAL   Groupie

TO ITS MAXIMUM VALUE, 99 OR 999, RESPECTIVELY Groupie

IF THE FIRST REQUEST LINE IS BLANK IT WILL    Groupie

TERMINATE THE LIST OF REQUESTS AND CAUSE ALL  Groupie

DATA TO BE RETRIEVED (SEE EXAMPLE INPUT).     Groupie

Groupie

VARY   1-66  6D11.4 ENERGY GROUP BOUNDARIES. ONLY
REQUIRED IF
Groupie

THE NUMBER OF GROUPS INDICATED ON THE FIRST   Groupie

INPUT CARD IS POSITIVE. ALL ENERGIES MUST     Groupie

BE
IN ASCENDING ENERGY IN EV. THE PRESENT     Groupie

LIMITS ARE 1 TO 1000 GROUPS. FOR N GROUPS     Groupie

N+1 BOUNDARIES WILL BE READ FROM THE
Groupie

INPUT FILE, E.G.
IF THE FIRST INPUT CARD      Groupie

INDICATES 20 GROUPS, 21 ENERGY BOUNDARIES     Groupie

WILL BE READ FROM THE INPUT FILE.
Groupie

Groupie

VARY   1-66  6D11.4 ENERGY DEPENDENT WEIGHTING
SPECTRUM. ONLY
Groupie

REQUIRED IF THE NUMBER OF POINTS INDICATED    Groupie

ON FIRST CARD IS MORE THAN ONE. DATA IS       Groupie

GIVEN IN (ENERGY, WEIGHT) PAIRS, UP TO 3      Groupie

PAIRS PER CARD, USING ANY NUMBER OF CARDS     Groupie

REQUIRED. ENERGIES MUST BE IN ASCENDING       Groupie

ORDER IN EV. THE SPECTRUM VALUES MUST BE      Groupie

NON-NEGATIVE. THE ENERGY RANGE OF SPECTRUM    Groupie

MUST AT LEAST SPAN THE ENERGY RANGE OF THE    Groupie

ENERGY GROUPS. SINCE SPECTRUM IS STORED IN    Groupie

PAGING SYSTEM THERE IS NO LIMIT TO NUMBER     Groupie

OF POINTS THAT CAN BE USED TO DESCRIBE THE    Groupie

WEIGHTING SPECTRUM.
Groupie

Groupie

EXAMPLE INPUT
NO. 1
Groupie

-------------------
Groupie

REQUEST DATA BY
MAT AND PROCESS ALL DATA (ALL MAT BETWEEN 1 AND    Groupie

9999). USE THE
TART 175 GROUP STRUCTURE, GENERATE 2 BAND
Groupie

PARAMETERS (THE
FOR ALL ISOTOPES) TO 0.1 PER-CENT ACCURACY
Groupie

IN THE
SELF-SHIELDING CURVE. OUTPUT ALL
LISTING, COMPUTER
Groupie

READABLE AND
ENDF/B FORMAT GROUP AVERAGES.
Groupie

Groupie

EXPLICITLY
SPECIFY THE STANDARD FILENAMES.
Groupie

Groupie

THE FOLLOWING 7
INPUT LINES ARE REQUIRED.
Groupie

Groupie

0
0
-2
0 1.00000-03
0
Groupie

ENDFB.IN
Groupie

ENDFB.OUT
Groupie

1
1
1
1
1
Groupie

TART
175 GROUP, 2 BAND LIBRARY TO 0.1 PER-CENT ACCURACY
Groupie

1 1  1
9999 0  0
Groupie

(BLANK CARD TERMINATES REQUEST LIST)
Groupie

Groupie

EXAMPLE INPUT
NO. 2
Groupie

-------------------
Groupie

THE SAME EXAMPLE
1, AS ABOVE, ONLY THE ENDF/B DATA WILL BE READ    Groupie

FROM
\ENDFB6\SIGMA1\K300\ZA092238 (U-238 AT 300 KELVIN) AND
Groupie

WRITTEN TO
\ENDFB6\GROUPIE\K300\ZA092238
Groupie

Groupie

THE FOLLOWING 7
INPUT LINES ARE REQUIRED.
Groupie

Groupie

0
0
-2
0 1.00000-03
0
Groupie

\ENDFB6\SIGMA1\K300\ZA092238
Groupie

\ENDFB6\GROUPIE\K300\ZA092238
Groupie

1
1
1
1
1
Groupie

TART
175 GROUP, 2 BAND LIBRARY TO 0.1 PER-CENT ACCURACY
Groupie

1 1  1
9999 0  0
Groupie

(BLANK CARD TERMINATES REQUEST LIST)
Groupie

Groupie

EXAMPLE INPUT
NO. 3
Groupie

-------------------
Groupie

PROCESS ALL
DATA. USE 1/V WEIGHTING IN ORDER TO CALCULATE
Groupie

UNSHIELDED ONE
GROUP CROSS SECTIONS OVER THE ENERGY
RANGE 0.5 EV   Groupie

TO 1 MEV (NOTE
THAT THE RESULTS ARE SIMPLY PROPORTIONAL TO THE     Groupie

RESONANCE
INTEGRAL FOR EACH REACTION). OUTPUT UNSHIELDED LISTING.  Groupie

Groupie

LEAVE THE
DEFINITION OF THE FILENAMES BLANK - THE PROGRAM WILL     Groupie

THEN USE
STANDARD FILENAMES.
Groupie

Groupie

THE FOLLOWING 7
INPUT CARDS ARE REQUIRED.
Groupie

Groupie

0
0
1
-1
0
Groupie

(USE STANDARD FILENAME = ENDFB.IN)
Groupie

(USE STANDARD FILENAME = ENDFB.OUT)
Groupie

0
0
0
0
1
Groupie

RESONANCE INTEGRAL CALCULATION (FROM 0.5 EV TO 1 MEV)
Groupie

(RETRIEVE ALL DATA, TERMINATE REQUEST LIST)      Groupie

5.00000-01
1.00000+06
Groupie

Groupie

=======================================================================
Groupie

=======================================================================
Legend

Legend

PROGRAM
LEGEND
Legend

VERSION 80-1
(SEPTEMBER 1980)
Legend

VERSION 84-1
(NOVEMBER 1984)
Legend

VERSION 86-1
(JANUARY 1986) *CORRECTED BASED ON USER COMMENTS      Legend

*FORTRAN-77/H VERSION
Legend

VERSION 87-1
(JANUARY 1987) *CORRECTED BASED ON USER COMMENTS      Legend

VERSION 88-1
(JULY 1988)
*OPTION...INTERNALLY DEFINE ALL I/O    Legend

FILE NAMES (SEE, SUBROUTINE FILEIO    Legend

FOR DETAILS).
Legend

*IMPROVED BASED ON USER COMMENTS.      Legend

VERSION 89-1
(JANUARY 1989) *PSYCHOANALYZED BY PROGRAM FREUD TO    Legend

INSURE PROGRAM WILL NOT DO ANYTHING   Legend

CRAZY.
Legend

*UPDATED TO USE NEW PROGRAM CONVERT    Legend

KEYWORDS.
Legend

*ADDED LIVERMORE
CIVIC COMPILER
Legend

CONVENTIONS.
Legend

VERSION 92-1
(JANUARY 1992) *FOR ANGULAR DISTRIBUTIONS CALCULATED  Legend

FROM LEGENDRE COEFFICIENTS, INTERVAL  Legend

HALF TO CONVERGENCE.
Legend

*UPDATED
BASED ON USER COMMENTS
Legend

*ADDED FORTRAN SAVE OPTION
Legend

*ADDED SELECTED OF DATA TO PROCESS     Legend

BY
MAT/MF/MT/ENERGY RANGES.
Legend

*WARNING...THE INPUT PARAMETER FORMAT  Legend

HAS BEEN CHANGED - FOR DETAILS SEE    Legend

BELOW.
Legend

VERSION 92-2
(SEPT. 1992)   *CORRECTED
PROCESSING OF ISOTROPIC
Legend

ANGULAR DISTRIBUTIONS
Legend

VERSION 94-1
(JANUARY 1994) *VARIABLE ENDF/B DATA FILENAMES
Legend

TO ALLOW ACCESS TO FILE STRUCTURES    Legend

(WARNING - INPUT PARAMETER FORMAT     Legend

HAS BEEN CHANGED)
Legend

*CLOSE ALL FILES BEFORE TERMINATING    Legend

(SEE, SUBROUTINE ENDIT)
Legend

VERSION 96-1
(JANUARY 1996) *COMPLETE RE-WRITE
Legend

*IMPROVED COMPUTER INDEPENDENCE
Legend

*ALL DOUBLE PRECISION
Legend

*ON SCREEN OUTPUT
Legend

*UNIFORM TREATMENT OF ENDF/B I/O
Legend

*IMPROVED OUTPUT PRECISION
Legend

*INCREASED MAX. POINTS FROM 5,000      Legend

TO 20,000.
Legend

VERSION 99-1
(MARCH 1999)   *CORRECTED
CHARACTER TO FLOATING       Legend

POINT READ FOR MORE DIGITS
Legend

*UPDATED
TEST FOR ENDF/B FORMAT
Legend

VERSION BASED ON RECENT FORMAT CHANGE Legend

*GENERAL IMPROVEMENTS BASED ON
Legend

USER
FEEDBACK
Legend

VERS. 2000-1
(FEBRUARY 2000)*GENERAL IMPROVEMENTS BASED ON
Legend

USER FEEDBACK
Legend

VERS. 2001-1
(MARCH 2001)   *UPDATED TO
HANDLE COMBINATIONS OF
Legend

LEGENDRE COEFFICIENTS AT LOW ENERGY   Legend

AND TABULATED DATA AT HIGH ENERGY.    Legend

VERS. 2002-1
(MAY 2002)     *OPTIONAL INPUT PARAMETERS
Legend

VERS. 2004-1
(MARCH 2004)   *ADDED INCLUDE
FOR COMMON
Legend

*ZERO ANGULAR DISTRIBUTIONS ARE O.K.   Legend

(PREVIOUSLY ZERO OR NEGATIVE WAS      Legend

TREATED AS AN ERROR - ZERO IS O.K.   Legend

FOR SOME REACTIONS OVER SOME COSINE
Legend

RANGES)
Legend

VERS. 2006-1
(MARCH 2006)   *INCREASED
MAXIMUM NUMBER OF LEGENDRE  Legend

COEFFICIENTS FROM 50 TO 500.
Legend

WARNING - THE RECURSION RELATIONSHIP  Legend

FOR LEGENDRE POLYNOMIALS BECOMES      Legend

UNSTABLE IN HIGHER ORDER POLYTNOMIALS Legend

EVEN USING DOUBLE PRECISION.
Legend

VERS. 2007-1
(JAN.  2007)   *CHECKED AGAINST ALL ENDF/B=VII.
Legend

*INCREASED MAX. POINTS FROM 60,000     Legend

TO 240,000.
Legend

Legend

OWNED,
MAINTAINED AND DISTRIBUTED BY
Legend

------------------------------------
Legend

THE NUCLEAR DATA
SECTION
Legend

INTERNATIONAL
ATOMIC ENERGY AGENCY
Legend

P.O. BOX 100
Legend

A-1400, VIENNA, AUSTRIA
Legend

EUROPE
Legend

Legend

ORIGINALLY
WRITTEN BY                                              Legend

------------------------------------
Legend

DERMOTT E.
CULLEN
Legend

CURRENT
ADDRESS
Legend

UNIVERSITY OF CALIFORNIA
Legend

LAWRENCE
LIVERMORE
NATIONAL LABORATORY
Legend

L-159
Legend

P.O. BOX
808
Legend

LIVERMORE, CA
94550
Legend

U.S.A.
Legend

TELEPHONE  925-423-7359
Legend

E. MAIL    [email-masked]
Legend

WEBSITE
HTTP://WWW.LLNL.GOV/CULLEN1
Legend

Legend

PURPOSE
Legend

-------
Legend

CALCULATE
LINEARLY INTERPOLABLE TABULATED ANGULAR DISTRIBUTIONS    Legend

STARTING FROM
DATA IN THE ENDF/B FORMAT. ANGULAR DISTRIBUTIONS     Legend

MAY BE DESCRIBED
IN THE ENDF/B FORMAT IN ONE OF THREE WAYS.
Legend

FOR EACH OF
THESE THREE FORMS THE USER MAY CHOOSE (SEE, INPUT      Legend

OPTIONS) TO
EITHER COPY EACH TYPE OF DATA OR TO PROCESS IT AT      Legend

AS FOLLOWS,
Legend

Legend

(1) ANGULAR
DISTRIBUTION IS ISOTROPIC AT ALL ENERGIES (LTT=0)      Legend

-------------------------------------------------------------      Legend

IN THIS CASE THE
INPUT DATA DOES NOT INCLUDE ANY ANGULAR
Legend

DISTRIBUTIONS. A
SECTION MERELY CONTAINS A FLAG TO INDICATE
Legend

THE ANGULAR
DISTRIBUTION IS ISOTROPIC AT ALL ENERGIES. IN THIS     Legend

CASE THE SECTION
IS OUTPUT IN EXACTLY THE SAME FORM IN WHICH IT    Legend

WAS READ FROM
THE INPUT.
Legend

Legend

(2) ANGULAR
DISTRIBUTIONS GIVEN BY LEGENDRE COEFFICIENTS (LTT=1)   Legend

----------------------------------------------------------------   Legend

LEGENDRE
COEFFICIENTS ARE GIVEN AT A SERIES OF ENERGIES. AN
Legend

INTERPOLATION
LAW IS GIVEN BETWEEN ENERGIES. THE INTERPOLATION     Legend

LAW BETWEEN
ENERGIES IS COPIED AS INPUT (I.E., NO ATTEMPT IS
Legend

MADE TO
LINEARIZE THE VARIATION WITH ENERGY). FOR EACH ENERGY AT   Legend

WHICH LEGENDRE
COEFFICIENTS ARE GIVEN A LINEARLY INTERPOLABLE      Legend

ANGULAR
DISITRIBUTION IS RECONSTRUCTED IN THE SYSTEM IN WHICH THE  Legend

THE COEFFICIENTS
ARE GIVEN (I.E., CM OR LAB - NO ATTEMPT IS MADE   Legend

TO CONVERT FROM
ONE SYSTEM TO THE OTHER). A MAXIMUM OF 50 LEGENDRE Legend

COEFFICIENTS IS
ALLOWED. REGARDLESS OF THE NUMBER OF COEFFICIENTS  Legend

INPUT THE
PROGRAM WILL ONLY USE COEFFICIENTS UP TO THE LAST ORDER  Legend

AT WHICH THE
COEFFICIENTS ARE NON-ZERO (E.G. IF COEFFICIENTS P1    Legend

THROUGH P12 ARE
READ, BUT P9=P10=P11=P12=0.0, THE PROGRAM WILL     Legend

ONLY USE
COEFFICIENTS UP TO P8). IF OVER 50 NON-ZERO COEFFICIENTS  Legend

ARE READ ONLY
THE FIRST 50 WILL BE USED.
Legend

Legend

(2) ANGULAR
DISTRIBUTIONS IS TABULATED (LTT=2)
Legend

----------------------------------------------------------------   Legend

ANGULAR
DISTRIBUTIONS ARE GIVEN AT A SERIES OF ENERGIES. AN
Legend

INTERPOLATION
LAW IS GIVEN BETWEEN ENERGIES AND A SECOND
Legend

INTERPOLATION
LAW IS GIVEN AT EACH ENERGY TO INTERPOLATE BETWEEN   Legend

THE POINTS IN
EACH TABULATED DISTRIBUTION. AT EACH ENERGY THE      Legend

ANGULAR
DISTRIBUTION WILL BE CONVERTED TO LINEARLY INTERPOLABLE    Legend

FORM. THE
INTERPOLATION BETWEEN ENERGIES IS OUTPUT EXACTLY AS      Legend

INPUT. THE
INTERPOLATION LAW AT EACH ENERGY IS OUTPUT TO INDICATE  Legend

THE NOW LINEARLY
INTERPOLABLE ANGULAR DISTRIBUTION.
Legend

Legend

(3) LEGENDRE
COEFFICIENTS AND TABULATED (LTT=3)                    Legend

----------------------------------------------------------------   Legend

ENDF-102 SAYS
THIS SHOULD BE LTT=4, BUT ALL OF THE EVALUATIONS     Legend

IN ENDF/B-VI,
RELEASE 7, USE LTT=3? THIS CODE WILL TREAT THESE     Legend

AS LTT=4 - SEE
BELOW.
Legend

Legend

(4) LEGENDRE
COEFFICIENTS AND TABULATED (LTT=4)
Legend

----------------------------------------------------------------   Legend

THIS IS A
COMBINATION OF (1) AND (2) DESCRIBED ABOVE. THE
Legend

LEGENDRE DATA IS
ALWAYS GIVEN FIRST, FOR LOWER ENERGIES,
Legend

FOLLOWED BY TABULATED ANGULAR
DISTRIBUTIONS, FOR HIGHER ENERGIES.
Legend

Legend

THIS TYPE OF
DATA CAN ONLY BE COPIED OR ALL CONVERTED TO
Legend

TABULATED
(LTT=2).
Legend

Legend

POINT VALUES -
NORMALIZED VS. UNNORMALIZED
Legend

------------------------------------------------------------------
Legend

THE VALUE OF AN
ANGULAR DISTRIBUTION AT ANY COSINE WILL BE
Legend

CORRECTLY
CALCULATED BY THIS CODE, BASED EITHER DIRECTLY ON THE    Legend

ANGULAR
DISTRIBUTION, OR ON THE SUM OF THE CONTRIBUTING LEGENDRE   Legend

MOMENTS.
Legend

Legend

ENDF/B ANGULAR
DISTRIBUTIONS ARE BY DEFINITION NORMALIZED WHEN     Legend

INTEGRATED OVER
COSINE. THEREFORE THIS CODE WILL NORMALIZE EACH    Legend

ANGULAR
DISTRIBUTION BEFORE IT IS OUTPUT. THE OUTPUT REPORT FROM   Legend

THIS CODE WILL
INDICATE THE NORMALIZATION FACTOR USED.
Legend

Legend

THE REASON THAT
AN ANGULAR DISTRIBUTION MAY NOT BE NORMALIZED IS   Legend

DUE TO THE
APPROXIMATION OF CREATING LINEARLY INTERPOLABLE         Legend

TABULATED
ANGULAR DISTRIBUTIONS - THE MORE ACCURATELY THIS IS      Legend

DONE THE CLOSER
THE NORMALIZATION FACTOR WILL BE TO UNITY. AS YOU  Legend

DECREASE THE
ALLOWABLE ERROR THE NORMALIZED VALUES WILL APPROACH   Legend

THE CORRECT
POINT VALUES CALCULATED BY THE CODE.
Legend

Legend

SINCE THE DATA
IS NORMALIZED PRIOR TO OUTPUT THE RESULTS IN THE    Legend

ENDF/B FORMAT MAY DIFFER
SLIGHTLY FROM VALUES REFERRED TO BE ERROR Legend

MESSAGES, ETC.
PRINTED BY THE CODE DURING EXECUTION. IN ALL CASES  Legend

THE VALUES
PRINTED BY THE CODE IN ERROR MESSAGES, ETC. SHOULD BE   Legend

CONSIDERED TO BE
THE CORRECT VALUES AND THE OUTPUT TABULATED
Legend

ANGULAR
DISTRIBUTIONS APPROXIMATE DUE TO THE RE-NORMALIZATION -    Legend

TO RE-ITERATE,
THE OUTPUT TABULATED VALUES ARE APPROXIMATE DUE     Legend

TO THE
APPROXIMATIONS USED IN CONSTRUCTING LINEAR INTERPOLABLE     Legend

ANGULAR
DISTRIBUTIONS TO WITHIN SOME ALLOWABLE TOLERANCE.
Legend

Legend

ELIMINATION OF
NEGATIVE VALUES
Legend

------------------------------
Legend

THE
RECONSTRUCTED ANGULAR DISTRIBUTION WILL BE TESTED AND IF IT    Legend

IS NEGATIVE AT
ONE OR MORE COSINES AN ERROR MESSAGE WILL BE OUTPUT Legend

AND BASED ON THE
INPUT OPTION SELECTED ONE OF THE FOLLOWING
Legend

CORRECTIVE
ACTIONS WILL BE TAKEN (SEE, INPUT OPTIONS),
Legend

(1) NO
CORRECTION
Legend

(2) CHANGE
INDIVIDUAL LEGENDRE COEFFICIENTS (EACH BY LESS THAN     Legend

1.0 PER-CENT) UNTIL THE RECONSTRUCTED ANGULAR DISTRIBUTION     Legend

IS POSITIVE (MINIMUM MORE THAN 1 MILLI-BARN). THE ALLOWABLE    Legend

PER-CENT CHANGE IN COEFFICIENTS AND MINIMUM CROSS SECTION CAN  Legend

BE CHANGED BY INPUT.
Legend

(3) CHANGE ALL
LEGENDRE COEFFICIENTS TO FORCE DISTRIBUTION TO BE   Legend

POSITIVE (MINIMUM MORE THAN 1 MILLI-BARN). WITH THIS OPTION    Legend

THERE IS NO RESTRICTION ON THE AMOUNT THAT EACH COEFFICIENT    Legend

IS CHANGED AND AS SUCH THIS OPTION SHOULD BE USED WITH
Legend

CAUTION AND ONLY AS A LAST RESORT IF NO OTHER APPROACH CAN     Legend

BE USED TO MAKE THE DISTRIBUTION POSITIVE.
Legend

Legend

OUTPUT
Legend

------
Legend

THE USER MAY
REQUEST OUTPUT OF EITHER,
Legend

(1) TABULATED VALUES
- POSSIBLY CORRECTED TO ELIMINATE NEGATIVE    Legend

VALUES. THE TABULATED DISTRIBUTION WILL BE NORMALIZED BEFORE   Legend

OUTPUT.
Legend

(2) LEGENDRE
COEFFICIENTS - POSSIBLY CORRECTED TO ELIMINATE
Legend

NEGATIVE VALUES AND WITHOUT HIGHER ORDER ZERO COEFFICIENTS.    Legend

BY DEFINITION DISTRIBUTIONS DEFINED BY LEGENDRE COEFFICIENTS   Legend

ARE NORMALIZED TO UNITY.                                       Legend

Legend

(3) ANGULAR
DISTRIBUTIONS GIVEN BY A TABULATION (LTT=2)
Legend

-------------------------------------------------------
Legend

TABULATED
ANGULAR DISTRIBUTIONS ARE GIVEN AT A SERIES OF ENERGIES. Legend

AN INTERPOLATION
LAW IS GIVEN BETWEEN ENERGIES. THE INTERPOLATION  Legend

LAW BETWEEN
ENERGIES IS COPIED AS INPUT (I.E., NO ATTEMPT IS
Legend

MADE TO
LINEARIZE THE VARIATION WITH ENERGY). FOR EACH ENERGY AT   Legend

AT WHICH
TABULATED DATA ARE GIVEN A LINEARLY INTERPOLABLE ANGULAR  Legend

DISTRIBUTION IS
CONSTRUCTED IN THE SYSTEM IN WHICH THE TABULATED   Legend

DATA ARE GIVEN
(I.E., CM OR LAB - NO ATTEMPT IS MADE TO CONVERT    Legend

FROM ONE SYSTEM
TO THE OTHER). A MAXIMUM OF 60000 POINTS IS ALLOWE Legend

TO REPRESENT THE
ANGULAR DISTRIBUTION AT EACH ENERGY.
Legend

Legend

ELIMINATION OF
NEGATIVE VALUES
Legend

------------------------------
Legend

THE
RECONSTRUCTED ANGULAR DISTRIBUTION WILL BE TESTED AND IF IT    Legend

IS NEGATIVE AT
ONE OR MORE COSINES AN ERROR MESSAGE WILL BE OUTPUT Legend

AND BASED ON THE
INPUT OPTION SELECTED ONE OF THE FOLLOWING
Legend

CORRECTIVE ACTIONS
WILL BE TAKEN (SEE, INPUT OPTIONS),
Legend

(1) NO
CORRECTION
Legend

(2) CHANGE ALL
TABULATED VALUES TO FORCE DISTRIBUTION TO BE
Legend

POSITIVE (MINIMUM MORE THAN 1 MILLI-BARN). THE MINIMUM VALUE   Legend

MAY BE CHANGED BY INPUT. WITH THIS OPTION THERE IS NO
Legend

RESTRICTION ON THE AMOUNT THAT EACH VALUE IS CHANGED AND AS    Legend

SUCH THIS OPTION SHOULD BE USED WITH CAUTION AND ONLY AS A     Legend

LAST RESORT IF NO OTHER APPROACH CAN BE USED TO MAKE THE       Legend

DISTRIBUTION POSITIVE.
Legend

Legend

OUTPUT
Legend

------
Legend

THE OUTPUT WILL
BE THE LINEARIZED ANGULAR DISTRIBUTION. THE
Legend

TABULATED
DISTRIBUTION WILL BE NORMALIZED TO UNITY BEFORE OUTPUT.  Legend

Legend

CORRECTING
NEGATIVE ANGULAR DISTRIBUTION
Legend

----------------------------------------
Legend

IF AN ANGULAR
DISTRIBUTION IS NEGATIVE AN ERROR MESSAGE WILL BE    Legend

PRINTED AND THE
USER MAY DECIDE (BASED ON INPUT OPTION) TO,
Legend

(1) NOT PERFORM
ANY CORRECTIVE ACTION.
Legend

(2) FOR
TABULATED DISTRIBUTIONS - ADD THE SAME VALUE TO EACH POINT Legend

VALUE SUCH THAT WHEN THE DISTRIBUTION IS RE-NORMALIZED THE     Legend

MINIMUM VALUE IS 0.001
(1 MILLI-BARN). THE MINIMUM VALUE CAN   Legend

BE CHANGED BY INPUT. WARNING...EXCEPT FOR SELECTION OF THE     Legend

MINIMUM VALUE (BY INPUT) THE USER HAS NO CONTROL OVER HOW      Legend

MUCH THE DISTRIBUTION IS CHANGED. THEREFORE THIS OPTION SHOULD
Legend

BE USED WITH CAUTION.
Legend

(3) FOR LEGENDRE
COEFFICIENTS ONE OF TWO OPTIONS MAY BE SELECTED,  Legend

(A) CHANGE
INDIVIDUAL COEFFICIENTS (NO ONE COEFFICIENT BY MORE     Legend

THAN 1 PER-CENT) TO MAKE THE DISTRIBUTION POSITIVE WITH A      Legend

MINIMUM VALUE OF 0.001 (1 MILLI-BARN). THE MAXIMUM PER-CENT    Legend

CHANGE IN EACH COEFFICIENT AND MINIMUM VALUE MAY BE CHANGED    Legend

BY INPUT. INPUT THE PROGRAM CANNOT MAKE THE DISTRIBUTION       Legend

POSITIVE BY CHANGING EACH COEFFICIENT BY UP TO THE MAXIMUM     Legend

ALLOWABLE AMOUNT, THE ORIGINAL ANGULAR DISTRIBUTION OR
Legend

COEFFICIENTS WILL BE OUTPUT. ONLY IN THE LATTER CASE SHOULD    Legend

ONE CONSIDER USING OPTION (B) DESCRIBED BELOW.
Legend

(B) LOGICALLY
ADD THE SAME VALUE TO EACH POINT VALUE SUCH THAT     Legend

WHEN THE DISTRIBUTION IS RE-NORMALIZED THE MINIMUM VALUE IS    Legend

0.001 (1 MILLI-BARN). THIS IS EQUIVALENT AT INCREASING P0      Legend

BY A CERTAIN AMOUNT AND RE-NORMALIZATION IS EQUIVALENT TO THEN
Legend

DIVIDING EACH COEFFICIENT BY A CERTAIN AMOUNT. THEREFORE,      Legend

WHAT IS PHYSICALLY DONE BY THE PROGRAM IS TO DIVIDE EACH       Legend

COEFFICIENT BY THE SAME AMOUNT. WARNING..EXCEPT FOR SELECTION  Legend

OF THE MINIMUM VALUE (BY INPUT) THE USER HAS NO CONTROL OVER   Legend

HOW MUCH THE DISTRIBUTION IS CHANGED. THEREFORE THIS OPTION    Legend

SHOULD BE USED WITH CAUTION.
Legend

Legend

WARNING MESSAGES
FROM PROGRAM
Legend

-----------------------------
Legend

THE WARNING
MESSAGES PRINTED BY THIS PROGRAM SHOULD ONLY BE
Legend

CONSIDERED TO BE
EXACTLY THAT..WARNINGS..NOT AN ABSOLUTE JUDGEMENT Legend

BY THIS PROGRAM
THAT THERE IS SOMETHING WRONG WITH THE DATA. WHEN  Legend

WARNING MESSAGES
ARE PRINTED EXAMINE THE DATA AND EITHER TAKE NO   Legend

ACTION (IF YOU
FEEL THAT THE DATA IS O.K.) OR CORRECT THE DATA     Legend

(IF YOU FEEL
THAT THE DATA IS INCORRECT AND YOU CAN CORRECT IT).   Legend

Legend

VALIDITY OF
MODIFIED DATA
Legend

-------------------------
Legend

BEFORE BELIEVING
AND USING DATA WHICH HAS BEEN MODIFIED (EITHER    Legend

TABULATED
ANGULAR DISTRIBUTIONS OR LEGENDRE COEFFICIENTS) THE USER Legend

SHOULD INSURE
THAT THE MODIFIED DATA IS PHYSICALLY MORE ACCEPTABLE Legend

THAN THE
ORIGINAL DATA. IN ORDER TO DO THIS ONE OR MORE OF THE     Legend

FOLLOWING
METHODS SHOULD BE USED,
Legend

Legend

(1) USE THE
ENERGY VARIATION TESTS BUILT-IN TO THIS PROGRAM AND    Legend

EVALPLOT TO PLOT THE ENERGY DEPENDENCE OF THE LEGENDRE
Legend

COEFFICIENTS IN ORDER TO IDENTIFY AND CORRECT (BY HAND...NOT   Legend

BY THIS PROGRAM) ANY COEFFICIENTS WHICH HAVE UNREALISTIC       Legend

ENERGY AND L ORDER VARIATIONS. THIS SHOULD ALWAYS BE DONE      Legend

FIRST TO ELIMINATE MAJOR PROBLEMS BEFORE USING THIS PROGRAM    Legend

TO AUTOMATICALLY MAKE MINOR CORRECTIONS.
Legend

(1) OUTPUT AND PLOT THE
UNCORRECTED AND CORRECTED ANGULAR
Legend

DISTRIBUTIONS. COMPARE THE PLOTS TO INSURE THAT THE CORRECTED  Legend

DATA DOES NOT SERIOUSLY CHANGE THE ENERGY DEPENDENCE OF THE    Legend

ANGULAR DISTRIBUTION.
Legend

(2) IF PLOTTING
CAPABILITY IS NOT AVAIALABLE, USE THE PRINTED OUT  Legend

OF THIS PROGRAM TO DETERMINE HOW MUCH THE TABULATED ANGULAR    Legend

DISTRIBUTION OR LEGENDRE COEFFICIENTS HAVE BEEN MODIFIED.      Legend

GENERALLY IF ONE COEFFICIENT HAS BEEN ONLY SLIGHTLY MODIFIED   Legend

THE DISTRIBUTION WILL BE ACCEPTABLE. HOWEVER IF MANY
Legend

COEFFICIENTS HAVE BEEN MODIFIED THE RESULT WILL NOT BE
Legend

RELIABLE.
Legend

Legend

SEEING ANGULAR
DISTRIBUTIONS AND LEGENDRE COEFFICIENTS
Legend

------------------------------------------------------
Legend

PROGRAM EVALPLOT
CAN BE USED TO PLOT ANGULAR DISTRIBUTION AND      Legend

LEGENDRE
COEFFICIENTS - WHEN IT COMES TO CHECKING THIS TYPE OF     Legend

DATA THERE IS NO
SUBSTITUTE FOR PLOTS OF THE DATA TO MAKE THE      Legend

JOB EASY AND
STRAIGHTFORWARD.
Legend

Legend

FOR LEGENDRE
COEFFICIENTS EVALPLOT CAN BE USED TO SEE THE ENERGY   Legend

DEPENDENCE OF
EACH COEFFICIENT - THIS IS AN EXTREMELY EASY AND     Legend

USEFUL WAY TO
CHECK FOR ERRORS IN THE BASIC DATA.
Legend

Legend

FOR ANGULAR
DISTRIBUTION EVALPLOT CAN BE USED TO PLOT THEM AT      Legend

EACH ENERGY THAT
THEY ARE TABULATED - THIS IS ALSO AN EASY AND     Legend

USEFUL WAY TO
CHECK FOR ERRORS.
Legend

Legend

I/O UNIT
DEFINITIONS
Legend

--------------------
Legend

UNIT  DESCRIPTION
Legend

----  -----------
Legend

2   INPUT CARDS
Legend

3   OUTPUT REPORT
Legend

10   ORIGINAL DATA IN ENDF/B
FORMAT
Legend

11   FINAL DATA IN ENDF/B FORMAT
Legend

Legend

OPTIONAL
STANDARD FILE NAMES (SEE SUBROUTINE FILIO1 AND FILIO2)    Legend

---------------------------------------------------------------    Legend

UNIT  FILE NAME
Legend

----  ----------
Legend

2   LEGEND.INP
Legend

3   LEGEND.LST
Legend

10   ENDFB.IN
Legend

11   ENDFB.OUT
Legend

Legend

INPUT CARD
Legend

----------
Legend

CARD
COLS.  FORMAT  DESCRIPTION
Legend

----
-----  ------ -----------
Legend

1    1-11   E11.4 FRACTIONAL THINNING
CRITERIA
Legend

12-22   I11   MAXIMUM NUMBER OF POINTS IN
ANGULAR DISTRIBUTION
Legend

RECONSTRUCTED FROM LEGENDRE COEFFICIENTS (PRESENT   Legend

LIMITS ARE 11 TO 60000 POINTS)
Legend

*THIS
OPTION CAN BE USED TO RUN QUICK, BUT NOT       Legend

NECESSARILY SO ACCURATE CALCULATIONS - TO ROUGHLY   Legend

SEE WHAT THE ANGULAR DISTRIBUTIONS LOOK LIKE.
Legend

*IT IS RECOMMENDED
THAT YOU USE 0 AS INPUT - IN      Legend

WHICH CASE THE PROGRAM WILL USE THE MAXIMUM
Legend

ALLOWABLE NUMBER OF POINTS = 60000.
Legend

23-33   I11   TABULATED ANGULAR DISTRIBUTION
TREATMENT
Legend

= 0 - COPY TABLES
Legend

= 1 - LINEARIZE TABLES (OUTPUT TABLES)
Legend

= 2 - LINEARIZE AND THIN TABLES (OUTPUT TABLES)     Legend

34-44   I11   LEGENDRE COEFFICIENT
TREATMENT
Legend

= 0 - COPY LEGENDRE COEFFICIENTS
Legend

= 1 - RECONSTRUCT TABULATED ANGULAR DISTRIBUTION.   Legend

(OUTPUT TABLES).
Legend

= 2 - RECONSTRUCT TABULATED ANGULAR DISTRIBUTION.   Legend

(OUTPUT LEGENDRE COEFFICIENTS).
Legend

45-55   I11   NEGATIVE ANGULAR DISTRIBUTION
TREATMENT.
Legend

= 0 - NO CORRECTION
Legend

= 1 - TABULATE DATA - NO CORRECTION.
Legend

- LEGENDRE DATA - CHANGE COEFFICIENTS
Legend

(NONE BY MORE THAN 1.0 PER-CENT - CAN BE      Legend

CHANGED BY INPUT).
Legend

= 2 - FORCE DISTRIBUTIONS TO BE POSITIVE
Legend

(TABULATED OR LEGENDRE DATA).
Legend

56-66   I11   LEGENDRE COEFFICIENT VARIATION
TEST FLAG.
Legend

=
0 - TEST TESTS.
Legend

= 1 - PERFORM TESTS,
Legend

(A) LEGENDRE ORDER INCREASES WITH ENERGY.     Legend

(C)
MONOTONIC VARIATION OF COEFFICIENTS       Legend

AS A FUNCTION OF ENERGY.
Legend

(C) COEFFICIENTS DECREASE AS A FUNCTION OF    Legend

LEGENDRE
ORDER.
Legend

2   1-60   60A1  ENDF/B INPUT DATA FILENAME
Legend

(STANDARD OPTION = ENDFB.IN)
Legend

3   1-60   60A1  ENDF/B OUTPUT DATA FILENAME
Legend

(STANDARD OPTION = ENDFB.OUT)
Legend

4-N   1- 6    I6   LOWER MAT LIMIT
Legend

7-
8    I2   LOWER MF LIMIT
Legend

9-11    I3   LOWER MT LIMIT
Legend

12-17    I6   UPPER MAT LIMIT
Legend

18-19    I2   UPPER MF LIMIT
Legend

20-22    I3   UPPER MT LIMIT
Legend

23-33  E11.4  LOWER ENERGY LIMIT
Legend

34-44  E11.4  UPPER ENERGY LIMIT
Legend

45-55  E11.4  MINIMUM ALLOWABLE VALUE OF ANGULAR
DISTRIBUTION
Legend

56-66  E11.4  ALLOWABLE FRACTION (NOT PER-CENT) CHANGE
IN ANY
Legend

ONE LEGENDRE COEFFICIENT TO MAKE THE ANGULAR        Legend

DISTRIBUTION POSITIVE (AND AT LEAST EQUAL TO THE    Legend

INPUT MINIMUM ALLOWABLE VALUE).
Legend

Legend

*UP TO 100 MAT/MT/E
RANGES MAY BE INPUT, EACH SPECIFYING AN
Legend

ALLOWABLE
MINIMUM SIGMA AND MAXIMUM CHANGE IN COEFFICIENTS.
Legend

*INPUT IS
TERMINATED BY A BLANK CARD.
Legend

*ALL MAY/MT/E
RANGES NOT SPECIFIED BY INPUT WILL BE TREATED BY     Legend

ALLOWING A
MINIMUM SIGMA OF 0.001 (1 MILLI-BARN) AND A CHANGE     Legend

IN EACH
COEFFICIENT BY UP TO 0.01 (1 PER-CENT).
Legend

*THESE MAT/MT/E
RANGES ARE NOT USED TO CORRECT ALL ANGULAR
Legend

DISTRIBUTIONS WHERE SIGMA IS LESS THAN THE MINIMUM. THEY ARE      Legend

ONLY USED
TO CORRECT DISTRIBUTION THAT ARE NEGATIVE AND TO
Legend

INSURE
THAT THE CROSS SECTION AT THE COSINES WHERE THE ANGULAR    Legend

DISTRIBUTION ARE INITIALLY NEGATIVE ARE CORRECTED TO BE POSITIVE  Legend

AND AT
LEAST AS LARGE AS THE MINIMUM ALLOWABLE SIGMA (SPECIFIED   Legend

BY
INPUT).
Legend

Legend

EXAMPLE INPUT
NO. 1
Legend

-------------------
Legend

PROCESS BOTH
LEGENDRE COEFFICIENTS AND TABULATED DATA TO OBTAIN    Legend

ANGULAR
DISTRIBUTION WHICH ARE ACCURATE TO WITHIN 0.1 PER-CENT     Legend

AND OUTPUT
UNCORRECTED TABULATED ANGULAR DISTRIBUTION USING
Legend

A MAXIMUM OF 501
POINTS IN EACH TABULATED ANGULAR DISTRIBUTION.    Legend

SINCE LEGENDRE
COEFFICIENTS WILL NOT BE CORRECTED THE INPUT NEED   Legend

NOT SPECIFY
MAT/MT/E RANGES.
Legend

Legend

READ
/ENDFB6/K300/LEAD.IN AND WRITE /ENDFB6/K300/LEAD.OUT
Legend

Legend

THE FOLLOWING 4 INPUT
LINES ARE REQUIRED,
Legend

Legend

1.00000- 3
501
2
1
0
Legend

/ENDFB6/K300/LEAD.IN
Legend

/ENDFB6/K300/LEAD.OUT
Legend

(BLANK CARD
TERMINATED INPUT)
Legend

Legend

EXAMPLE INPUT
NO. 2
Legend

-------------------
Legend

PROCESS BOTH
LEGENDRE COEFFICIENTS AND TABULATED DATA TO OBTAIN    Legend

ANGULAR
DISTRIBUTION WHICH ARE ACCURATE TO WITHIN 0.1 PER-CENT     Legend

AND OUTPUT
CORRECTED TABULATED ANGULAR DISTRIBUTION (ONLY THOSE    Legend

RE-CONSTRUCTED
FROM LEGENDRE COEFFICIENTS WILL BE CORRECTED).      Legend

FOR ALL MAT/MT/E
CORRECT NEGATIVE ANGULAR DISTRIBUTION TO A VALUE  Legend

OF 0.01 (10
MILLI-BARNS) AND ALLOW LEGENDRE COEFFICIENTS TO BE     Legend

CHANGED BY UP TO
0.02 (2 PER-CENT).
Legend

Legend

USE THE DEFAULT
FILENAMES ENDFB.IN AND ENDFB.OUT (THIS CAN BE      Legend

DONE BY LEAVING
THE SECOND AND THIRD INPUT LINES BLANK).
Legend

Legend

THE FOLLOWING 5
INPUT LINES ARE REQUIRED,
Legend

Legend

1.00000- 3
501
2
1
1
Legend

Legend

Legend

1 1  1
999999999 0.00000+ 0 3.00000+ 7 1.00000- 2 2.00000- 2      Legend

(BLANK CARD
TERMINATED INPUT)
Legend

Legend

EXAMPLE INPUT
NO. 3
Legend

-------------------
Legend

PROCESS BOTH
LEGENDRE COEFFICIENTS AND TABULATED DATA TO OBTAIN    Legend

ANGULAR DISTRIBUTION
WHICH ARE ACCURATE TO WITHIN 0.1 PER-CENT     Legend

AND OUTPUT
CORRECTED LEGENDRE COEFFICIENTS AND UNCORRECTED
Legend

TABULATED
ANGULAR DISTRIBUTIONS. FOR MAT=1800, MT=2 CORRECT
Legend

NEGATIVE ANGULAR
DISTRIBUTIONS TO INSURE THE MINIMUM IS 0.01
Legend

(10 MILLI-BARNS)
ALLOWING EACH LEGENDRE COEFFICIENT TO CHANGE BY   Legend

UP TO 0.02 (2
PER-CENT). ALL OTHER MAT/MT/E WILL BE CORRECTED      Legend

TO A MINIMUM OF
0.001 (1 MILLI-BARN) ALLOWING A 0.01 (1 PER-CENT)  Legend

CHANGE (BUILT-IN
OPTION).
Legend

Legend

READ
/ENDFB6/K300/LEAD.IN AND WRITE /ENDFB6/K300/LEAD.OUT
Legend

Legend

THE FOLLOWING 5
INPUT LINES ARE REQUIRED,
Legend

Legend

1.00000- 3
501
2
2
1
Legend

/ENDFB6/K300/LEAD.IN
Legend

/ENDFB6/K300/LEAD.OUT
Legend

1800 4  2  1800 4  2 0.00000+ 0 3.00000+ 7 1.00000- 2
2.00000- 2
Legend

(BLANK CARD
TERMINATED INPUT)
Legend

Legend

EXAMPLE INPUT
NO. 4
Legend

-------------------
Legend

TO COPY
TABULATED ANGULAR DISTRIBUTION AND CONVERT LEGENDRE
Legend

COEFFICIENTS TO
UNCORRECTED TABULAR DISTRIBUTIONS.
Legend

Legend

USE THE DEFAULT
FILENAMES ENDFB.IN AND ENDFB.OUT (THIS CAN BE      Legend

DONE BY LEAVING
THE SECOND AND THIRD INPUT LINES BLANK).
Legend

Legend

THE FOLLOWING 4
INPUT LINES ARE REQUIRED,
Legend

Legend

1.00000- 3
501
0
1
0
Legend

Legend

Legend

(BLANK CARD
TERMINATED INPUT)
Legend

Legend

=======================================================================
Legend

=======================================================================
Linear

Linear

PROGRAM
LINEAR
Linear

VERSION 74-1
(MAY 1974)
Linear

VERSION 75-1
(APRIL 1975)
Linear

VERSION 76-2
(OCTOBER 1976)
Linear

VERSION 77-1
(JANUARY 1977)
Linear

VERSION 78-1
(JULY 1978)
Linear

VERSION 79-1
(JULY 1979) CDC-7600 AND CRAY-1 VERSION.
Linear

VERSION 80-1
(MAY 1980) IBM, CDC AND CRAY VERSION.
Linear

VERSION 80-2
(DECEMBER 1980)
Linear

VERSION 81-1
(MARCH 1981)
Linear

VERSION 82-1
(JANUARY 1982) IMPROVED COMPUTER COMPATIBILITY.
Linear

VERSION 83-1
(JANUARY 1983) *MAJOR RE-DESIGN.
Linear

*PAGE SIZE INCREASED - 1002 TO 3006.   Linear

*ELIMINATED
COMPUTER DEPENDENT CODING. Linear

*NEW, MORE COMPATIBLE I/O UNIT NUMBER. Linear

*ADDED OPTION TO KEEP ALL ORIGINAL     Linear

ENERGY
POINTS FROM EVALUATION.
Linear

*ADDED STANDARD ALLOWABLE ERROR OPTION Linear

(CURRENTLY 0.1 PER-CENT).
Linear

VERSION 83-2
(OCTOBER 1983) IMPROVED BASED ON USER COMMENTS.
Linear

VERSION 84-1
(APRIL 1984)   IMPROVED BASED
ON USER COMMENTS.       Linear

VERSION 84-2
(JUNE 1984)   *UPDATED FOR
ENDF/B-VI FORMATS.
Linear

*SPECIAL I/O ROUTINES TO GUARANTEE      Linear

ACCURACY OF ENERGY.
Linear

*DOUBLE PRECISION TREATMENT OF ENERGY   Linear

(REQUIRED FOR NARROW RESONANCES).      Linear

VERSION 85-1
(AUGUST 1985) *FORTRAN-77/H VERSION
Linear

VERSION 86-1
(JANUARY 1986)*ENDF/B-VI FORMAT
Linear

VERSION 87-1
(JANUARY 1987)*DOUBLE PRECISION TREATMENT OF CROSS    Linear

SECTION
Linear

VERSION 88-1
(JULY 1988)
*OPTION...INTERNALLY DEFINE ALL I/O     Linear

FILE NAMES (SEE, SUBROUTINE FILEIO     Linear

FOR DETAILS).
Linear

*IMPROVED BASED ON USER COMMENTS.
Linear

VERSION 89-1
(JANUARY 1989)*PSYCHOANALYZED BY PROGRAM FREUD TO     Linear

INSURE
PROGRAM WILL NOT DO ANYTHING
Linear

CRAZY.
Linear

*UPDATED TO USE NEW PROGRAM CONVERT     Linear

KEYWORDS.
Linear

*ADDED LIVERMORE
CIVIC COMPILER
Linear

CONVENTIONS.
Linear

VERSION 90-1
(JUNE 1990)   *EXTENDED TO
LINEARIZE PHOTON
Linear

INTERACTION DATA, MF=23 AND 27
Linear

*ADDED FORTRAN SAVE OPTION
Linear

*UPDATED BASED ON USER COMMENTS.
Linear

*NEW MORE CONSISTENT ENERGY OUTPUT      Linear

ROUTINE.
Linear

*WARNING...INPUT PARAMETER FORMAT
Linear

HAS BEEN CHANGED...SEE DESCRIPTION     Linear

BELOW.
Linear

VERSION 91-1
(JULY 1991)   *ADDED
INTERPOLATION LAW 6 - ONLY USED
Linear

FOR CHARGED PARTICLE CROSS SECTIONS    Linear

FOR COULOMB PENETRABILITIES.
Linear

VERSION 92-1
(JANUARY 1992)*ADDED NU-BAR (TOTAL, DELAYED, PROMPT)  Linear

POLYNOMIAL OR TABULATED ALL CONVERTED  Linear

TO LINEARLY INTERPOLABLE
Linear

*INCREASED PAGE SIZE FROM 3006 TO 5010  Linear

POINTS.
Linear

*ALL ENERGIES INTERNALLY ROUNDED PRIOR  Linear

TO CALCULATIONS.
Linear

*COMPLETELY
CONSISTENT I/O AND ROUNDING Linear

ROUTINES - TO MINIMIZE COMPUTER
Linear

DEPENDENCE.
Linear

VERSION 92-2
(JULY 1992)   *CORRECTED
CONVERSION OF NU-BAR FROM
Linear

POLYNOMIAL TO TABULATED - COPY
Linear

SPONTANEOUS NU-BAR (BY DEFINITION      Linear

THE
SPONTANEOUS NU-BAR IS NOT AN
Linear

ENERGY DEPENDENT QUANTITY).
Linear

VERSION 93-1
(MARCH 1993)  *UPDATED FOR USE WITH
LAHEY COMPILER    Linear

ON IBM-PCS.
Linear

*INCREASED PAGE SIZE FROM 5010 TO
Linear

30000 POINTS
Linear

VERSION 94-1
(JANUARY 1994)*VARIABLE ENDF/B DATA FILENAMES
Linear

TO ALLOW ACCESS TO FILE STRUCTURES     Linear

(WARNING - INPUT PARAMETER FORMAT      Linear

HAS BEEN CHANGED)                      Linear

*CLOSE ALL FILES BEFORE TERMINATING     Linear

(SEE, SUBROUTINE ENDIT)
Linear

VERSION 96-1
(JANUARY 1996) *COMPLETE RE-WRITE
Linear

*IMPROVED COMPUTER INDEPENDENCE
Linear

*ALL DOUBLE PRECISION
Linear

*ON SCREEN OUTPUT
Linear

*UNIFORM TREATMENT OF ENDF/B I/O
Linear

*IMPROVED OUTPUT PRECISION
Linear

*DEFINED SCRATCH FILE NAMES
Linear

*ALWAYS INCLUDE THERMAL VALUE
Linear

*INCREASED PAGE SIZE FROM 30000 TO     Linear

60000 POINTS
Linear

VERSION 99-1
(MARCH 1999)   *CORRECTED
CHARACTER TO FLOATING
Linear

POINT READ FOR MORE DIGITS
Linear

*UPDATED TEST FOR ENDF/B FORMAT
Linear

VERSION
BASED ON RECENT FORMAT CHANGE Linear

*GENERAL IMPROVEMENTS BASED ON
Linear

USER FEEDBACK
Linear

VERSION 99-2
(JUNE 1999)    *ASSUME
ENDF/B-VI, NOT V, IF MISSING
Linear

MF=1, MT-451.
Linear

VERS. 2000-1
(FEBRUARY 2000)*ADDED MF = 9 AND 10 LINEARIZATION     Linear

*GENERAL IMPROVEMENTS BASED ON
Linear

USER FEEDBACK
Linear

VERS. 2002-1
(MAY 2002)
*OPTIONAL INPUT PARAMETERS
Linear

VERS. 2004-1
(JAN. 2004)    *GENERAL
UPDATE BASED ON USER FEEDBACK Linear

VERS. 2005-1
(JAN. 2005)    *ALWAYS
KEEP ORIGINAL TABULATED
Linear

NU-BAR POINTS.
Linear

VERS. 2006-1
(FEB. 2006)    *CORRECTED
INT=6 NEAR THRESHOLD
Linear

*NO SUBDIVIDE BELOW MINIMUM XCMIN      Linear

VERS. 2007-1
(JAN. 2007)    *CHECKED
AGAINST ALL ENDF/B-VII.
Linear

*INCREASED PAGE SIZE FROM 60,000 TO
Linear

600,000 POINTS
Linear

Linear

OWNED,
MAINTAINED AND DISTRIBUTED BY
Linear

------------------------------------
Linear

THE NUCLEAR DATA
SECTION
Linear

INTERNATIONAL
ATOMIC ENERGY AGENCY
Linear

P.O. BOX 100
Linear

A-1400, VIENNA, AUSTRIA
Linear

EUROPE
Linear

Linear

ORIGINALLY
WRITTEN BY
Linear

------------------------------------
Linear

DERMOTT E.
CULLEN                                                  Linear

UNIVERSITY OF CALIFORNIA
Linear

LAWRENCE
LIVERMORE
NATIONAL LABORATORY
Linear

L-159
Linear

P.O. BOX 808
Linear

LIVERMORE, CA
94550
Linear

U.S.A.
Linear

TELEPHONE  925-423-7359
Linear

E. MAIL    [email-masked]
Linear

WEBSITE
HTTP://WWW.LLNL.GOV/CULLEN1
Linear

Linear

AUTHORS
MESSAGE
Linear

---------------
Linear

THE REPORT
DESCRIBED ABOVE IS THE LATEST PUBLISHED DOCUMENTATION   Linear

FOR THIS
PROGRAM. HOWEVER, THE COMMENTS BELOW SHOULD BE CONSIDERED Linear

THE LATEST
DOCUMENTATION INCLUDING ALL RECENT IMPROVEMENTS. PLEASE Linear

READ ALL OF
THESE COMMENTS BEFORE IMPLEMENTATION.
Linear

Linear

AT THE PRESENT
TIME WE ARE ATTEMPTING TO DEVELOP A SET OF COMPUTER Linear

INDEPENDENT
PROGRAMS THAT CAN EASILY BE IMPLEMENTED ON ANY ONE     Linear

OF A WIDE
VARIETY OF COMPUTERS. IN ORDER TO ASSIST IN THIS PROJECT Linear

IT WOULD BE
APPECIATED IF YOU WOULD NOTIFY THE AUTHOR OF ANY
Linear

COMPILER DIAGNOSTICS,
OPERATING PROBLEMS OR SUGGESTIONS ON HOW TO  Linear

IMPROVE THIS
PROGRAM. HOPEFULLY, IN THIS WAY FUTURE VERSIONS OF    Linear

THIS PROGRAM
WILL BE COMPLETELY COMPATIBLE FOR USE ON YOUR
Linear

COMPUTER.
Linear

Linear

PURPOSE
Linear

-------
Linear

THIS PROGRAM IS
DESIGNED TO CONVERT ENDF/B FILE 3, 23 AND 27 DATA  Linear

TO LINEAR-LINEAR
INTERPOLABLE FORM. ANY SECTION THAT IS ALREADY    Linear

LINEAR-LINEAR
INTERPOLABLE WILL BE THINNED.
Linear

Linear

IN THE FOLLOWING
DISCUSSION FOR SIMPLICITY THE ENDF/B TERMINOLOGY  Linear

---ENDF/B
TAPE---WILL BE USED. IN FACT THE ACTUAL MEDIUM MAY BE    Linear

TAPE, CARDS,
DISK OR ANY OTHER MEDIUM.
Linear

Linear

ENDF/B
FORMAT
Linear

-------------
Linear

THIS PROGRAM
ONLY USES THE ENDF/B BCD OR CARD IMAGE FORMAT (AS     Linear

OPPOSED TO THE
BINARY FORMAT) AND CAN HANDLE DATA IN ANY VERSION   Linear

OF THE ENDF/B
FORMAT (I.E., ENDF/B-I, II,III, IV, V OR VI FORMAT). Linear

Linear

IT IS ASSUMED
THAT THE DATA IS CORRECTLY CODED IN THE ENDF/B
Linear

FORMAT AND NO ERROR CHECKING IS
PERFORMED. IN PARTICULAR IT IS     Linear

ASSUMED THAT THE
MAT, MF AND MT ON EACH LINE IS CORRECT. SEQUENCE  Linear

NUMBERS (COLUMNS
76-80) ARE IGNORED ON INPUT, BUT WILL BE
Linear

CORRECTLY OUTPUT
ON ALL LINES. THE FORMAT OF SECTION MF=1, MT=451  Linear

AND ALL SECTIONS
OF MF=3 MUST BE CORRECT. THE PROGRAM COPIES ALL   Linear

OTHER SECTION OF
DATA AS HOLLERITH AND AS SUCH IS INSENSITIVE TO   Linear

THE CORRECTNESS
OR INCORRECTNESS OF ALL OTHER SECTIONS.
Linear

Linear

OUTPUT
FORMAT
Linear

-------------
Linear

IN THIS VERSION
OF LINEAR ALL ENERGIES WILL BE OUTPUT IN
Linear

F (INSTEAD OF E)
FORMAT IN ORDER TO ALLOW ENERGIES TO BE WRITTEN   Linear

WITH UP TO 9
DIGITS OF ACCURACY. IN PREVIOUS VERSIONS THIS WAS AN  Linear

OUTPUT OPTION.
HOWEVER USE OF THIS OPTION TO COMPARE THE RESULTS   Linear

OF ENERGIES
WRITTEN IN THE NORMAL ENDF/B CONVENTION OF 6
DIGITS    Linear

TO THE 9 DIGIT
OUTPUT FROM THIS PROGRAM DEMONSTRATED THAT FAILURE  Linear

TO USE THE 9
DIGIT OUTPUT CAN LEAD TO LARGE ERRORS IN THE DATA     Linear

DUE TO
TRUNCATION OF ENERGIES TO 6 DIGITS DURING OUTPUT.
Linear

Linear

CONTENTS OF
OUTPUT
Linear

------------------
Linear

ENTIRE
EVALUATIONS ARE OUTPUT, NOT JUST THE LINEARIZED DATA        Linear

CROSS SECTIONS,
E.G. ANGULAR AND ENERGY DISTRIBUTIONS ARE ALSO     Linear

INCLUDED.
Linear

Linear

DOCUMENTATION
Linear

-------------
Linear

THE FACT THAT
THIS PROGRAM HAS OPERATED ON THE DATA IS DOCUMENTED  Linear

BY THE ADDITION
OF 3 COMMENT LINES AT THE END OF EACH HOLLERITH    Linear

SECTION IN THE
FORM
Linear

Linear

***************** PROGRAM LINEAR (2007-1) ****************
Linear

FOR ALL DATA
GREATER THAN 1.00000-10 IN ABSOLUTE VALUE
Linear

DATA LINEARIZED
TO WITHIN AN ACCURACY OF  0.1  PER-CENT
Linear

Linear

THE ORDER OF
SIMILAR COMMENTS (FROM RECENT, SIGMA1 AND GROUPIE)    Linear

REPRESENTS A
COMPLETE HISTORY OF ALL OPERATIONS PERFORMED ON
Linear

THE DATA BY
THESE PROGRAMS.
Linear

Linear

THESE COMMENT
LINES ARE ONLY ADDED TO EXISTING HOLLERITH SECTIONS, Linear

I.E., THIS
PROGRAM WILL NOT CREATE A HOLLERITH SECTION. THE FORMAT Linear

OF THE HOLLERITH
SECTION IN ENDF/B-V DIFFERS FROM THE THAT OF      Linear

EARLIER VERSIONS
OF ENDF/B. BY READING AN EXISTING MF=1, MT=451    Linear

IT IS POSSIBLE
FOR THIS PROGRAM TO DETERMINE WHICH VERSION OF      Linear

THE ENDF/B
FORMAT THE DATA IS IN. WITHOUT HAVING A SECTION OF      Linear

MF=1, MT=451
PRESENT IT IS IMPOSSIBLE FOR THIS PROGRAM TO
Linear

DETERMINE WHICH
VERSION OF THE ENDF/B FORMAT THE DATA IS IN, AND   Linear

AS SUCH IT IS
IMPOSSIBLE FOR THE PROGRAM TO DETERMINE WHAT FORMAT  Linear

SHOULD BE USED
TO CREATE A HOLLERITH SECTION.
Linear

Linear

REACTION INDEX
Linear

--------------
Linear

THIS PROGRAM
DOES NOT USE THE REACTION INDEX WHICH IS GIVEN IN     Linear

SECTION MF=1,
MT=451 OF EACH EVALUATION.
Linear

Linear

THIS PROGRAM
DOES NOT UPDATE THE REACTION INDEX IN MF=1, MT=451.   Linear

THIS CONVENTION
HAS BEEN ADOPTED BECAUSE MOST USERS DO NOT
Linear

REQUIRE A
CORRECT REACTION INDEX FOR THEIR APPLICATIONS AND IT WAS Linear

NOT CONSIDERED
WORTHWHILE TO INCLUDE THE OVERHEAD OF CONSTRUCTING  Linear

A CORRECT
REACTION INDEX IN THIS PROGRAM. HOWEVER, IF YOU REQUIRE  Linear

A REACTION INDEX
FOR YOUR APPLICATIONS, AFTER RUNNING THIS PROGRAM Linear

YOU MAY USE
PROGRAM DICTIN TO CREATE A CORRECT REACTION INDEX.     Linear

Linear

SECTION
SIZE
Linear

------------
Linear

SINCE THIS
PROGRAM USES A LOGICAL PAGING SYSTEM THERE IS NO LIMIT  Linear

TO THE NUMBER OF
POINTS IN ANY SECTION, E.G., THE TOTAL CROSS      Linear

SECTION MAY BE
REPRESENTED BY 200,000 DATA POINTS.
Linear

Linear

FOR ANY
LINEARIZED SECTION THAT CONTAINS 60000 OR FEWER POINTS     Linear

THE ENTIRE
OPERATION WILL BE PERFORMED IN CORE AND THE LINEARIZED  Linear

DATA WILL BE
OUTPUT DIRECTLY TO THE ENDF/B FORMAT. FOR ANY SECTION Linear

THAT CONTAINS
MORE POINTS THE DATA WILL BE LINEARIZED A PAGE AT A  Linear

TIME (1 PAGE =
60000 POINTS) AND OUTPUT TO SCRATCH. AFTER THE      Linear

ENTIRE SECTION
HAS BEEN LINEARIZED THE DATA WILL BE READ BACK FROM Linear

SCRATCH AND
OUTPUT TO THE ENDF/B FORMAT.
Linear

Linear

SELECTION OF
DATA
Linear

-----------------
Linear

THE PROGRAM
SELECTS DATA TO BE LINEARIZED BASED EITHER ON EITHER   Linear

MAT (ENDF/B MAT
NO.) OR ZA AS WELL AS MF AND MT NUMBERS. THIS      Linear

PROGRAM ALLOWS
UP TO 100 MAT/MF/MT OR ZA/MF/MT RANGES TO BE
Linear

SPECIFIED BY
INPUT PARAMETERS. THE PROGRAM WILL ASSUME THAT THE    Linear

ENDF/B TAPE IS
IN MAT ORDER, REGARDLESS OF THE CRITERIA USED
Linear

TO RETRIEVE
MATERIALS. IF RETRIEVAL IS BY MAT RANGE THE PROGRAM    Linear

WILL TERMINATE
WHEN A MAT IS FOUND THAT IS ABOVE ALL REQUESTED     Linear

MAT RANGES. IF
RETRIEVAL IS BY ZA RANGE THE PROGRAM WILL SEARCH    Linear

THE ENTIRE
ENDF/B TAPE.
Linear

Linear

PROGRAM
OPERATION
Linear

-----------------
Linear

EACH SECTION OF
DATA IS CONSIDERED SEPARATELY. EACH SECTION OF     Linear

ENDF/B DATA TO
LINEARIZE IS REPRESENTED BY A TABLE OF ENERGY
Linear

VS. CROSS
SECTION AND ANY ONE OF FIVE ALLOWABLE INTERPOLATION LAWS Linear

BETWEEN ANY TWO
TABULATED POINTS. THIS PROGRAM WILL REPLACE EACH   Linear

SECTION OF DATA
CROSS SECTIONS BY A NEW TABLE OF ENERGY VS.
Linear

CROSS SECTION IN
WHICH THE INTERPOLATION LAW IS ALWAYS LINEAR IN   Linear

ENERGY AND CROSS
SECTION BETWEEN ANY TWO TABULATED POINTS.
Linear

Linear

DATA IS READ AND
LINEARIZED A PAGE AT A TIME (ONE PAGE CONTAINS    Linear

60000 DATA
POINTS). IF THE FINAL LINEARIZED SECTION CONTAINS TWO   Linear

PAGES OR LESS,
DATA POINTS IT WILL BE ENTIRELY CORE RESIDENT
Linear

AFTER IT HAS
BEEN LINEARIZED AND WILL BE WRITTEN DIRECTLY FROM     Linear

CORE TO THE
OUTPUT TAPE. IF THE LINEARIZED SECTION IS LARGER THAN  Linear

TWO PAGES, AFTER
EACH PAGE IS LINEARIZED IT WILL BE WRITTEN TO     Linear

SCRATCH. AFTER
THE ENTIRE SECTION HAS BEEN LINEARIZED IT WILL      Linear

BE READ BACK
FROM SCRATCH, TWO PAGES AT A TIME, AND WRITTEN TO     Linear

THE OUTPUT
TAPE.
Linear

Linear

KEEP EVALUATED
DATA POINTS
Linear

--------------------------
Linear

SOMETIMES IT IS
CONVENIENT TO KEEP ALL ENERGY POINTS WHICH WERE    Linear

PRESENT IN THE
ORIGINAL EVALUATION AND TO MERELY SUPPLEMENT THESE  Linear

POINTS WITH
ADDITIONAL ENERGY POINTS IN ORDER TO LINEARIZE THE     Linear

CROSS SECTIONS.
FOR EXAMPLE, IT IS OFTEN CONVENIENT TO KEEP THE    Linear

THERMAL VALUE
(AT 0.0253 EV) OR THE VALUE AT 14.1 MEV.
Linear

Linear

THE CURRENT
VERSION OF THIS PROGRAM WILL ALLOW THE USER TO KEEP    Linear

ALL ORIGINAL
EVALUATED DATA POINTS BY SPECIFYING 1 IN COLUMNS      Linear

34-44 OF THE
FIRST INPUT LINE. THIS WILL TURN OFF THE BACKWARD     Linear

THINNING (SEE
UCRL-50400, VOL. 17, PART A FOR EXPLANATION) AND     Linear

RESULT IN ALL
ORIGINAL ENERGY POINTS BEING KEPT. CAUTION SHOULD    Linear

BE EXERCISED IN
USING THIS OPTION SINCE IT CAN RESULT IN A
Linear

CONSIDERABLE
INCREASE IN THE NUMBER OF DATA POINTS OUTPUT BY
Linear

THIS CODE.
Linear

Linear

FOR ALL USERS
WHO ARE NOT INTERESTED IN THIS OPTIONS NO CHANGES    Linear

ARE REQUIRED IN
THE INPUT TO THIS PROGRAM, I. E. IF COLUMNS
Linear

34-44 ARE BLANK (AS
FOR ALL PREVIOUS VERSIONS OF THIS CODE) THE    Linear

PROGRAM WILL
OPERATE EXACTLY AS IT DID BEFORE.
Linear

Linear

ALLOWABLE
ERROR
Linear

---------------
Linear

ALLOWABLE ERROR
MUST ALWAYS BE SPECIFIED IN THE INPUT TO THIS      Linear

PROGRAM AS A
FRACTION, NOT A PER-CENT. FOR EXAMPLE, INPUT THE      Linear

ALLOWABLE
FRACTIONAL ERROR 0.001 IN ORDER TO OBTAIN DATA THAT IS   Linear

ACCURATE TO
WITHIN 0.1 PER-CENT.
Linear

Linear

THE CONVERSION
OF THE DATA FROM THE GENERAL INTERPOLATION FORM TO  Linear

LINARLY
INTERPOLABLE FORM CANNOT BE PERFORMED EXACTLY. HOWEVER, IT Linear

CAN BE PERFORMED
TO VIRTUALLY ANY REQUIRED ACCURACY AND MOST
Linear

IMPORTANTLY CAN
BE PERFORMED TO A TOLERANCE THAT IS SMALL COMPARED Linear

TO THE
UNCERTAINTY IN THE CROSS SECTIONS THEMSELVES. AS SUCH THE   Linear

CONVERSION OF
CROSS SECTIONS TO LINEARLY INTERPOLABLE FORM CAN BE  Linear

PERFORMED WITH
ESSENTIALLY NO LOSE OF INFORMATION.
Linear

Linear

THE ALLOWABLE
ERROR MAY BE ENERGY INDEPENDENT (CONSTANT) OR ENERGY Linear

DEPENDENT. THE
ALLOWABLE ERROR IS DESCRIBED BY A TABULATED
Linear

FUNCTION OF UP
TO 20 (ENERGY,ERROR) PAIRS AND LINEAR INTERPOLATION Linear

BETWEEN
TABULATED POINTS. IF ONLY ONE TABULATED POINT IS GIVEN THE Linear

ERROR WILL BE
CONSIDERED CONSTANT OVER THE ENTIRE ENERGY RANGE.    Linear

WITH THIS ENERGY
DEPENDENT ERROR ONE MAY OPTIMIZE THE OUTPUT FOR   Linear

ANY GIVEN
APPLICATION BY USING A SMALL ERROR IN THE ENERGY RANGE   Linear

OF INTEREST AND A LESS
STRINGENT ERROR IN OTHER ENERGY RANGES.     Linear

Linear

DEFAULT
ALLOWABLE ERROR
Linear

-----------------------
Linear

IN ORDER TO
INSURE CONVERGENCE OF THE LINEARIZING ALGORITHM THE    Linear

ALLOWABLE ERROR
MUST BE POSITIVE. IF THE USER INPUTS AN ERROR      Linear

THAT IS NOT POSITIVE
IT WILL AUTOMATICALLY BE SET TO THE DEFAULT   Linear

VALUE (CURRENTLY
0.001, CORRESPONDING TO 0.1 PER-CENT) AND
Linear

INDICATED AS
SUCH IN THE OUTPUT LISTING.
Linear

Linear

COULOMB
PENETRABILITY (INTERPOLATION LAW = 6)
Linear

--------------------------------------------
Linear

INTRODUCED FOR
ENDF/B-VI. THIS IS DEFINED AS,
Linear

Linear

SIG(E) =
C1*EXP(-C2/SQRT(E - T))
Linear

Linear

THIS PROGRAM
ONLY CONSIDERS EXOTHERMIC REACTIONS - T = 0
Linear

Linear

SIG(E) =
C1*EXP(-C2/SQRT(E))
Linear

Linear

WARNING...THIS
INTERPOLATION LAW SHOULD ONLY BE USED FOR REACTIONS Linear

WHICH HAVE A POSITIVE Q-VALUE (EXOTHERMIC REACTIONS),    Linear

SINCE HERE WE ONLY CONSIDER T = 0.0 IN THE FORMALISM.    Linear

IN ALL OTHER CASES A WARNING MESSAGE WILL BE PRINTED.    Linear

Linear

INPUT FILES
Linear

-----------
Linear

UNIT  DESCRIPTION
Linear

----  -----------
Linear

2  INPUT LINES (BCD - 80
CHARACTERS/RECORD)
Linear

10  ORIGINAL ENDF/B DATA (BCD
- 80 CHARACTERS/RECORD)
Linear

Linear

OUTPUT
FILES
Linear

------------
Linear

UNIT  DESCRIPTION                                                  Linear

----  -----------
Linear

3  OUTPUT REPORT (BCD - 120
CHARACTERS/RECORD)
Linear

11  FINAL ENDF/B DATA (BCD -
80 CHARACTERS/RECORD)
Linear

Linear

SCRATCH
FILES
Linear

-------------
Linear

UNIT  DESCRIPTION
Linear

----  -----------
Linear

12  SCRATCH FILE (BINARY -
180000 WORDS/RECORD                   Linear

Linear

OPTIONAL
STANDARD FILE NAMES (SEE SUBROUTINE FILEIO)
Linear

----------------------------------------------------
Linear

UNIT  FILE NAME
Linear

----  ----------
Linear

2   LINEAR.INP
Linear

3   LINEAR.LST
Linear

10   ENDFB.IN
Linear

11   ENDFB.OUT
Linear

12   (SCRATCH)
Linear

Linear

Linear

INPUT PARAMETERS
Linear

----------------
Linear

FOR VERSIONS
EARLIER THAN 90-1 THIS PROGRAM ONLY ALLOWED THE USER  Linear

TO SPECIFY BY
INPUT PARAMETERS WHICH MATERIALS (MAT) TO PROCESS.   Linear

FOR EACH
REQUESTED MATERIAL NEUTRON INTERACTION CROSS SECTIONS     Linear

(MF=3) WOULD BE
LINEARIZED AND THE REMAINDER OF THE MATERIAL
Linear

WOULD BE
COPIED.
Linear

Linear

FOR VERSIONS
90-1 AND LATER THIS PROGRAM WILL ALLOW THE USER TO    Linear

TO SPECIFY BY
INPUT PARAMETERS EXACTLY WHAT SECTIONS OF DATA
Linear

TO PROCESS. FOR
EACH SECTION OF DATA, SPECIFIED BY MAT, MF, MT     Linear

RANGES, SECTIONS
OF MF=3, 23 AND 27 WILL BE LINEARIZED AND ALL     Linear

OTHER REQUESTED
SECTIONS WILL BE COPIED. ALL SECTIONS WHICH ARE    Linear

NOT EXPLICITLY
REQUESTED WILL BE SKIPPED AND WILL NOT APPEAR ON    Linear

ENDF/B FILE
OUTPUT BY THIS PROGRAM.
Linear

Linear

WITH THIS NEW
PROCEDURE YOU CAN MINIMIZE THE SIZE OF THE ENDF/B    Linear

FILE OUTPUT BY
THIS PROGRAM, E.G., IF YOU ONLY WANT NEUTRON
Linear

CROSS SECTIONS
FOR SUBSEQUENT PROCESSING YOU NEED ONLY REQUEST     Linear

ONLY MF=3
DATA.
Linear

Linear

HOWEVER, YOU
MUST UNDERSTAND THAT ONLY THOSE SECTIONS WHICH YOU    Linear

EXPLICITLY
REQUEST WILL APPEAR ON THE ENDF/B FILE OUTPUT BY
Linear

THIS PROGRAM.
FOR EXAMPLE, IF YOU WISH TO DOCUMENT EXACTLY
Linear

HOW YOU
LINEARIZED THE DATA BY INCLUDING COMMENTS IN MF=1, MT=451  Linear

THEN YOU MUST
EXPLICITLY REQUEST THAT MF=1, MT=451 BE PROCESSED    Linear

FOR EACH
MATERIAL THAT YOU REQUEST. SIMILAR IF YOU WANT THE
Linear

ENTIRE
EVALUATION YOU MUST REQUEST ALL MF AND MT TO BE OUTPUT.     Linear

Linear

LINE  COLS.  DESCRIPTION
Linear

----  -----  -----------
Linear

1   1-11  SELECTION CRITERIA (0=MAT, 1=ZA)
Linear

12-22  MONITOR MODE
SELECTOR
Linear

= 0 - NORMAL OPERATION
Linear

= 1 - MONITOR PROGRESS OF LINEARIZING OF THE DATA.    Linear

EACH TIME A PAGE OF DATA POINTS IS WRITTEN TO   Linear

THE SCRATCH FILE PRINT OUT THE TOTAL NUMBER OF  Linear

POINTS ON SCRATCH AND THE LOWER AND UPPER
Linear

ENERGY LIMITS OF THE PAGE (THIS OPTION MAY BE   Linear

USED IN ORDER TO MONITOR THE EXECUTION SPEED    Linear

OF LONG RUNNING JOBS).
Linear

23-33  MINIMUM CROSS SECTION
OF INTEREST (BARNS).
Linear

(IF 0.0 OR LESS IS INPUT THE PROGRAM WILL
Linear

USE 1.0E-10). ENERGY INTERVALS WILL NOT BE
Linear

SUB-DIVIDED IF THE ABSOLUTE VALUE OF THE CROSS
Linear

SECTION WITHIN THE INTERVAL IS LESS THAN THIS VALUE.  Linear

AN EXCEPTION TO THIS RULE IS NEAR THRESHOLDS ENERGY   Linear

INTERVALS
WILL BE SUB-DIVIDED UNTIL CONVERGENCE       Linear

REGARDLESS OF THE MAGNITUDE OF THE CROSS SECTION.     Linear

34-44  KEEP ORIGINAL
EVALUATED DATA POINTS.
Linear

= 0
- NO.
Linear

= 1 - YES - ADDITIONAL POINTS MAY BE ADDED IN ORDER   Linear

TO LINEARIZE DATA, BUT ALL ORIGINAL
Linear

DATA
POINTS WILL BE INCLUDED IN THE
Linear

RESULTS.
Linear

2   1-60  ENDF/B INPUT DATA FILENAME
Linear

(STANDARD OPTION = ENDFB.IN)
Linear

3   1-60  ENDF/B OUTPUT DATA FILENAME
Linear

(STANDARD OPTION = ENDFB.OUT)
Linear

4-N   1- 6  LOWER MAT OR ZA LIMIT                                 Linear

7- 8  LOWER MF LIMIT
Linear

9-11  LOWER MT LIMIT
Linear

12-17  UPPER MAT OR ZA
LIMIT
Linear

18-19  UPPER MF LIMIT
Linear

20-22  UPPER MT LIMIT
Linear

UP TO 100 RANGES MAY BE SPECIFIED, ONLY ONE RANGE     Linear

PER LINE. THE LIST OF RANGES IS TERMINATED BY A
Linear

BLANK LINE. IF THE UPPER MAT LIMIT OF ANY REQUEST     Linear

IS LESS THAN THE LOW LIMIT IT WILL BE SET EQUAL TO    Linear

THE LOWER LIMIT. IF THE UPPER LIMIT IS STILL ZERO     Linear

IT WILL BE SET EQUAL TO 999999. IF THE UPPER MF OR    Linear

MT LIMIT IS ZERO IT WILL BE SET TO 99 OR 999
Linear

RESPECTIVELY.
Linear

VARY  1-11  ENERGY FOR ERROR LAW
Linear

12-22  ALLOWABLE FRACTIONAL
ERROR FOR ERROR LAW.
Linear

THE
ACCEPTABLE LINEARIZING ERROR MAY BE SPECIFIED TO  Linear

BE EITHER ENERGY INDEPENDENT (DEFINED BY A SINGLE     Linear

ERROR), OR ENERGY DEPENDENT (DEFINED BY UP TO 20      Linear

ENERGY, ERROR PAIRS). FOR THE ENERGY DEPENDENT CASE   Linear

LINEAR INTERPOLATION WILL BE USED TO DEFINE THE ERROR Linear

AT ENERGIES BETWEEN THOSE AT WHICH IT IS TABULATED.   Linear

IN ALL CASES THE ERROR LAW IS TERMINATED BY A BLANK   Linear

LINE. IF ONLY ONE ENERGY, ERROR PAIR IS GIVEN THE     Linear

THE LAW WILL BE CONSIDERED TO BE ENERGY INDEPENDENT.  Linear

IF MORE THAN ONE PAIR IS GIVEN IT WILL BE CONSIDERED  Linear

TO BE ENERGY DEPENDENT (NOTE, ENERGY INDEPENDENT      Linear

FORM WILL RUN FASTER THAN THE EQUIVALENT ENERGY
Linear

DEPENDENT FORM). FOR AN ENERGY DEPENDENT ERROR LAW    Linear

ALL ENERGIES MUST BE ASCENDING ENERGY ORDER. FOR      Linear

CONVERGENCE OF THE LINEARIZING ALGORITHM ALL ERRORS   Linear

MUST BE POSITIVE. IF AN ALLOWABLE ERROR IS NOT
Linear

POSITIVE IT WILL BE SET EQUAL TO THE STANDARD OPTION  Linear

(CURRENTLY 0.001, CORRESPONDING TO 0.1 PER-CENT).     Linear

IF THE FIRST ERROR LINE IS BLANK IT WILL TERMINATE    Linear

THE ERROR LAW AND THE ERROR WILL BE TREATED AS
Linear

ENERGY INDEPENDENT, EQUAL TO THE STANDARD OPTION      Linear

(CURRENTLY 0.1 PER-CENT). (SEE EXAMPLE INPUT 4).      Linear

Linear

EXAMPLE INPUT
NO. 1
Linear

-------------------
Linear

RETRIEVE DATA BY
ZA IN ORDER TO FIND ALL URANIUM ISOTOPES AND      Linear

THORIUM 232.
RETRIEVE ALL NEUTRON INTERACTION CROSS SECTIONS
Linear

(MF=3). ALL
ENERGY INTERVALS IN WHICH THE CROSS SECTION IS
Linear

AT LEAST 1 MICRO-BARN
(1.0E-06 BARNS) WILL BE SUBDIVIDED.
Linear

BACKWARD
THINNING WILL BE PERFORMED. FROM 0 TO 100 EV LINEARIZE    Linear

TO WITHIN 0.1
PER-CENT ACCURACY. FROM 100 EV TO 1 KEV VARY
Linear

ACCURACY BETWEEN
0.1 AND 1.0 PER-CENT. ABOVE 1 KEV USE 1
Linear

PER-CENT
ACCURACY.
Linear

Linear

EXPLICITLY
SPECIFY THE STANDARD FILENAMES.
Linear

Linear

IN THIS CASE THE
FOLLOWING 11 INPUT LINES ARE REQUIRED
Linear

Linear

1
0 1.00000- 6
0
Linear

ENDFB.IN
Linear

ENDFB.OUT
Linear

92000
3  0 92999 3999
Linear

90232
3  0     0 3  0    (UPPER LIMIT AUTOMATICALLY
SET TO 90232 3999) Linear

(END OF REQUEST LIST)
Linear

0.00000+ 0 1.00000-03
Linear

1.00000+ 2 1.00000-03
Linear

1.00000+ 3 1.00000-02
Linear

1.00000+ 9 1.00000-02
Linear

(END OF ERROR LAW)
Linear

Linear

EXAMPLE INPUT
NO. 2
Linear

-------------------
Linear

SAME AS THE
ABOVE CASE, EXCEPT LINEARIZE ALL DATA TO WITHIN THE    Linear

STANDARD ACCURACY
(CURRENTLY 0.1 PER-CENT). IN ORDER TO USE THE    Linear

STANDARD
ACCURACY YOU NEED NOT SPECIFY ANY ERROR LAW AT ALL. IN    Linear

THIS CASE
INCLUDE THE HOLLERITH SECTION, MF=1, MT=451, FOR EACH    Linear

MATERIAL.
Linear

Linear

LEAVE THE
DEFINITION OF THE FILENAMES BLANK - THE PROGRAM WILL     Linear

THEN USE
STANDARD FILENAMES.                                       Linear

Linear

IN THIS CASE THE
FOLLOWING 9 INPUT LINES ARE REQUIRED
Linear

Linear

1
0 1.00000- 6
0
Linear

(USE DEFAULT FILENAME = ENDFB.IN)
Linear

(USE DEFAULT FILENAME = ENDFB.OUT)
Linear

92000
1451 92999 1451
Linear

92000
3  0 92999 3999
Linear

90232
1451     0 1451
Linear

90232
3  0     0 3  0    (UPPER LIMIT AUTOMATICALLY
SET TO 90232 3999) Linear

(END OF REQUEST LIST)
Linear

(0.1 PER-CENT ERROR, END OF ERROR LAW)        Linear

Linear

EXAMPLE INPUT
NO. 3
Linear

-------------------
Linear

LINEARIZE ALL MATERIALS ON AN ENDF/B TAPE
TO WITHIN AN ACCURACY
Linear

OF 0.5 PER-CENT
(0.005 AS A FRACTION). IN THIS CASE YOU NEED NOT   Linear

SPECIFY THE MAT,
MF, MT RANGES.
Linear

Linear

READ THE ENDF/B
DATA FROM \ENDFB6\ZA092238 AND WRITE THE ENDF/B    Linear

DATA TO
\ENDFB6\LINEAR\ZA092238.
Linear

Linear

IN THIS CASE THE
FOLLOWING 6 INPUT LINES ARE REQUIRED
Linear

Linear

(MAT,
1.0E-10 BARNS, THIN) Linear

\ENDFB6\ZA092238
Linear

\ENDFB6\LINEAR\ZA092238
Linear

(RETRIEVE ALL DATA, END REQUEST LIST)
Linear

5.00000-03
Linear

(END OF ERROR LAW)
Linear

Linear

NOTE THAT IN
THIS CASE IF THE INPUT HAD SPECIFIED AN EQUIVALENT    Linear

ENERGY DEPENDENT
ERROR LAW BY GIVING A NUMBER OF ENERGY POINTS     Linear

AT EACH OF WHICH
THE ERROR IS 0.5 PER-CENT THE PROGRAM WOULD TAKE  Linear

LONGER TO RUN
(I.E., ONLY USE AN ENERGY DEPENDENT ERROR LAW WHEN   Linear

IT IS
NECESSARY).
Linear

Linear

EXAMPLE INPUT
NO. 4
Linear

-------------------
Linear

IN ORDER TO
LINEARIZE ALL MATERIALS ON AN ENDF/B TAPE TO THE
Linear

STANDARD OPTION OF 0.1
PER-CENT IT IS ADEQUATE TO INPUT A SET      Linear

OF COMPLETELY
BLANK LINES WHICH WILL AUTOMATICALLY INVOKE ALL      Linear

OF THE STANDARD
OPTIONS.
Linear

Linear

LEAVE THE
DEFINITION OF THE FILENAMES BLANK - THE PROGRAM WILL     Linear

THEN USE
STANDARD FILENAMES.
Linear

Linear

IN THIS CASE THE
FOLLOWING THREE INPUT LINES ARE REQUIRED
Linear

Linear

(MAT,
1.0E-10 BARNS, THIN) Linear

(USE DEFAULT FILENAME = ENDFB.IN)
Linear

(USE DEFAULT FILENAME = ENDFB.OUT)
Linear

(RETRIEVE ALL DATA, END REQUEST LIST)
Linear

(0.1 PER-CENT ERROR, END OF ERROR LAW)
Linear

Linear

=======================================================================
Linear

=======================================================================
Merger

Merger

PROGRAM
MERGER
Merger

VERSION 80-1
(JANUARY 1980)
Merger

VERSION 80-2
(DECEMBER 1980)
Merger

VERSION 82-1
(JANUARY 1982)
Merger

VERSION 83-1
(JANUARY 1983)*NEW, MORE COMPATIBLE I/O UNIT NUMBERS. Merger

VERSION 85-1
(AUGUST 1985) *FORTRAN-77/H VERSION
Merger

VERSION 86-1
(JANUARY 1986)*ENDF/B-VI FORMATS
Merger

VERSION 88-1 (JULY
1988)   *OPTION...INTERNALLY
DEFINE ALL I/O
Merger

FILE NAMES (SEE, SUBROUTINES FILIO1    Merger

AND FILIO2 FOR DETAILS).
Merger

*IMPROVED
BASED ON USER COMMENTS.
Merger

VERSION 89-1
(JANUARY 1989)*PSYCHOANALYZED BY PROGRAM FREUD TO     Merger

INSURE PROGRAM WILL NOT DO ANYTHING    Merger

CRAZY.
Merger

*UPDATED TO USE NEW PROGRAM CONVERT     Merger

KEYWORDS.
Merger

*ADDED LIVERMORE
CIVIC COMPILER
Merger

CONVENTIONS.
Merger

VERSION 92-1
(JANUARY 1992)*UPDATED BASED ON USER COMMENTS
Merger

*ADDED FORTRAN SAVE OPTION
Merger

VERSION 92-2
(JULY 1992)   *ALLOW UP TO 99
ENDF/B DATA FILES.
Merger

(TO ALLOW MANAGEMENT OF THE ENTIRE     Merger

ENDF/B SYSTEM).                       Merger

VERSION 94-1
(JANUARY 1994)*VARIABLE ENDF/B DATA FILENAMES
Merger

TO ALLOW ACCESS TO FILE STRUCTURES     Merger

(WARNING - INPUT PARAMETER FORMAT      Merger

HAS BEEN CHANGED)
Merger

*ONLY SPECIFY FILENAMES - NO UNIT
Merger

NUMBERS ON INPUT (WARNING - INPUT      Merger

PARAMETERS FORMAT HAS BEEN CHANGED)    Merger

*CLOSE ALL FILES BEFORE TERMINATING     Merger

(SEE, SUBROUTINE ENDIT)
Merger

*REQUEST
LOG DELETED
Merger

VERSION 96-1
(JANUARY 1996) *COMPLETE RE-WRITE
Merger

*IMPROVED COMPUTER INDEPENDENCE
Merger

*ALL
DOUBLE PRECISION
Merger

*ON SCREEN OUTPUT
Merger

*UNIFORM TREATMENT OF ENDF/B I/O
Merger

*IMPROVED
OUTPUT PRECISION
Merger

VERSION 99-1
(MARCH 1999)   *GENERAL
IMPROVEMENTS BASED ON
Merger

USER FEEDBACK
Merger

VERS. 2000-1
(FEBRUARY 2000)*GENERAL IMPROVEMENTS BASED ON
Merger

USER FEEDBACK
Merger

VERS. 2002-1
(MAY 2002)
*OPTIONAL INPUT PARAMETERS
Merger

VERS. 2004-1
(MARCH 2004)   *ADDED INCLUDE
TO DEFINE COMMON
Merger

*ADDED TEND LINE IF NO DATA RETRIEVED  Merger

VERS. 2007-1
(JAN.  2007)   *CHECKED AGAINST ALL ENDF/B-VII.
Merger

Merger

OWNED,
MAINTAINED AND DISTRIBUTED BY
Merger

------------------------------------
Merger

THE NUCLEAR DATA
SECTION
Merger

INTERNATIONAL
ATOMIC ENERGY AGENCY
Merger

P.O. BOX 100
Merger

A-1400, VIENNA, AUSTRIA
Merger

EUROPE
Merger

Merger

ORIGINALLY
WRITTEN BY
Merger

------------------------------------
Merger

DERMOTT E.
CULLEN
Merger

UNIVERSITY OF CALIFORNIA
Merger

LAWRENCE
LIVERMORE
NATIONAL LABORATORY
Merger

L-159
Merger

P.O. BOX 808
Merger

LIVERMORE, CA
94550
Merger

U.S.A.
Merger

TELEPHONE  925-423-7359
Merger

E. MAIL    [email-masked]
Merger

WEBSITE
HTTP://WWW.LLNL.GOV/CULLEN1
Merger

Merger

AUTHORS
MESSAGE
Merger

---------------
Merger

THE COMMENTS
BELOW SHOULD BE CONSIDERED THE LATEST DOCUMENTATION   Merger

FOR THIS PROGRAM
INCLUDING ALL RECENT IMPROVEMENTS. PLEASE READ    Merger

ALL OF THESE
COMMENTS BEFORE IMPLEMENTATION, PARTICULARLY THE      Merger

COMMENTS
CONCERNING MACHINE DEPENDENT CODING.
Merger

Merger

AT THE PRESENT
TIME WE ARE ATTEMPTING TO DEVELOP A SET OF COMPUTER Merger

INDEPENDENT
PROGRAMS THAT CAN EASILY BE IMPLEMENTED ON ANY ONE     Merger

OF A WIDE
VARIETY OF COMPUTERS. IN ORDER TO ASSIST IN THIS PROJECT Merger

IT WOULD BE
APPECIATED IF YOU WOULD NOTIFY THE AUTHOR OF ANY
Merger

COMPILER
DIAGNOSTICS, OPERATING PROBLEMS OR SUGGESTIONS ON HOW TO  Merger

IMPROVE THIS
PROGRAM. HOPEFULLY, IN THIS WAY FUTURE VERSIONS OF    Merger

THIS PROGRAM
WILL BE COMPLETELY COMPATIBLE FOR USE ON YOUR
Merger

COMPUTER.
Merger

Merger

PURPOSE
Merger

-------
Merger

THIS PROGRAM IS
DESIGNED TO SELECTIVELY RETRIEVE DATA OFF OF FROM  Merger

1 TO 10 ENDF/B
DATA TAPES AND TO MERGE THE SELECTED DATA INTO A    Merger

SINGLE MAT/MF/MT
ORDERED FINAL OUTPUT FILE.
Merger

Merger

IN THE
DISCUSSION THAT FOLLOWS FOR SIMPLICITY THE ENDF/B
Merger

TERMINOLOGY---ENDF/B TAPE---WILL BE USED. IN FACT THE ACTUAL
Merger

MEDIUM USED MAY
BE TAPE, CARD, DISK OR ANY OTHER MEDIUM.
Merger

Merger

ENDF/B
FORMAT
Merger

-------------
Merger

THIS PROGRAM
ONLY USES THE ENDF/B BCD OR CARD IMAGE FORMAT (AS     Merger

OPPOSED TO THE
BINARY FORMAT) AND CAN HANDLE DATA IN ANY VERSION   Merger

OF THE ENDF/B
FORMAT (I.E., ENDF/B-I, II,III, IV OR V FORMAT).     Merger

Merger

THE ONLY
NUMERICAL DATA THAT THIS PROGRAM READS IS THE ZA FROM THE Merger

FIRST CARD OF
EACH SECTION AND THE MAT/MF/MT FROM EACH CARD.
Merger

SEQUENCE NUMBERS
ARE IGNORED ON INPUT AND ALL OTHER FIELDS ARE     Merger

READ AS
HOLLERITH. AS SUCH THIS PROGRAM NEED NOT DISTINGUISH
Merger

BETWEEN
DIFFERENT VERSIONS OF THE ENDF/B FORMAT.
Merger

Merger

IT IS ASSUMED
THAT THE DATA IS CORRECTLY CODED IN THE ENDF/B
Merger

FORMAT AND NO
ERROR CHECKING IS PERFORMED. IN PARTICULAR IT IS     Merger

ASSUMED THAT THE
MAT, MF AND MT ON EACH CARD IS CORRECT. SEQUENCE  Merger

NUMBERS (COLUMNS
76-80) ARE IGNORED ON INPUT, BUT WILL BE
Merger

CORRECTLY OUTPUT
ON ALL CARDS.
Merger

Merger

SECTION SIZE
Merger

------------
Merger

SINCE THIS
PROGRAM ONLY READS THE DATA ONE CARD AT A TIME THERE    Merger

IS NO LIMIT TO
THE SIZE OF ANY GIVEN SECTION, E.G. THE TOTAL
Merger

CROSS SECTION
MAY BE DESCRIBED BY 200,000 DATA POINTS.
Merger

Merger

SELECTION OF
DATA
Merger

-----------------
Merger

THE USER MAY
CHOOSE TO MERGE ALL DATA OR THE USER MAY SPECIFY      Merger

THAT ONLY
CERTAIN DATA SHOULD BE SELECTED. THE DATA TO BE
Merger

SELECTED IS
DEFINED BY SPECIFYING UP TO 100 MAT/MF/MT OR
Merger

ZA/MF/MT RANGES.
EACH RANGE IS DEFINED BY LOWER AND UPPER LIMITS   Merger

OF MAT/MF/MT OR
ZA/MF/MT.
Merger

Merger

REQUEST
LIMITS
Merger

--------------
Merger

IN ORDER TO
SIMPLIFY THE INPUT OF SELECTION REQUESTS THE FOLLOWING Merger

CONVENTIONS HAVE
BEEN INTRODUCED IN ORDER TO DEFINE THE UPPER      Merger

LIMITS OF
REQUESTS IF THEY ARE NOT DEFINED BY INPUT (I.E., IF THEY Merger

ARE ZERO).
Merger

Merger

(1) MAT OR ZA -
IF THE UPPER LIMIT IS ZERO IT IS SET EQUAL TO THE  Merger

LOWER
LIMIT.
Merger

(2) MF OR
MT  - IF THE UPPER LIMIT IS ZERO IT
IS SET EQUAL TO THE  Merger

MAXIMUM POSSIBLE VALUE, 99 OR 999 RESPECTIVELY.    Merger

Merger

WITH THESE
CONVENTIONS AN ENTIRE EVALUATION MAY BE SELECTED BY     Merger

MERELY
SPECIFYING THE LOWER LIMIT OF MAT OR ZA. THE UPPER MAT OR   Merger

ZA LIMIT WILL BE
SET EQUAL TO THE LOWER LIMIT, THE LOWER LIMITS OF Merger

MF/MT WILL BE
0/0 AND THE UPPER LIMITS OF MF/MT WILL BE SET TO     Merger

99/999. THIS
WILL CAUSE ALL SECTIONS OF A SINGLE EVALUATION TO BE  Merger

SELECTED.
Merger

Merger

SATISFYING
SELECTION CRITERIA
Merger

-----------------------------
Merger

IN ORDER FOR A
SECTION TO MEET THE SELECTION CRITERIA SPECIFIED    Merger

BY ONE OF THE
RETRIEVAL REQUESTS, EACH OF THE THREE FIELDS (
Merger

MAT/MF/MT OR
ZA/MF/MT) MUST INDIVIDUALLY SATISFY THE CORRESPONDING Merger

LIMITS OF THE
REQUEST. IT IS NOT SUFFICIENT THAT THE MAT OF A      Merger

SECTION LIE
BETWEEN THE MINIMUM AND MAXIMUM MATS OF A REQUEST. THE Merger

MF AND MT WILL
ALSO BE INDIVIDUALLY COMPARED TO THE MF AND MT      Merger

LIMITS OF THE
REQUEST. FOR EXAMPLE, A SECTION WITH MAT/MF/MT=      Merger

2500/3/2 DOES
NOT SATISFY A REQUEST THAT SPECIFIES A REQUEST USING Merger

THE RANGE
2000/3/1 THROUGH 3000/3/1. THIS REQUEST SPECIFIES ALL    Merger

MATERIALS WITH
MAT BETWEEN 2000 AND 3000, BUT ONLY THOSE SECTIONS  Merger

WITH MF/MT=3/1.
SIMILARLY A REQUEST FOR 2000/3/1 THROUGH 3000/99/  Merger

999 WILL NOT
SELECT ANY SECTIONS WITH MF=1 OR 2, SINCE THE
Merger

REQUEST SPECIFIES ALL
MATERIALS WITH MAT BETWEEN 2000 AND 3000,    Merger

BUT ONLY THOSE
SECTIONS WITH MF= 3, OR MORE.
Merger

Merger

DUPLICATE
SECTIONS
Merger

------------------
Merger

IF TWO OR MORE
SECTIONS WITH THE SAME MAT/MF/MT ARE FOUND EITHER   Merger

ON THE SAME OR DIFFERENT
TAPES, THE SECTION FROM THE TAPE DEFINED
Merger

EARLIEST IN THE
INPUT CARDS WILL BE COPIED TO THE FINAL TAPE AND   Merger

ALL OTHER
SECTIONS WITH THE SAME MAT/MF/MT WILL BE SKIPPED. THE    Merger

OUTPUT REPORT
WILL INDICATE WHICH SECTIONS WERE COPIED FROM WHICH  Merger

TAPES, AS WELL
AS WHICH SECTIONS ARE DUPLICATE AND WERE SKIPPED.   Merger

Merger

REACTION
INDEX
Merger

--------------
Merger

THIS PROGRAM
DOES NOT UPDATE THE REACTION INDEX IN MF=1, MT=451.   Merger

FOR EACH
MATERIAL THE PROGRAM WILL FOLLOW THE CONVENTIONS
Merger

DEFINED ABOVE
AND ONLY COPY ONE SECTION MF=1, MT=451 AND SKIP      Merger

ALL OTHERS (IF
MORE THAN ONE). THIS CONVENTION HAS BEEN ADOPTED    Merger

BECAUSE MOST
USERS DO NOT REQUIRE A CORRECT REACTION INDEX FOR     Merger

THERE
APPLICATIONS AND IT WAS NOT CONSIDERED WORTHWHILE TO INCLUDE Merger

THE OVERHEAD OF
CONSTRUCTING A CORRECT REACTION INDEX IN THIS      Merger

PROGRAM.
HOWEVER, IF YOU REQUIRE A REACTION INDEX FOR YOUR         Merger

APPLICATION
AFTER RUNNING THIS PROGRAM YOU MAY USE PROGRAM
Merger

DICTIN TO CREATE
ONE.
Merger

Merger

RETRIEVAL
STATISTICS
Merger

--------------------
Merger

THERE WILL
ALWAYS BE AN OUTPUT REPORT LISTING INDICATING WHICH     Merger

SECTIONS WHERE
SELECTED, WHICH DUPLICATE SECTIONS WERE SKIPPED,    Merger

WHICH TAPE THE
SECTION WAS ON, WHICH REQUEST (MAT/MF/MT OR
Merger

ZA/MF/MT RANGE)
CAUSED THE SECTION TO BE SELECTED AND HOW MANY     Merger

CARDS WERE IN THE
SECTION. IN ADDITION THE USER MAY OPTIONALLY     Merger

OBTAIN A FILE
CONTAINING THE SAME INFORMATION. THIS FILE MAY BE    Merger

COMBINED WITH
OTHER SIMILAR FILES OUTPUT BY THIS PROGRAM IN ORDER  Merger

TO ACCUMULATE
RETRIEVAL STATISTICS OVER A PERIOD OF TIME. IF
Merger

SPECIFIED THIS
FILE WILL CONTAIN THE FOLLOWING INFORMATION IN      Merger

6I7 FORMAT.
Merger

Merger

(1) ZA
Merger

(2) MAT
Merger

(3) MF
Merger

(4) MT
Merger

(5) NUMBER OF
CARDS IN SECTION
Merger

(6) REQUEST
NUMBER THAT CAUSED SECTION TO BE SELECTED              Merger

Merger

INPUT FILES
Merger

-----------
Merger

UNIT  DESCRIPTION
Merger

----  -----------
Merger

2   INPUT CARDS (BCD -
80 CHARACTERS/RECORD)
Merger

VARY  FROM 1 TO 99 ENDF/B DATA FILES (BCD - 80
CHARACTERS/RECORD)  Merger

Merger

OUTPUT
FILES
Merger

------------
Merger

UNIT  DESCRIPTION
Merger

----  -----------
Merger

3   OUTPUT REPORT
LISTING (BCD - 120 CHARACTERS/RECORD)
Merger

10   MERGED ENDF/B DATA (BCD - 80
CHARACTERS/RECORD)
Merger

Merger

OPTIONAL
STANDARD FILE NAMES (SEE SUBROUTINES FILIO1 AND FILIO2)   Merger

----------------------------------------------------------------   Merger

UNIT  FILE NAME   DESCRIPTION
Merger

----  ----------  -----------                                      Merger

2   MERGER.INP  INPUT PARAMETERS
Merger

3   MERGER.LST  OUTPUT LISTING
Merger

11   ENDFB.OUT   RETRIEVED ENDF/B DATA                            Merger

12   ENDFB.IN1   ENDF/B DATA TO READ...FILENAMES
WILL BE DEFINED  Merger

13   ENDFB.IN2   IN THE ORDER ENDFB.IN1,
ENDFB.IN2,...ENDFB.I99
Merger

14   ENDFB.IN3   CORRESPONDING TO THE FIRST, SECOND,...99-TH      Merger

15   ENDFB.IN4   ENDF/B DATA FILE TO READ.
Merger

16   ENDFB.IN5
Merger

17   ENDFB.IN6
Merger

18   ENDFB.IN7
Merger

.
Merger

.
Merger

110   ENDFB.I99
Merger

Merger

INPUT
CARDS
Merger

-----------
Merger

CARD  COLUMNS  FORMAT  DESCRIPTION
Merger

----  -------  ------  -----------
Merger

1     1-60    A60    FILENAME FOR MERGED
OUTPUT.
Merger

(LEAVE BLANK FOR STANDARD = ENDFB.OUT)     Merger

2
1-66  16A4,A2  MERGED FILE LABEL
Merger

IF
BLANK - LABEL FROM FIRST FILE READ WILL Merger

BE OUTPUT
Merger

67-70    I4     MERGED FILE ENDF/B
NUMBER
Merger

IF ZERO - NUMBER OF FIRST FILE READ WILL   Merger

BE OUTPUT.
Merger

71-72    I2     RETRIEVAL CRITERIA
Merger

= 0 - MAT/MF/MT RANGES
Merger

= 1 - ZA/MF/MT RANGES
Merger

3-N     1-60    A60    FILENAME FOR FILE TO
RETRIEVE DATA FROM
Merger

(LEAVE BLANK FOR STANDARD..ENDFB.IN1,ETC.) Merger

TERMINATE LIST OF FILES WITH A LINE THAT   Merger

SAYS END OR end
Merger

VARY    1- 6    I6     LOWER PRIMARY LIMIT
(MAT OR ZA)            Merger

7- 8    I2     LOWER MF LIMIT
Merger

9-11    I3     LOWER MT LIMIT
Merger

12-17    I6     UPPER PRIMARY LIMIT
(MAT OR ZA)
Merger

18-19    I2     UPPER MF LIMIT
Merger

20-22    I3     UPPER MT LIMIT
Merger

RANGES OF MAT/MF/MT OR ZA/MF/MT TO BE      Merger

RETRIEVED
ARE SPECIFIED BY DEFINING
Merger

ONE RANGE (LOWER AND UPPER LIMITS) PER     Merger

CARD. THE USER MAY SPECIFY 0 TO 100
Merger

RANGES
AND THE LIST OF REQUEST RANGES      Merger

IS TERMINATED BY A BLANK CARD. IF
Merger

THE FIRST CARD IS BLANK (0 REQUESTS)
Merger

ALL
DATA WILL BE RETRIEVED. IF THE UPPER
Merger

PRIMARY CRITERIA (MAT OR ZA) IS LESS THAN  Merger

THE LOWER PRIMARY CRITERIA, THE UPPER      Merger

PRIMARY CRITERIA WILL BE SET EQUAL TO      Merger

THE LOWER PRIMARY CRITERIA. IF THE UPPER   Merger

MF OR MT LIMIT IS ZERO, OR BLANK, IT
Merger

WILL BE SET TO THE MAXIMUM POSSIBLE
Merger

VALUE, I.E. MF=99 OR MT=999 (SEE
Merger

EXAMPLE INPUT).
Merger

Merger

EXAMPLE
INPUT NO. 1
Merger

-------------------
Merger

MERGE
ENDF/B DATA ONTO UNIT 10 FROM UNITS 11, 12, 13 AND 14.      Merger

RETRIEVE
DATA BY MAT NUMBER. RETRIEVE MATS 1103, 1106, ALL MATS   Merger

BETWEEN
1204 AND 1215, MF=1, 3, 4 AND 5 OF MAT 1219 AND MF=3,     Merger

MT=1 OF
MAT 1304. USE STANDARD FILENAMES.
Merger

Merger

THE
FOLLOWING 13 INPUT CARDS ARE REQUIRED.
Merger

Merger

ENDFB.OUT
Merger

EXAMPLE FILE
LABEL FOR MERGER
0 0 Merger

ENDFB.IN1
Merger

ENDFB.IN2
Merger

ENDFB.IN3
Merger

ENDFB.IN4
Merger

END
Merger

1103
4317  (UPPER LIMIT SET TO
1103/99/999) Merger

1106
4317  (UPPER LIMIT SET TO
1106/99/999) Merger

1204
1215           4317  (UPPER LIMIT SET TO 1215/99/999)
Merger

1219
1     1219 1
4317  (UPPER LIMIT SET TO
1219/ 1/999) Merger

1219
3     1219 5
4317  (UPPER LIMIT SET TO
1219/ 5/999) Merger

1304
3  1  1304 3  1      4317  (UPPER LIMIT COMPLETELY DEFINED)
Merger

(BLANK CARD TERMINATES REQUESTS) Merger

Merger

EXAMPLE
INPUT NO. 2
Merger

-------------------
Merger

THE SAME
AS EXAMPLE 1, EXCEPT SPECIFY FILENAMES
Merger

Merger

\ENDFB6\MERGED.LIB
Merger

EXAMPLE FILE
LABEL FOR MERGER
0 0 Merger

ENDFB6.PART1
Merger

ENDFB6.PART2
Merger

ENDFB6.PART3
Merger

ENDFB6.PART4
Merger

END
Merger

1103
4317  (UPPER LIMIT SET TO
1103/99/999) Merger

1106
4317  (UPPER LIMIT SET TO
1106/99/999) Merger

1204       1215
4317  (UPPER LIMIT SET TO
1215/99/999) Merger

1219
1     1219 1
4317  (UPPER LIMIT SET TO
1219/ 1/999) Merger

1219
3     1219 5
4317  (UPPER LIMIT SET TO
1219/ 5/999) Merger

1304
3  1  1304 3  1      4317  (UPPER LIMIT COMPLETELY DEFINED)
Merger

(BLANK CARD TERMINATES REQUESTS) Merger

Merger

=======================================================================
Merger

=======================================================================
Mixer

Mixer

PROGRAM
MIXER
Mixer

Mixer

VERSION 76-1
(NOVEMBER 1976)
Mixer

VERSION 81-1
(APRIL 1981)  *IBM VERSION                            Mixer

VERSION 82-1
(AUGUST 1982) *COMPUTER INDEPENDENT VERSION
Mixer

VERSION 84-1
(JUNE 1984)   *SPECIAL I/O
ROUTINES TO GUARANTEE      Mixer

ACCURACY OF ENERGY.                    Mixer

*DOUBLE PRECISION TREATMENT OF ENERGY   Mixer

(REQUIRED FOR NARROW RESONANCES).      Mixer

VERSION 86-1
(JANUARY 1986)*FORTRAN-77/H VERSION
Mixer

VERSION 88-1
(JULY 1988)
*OPTION...INTERNALLY DEFINE ALL I/O     Mixer

FILE NAMES (SEE, SUBROUTINE FILIO1     Mixer

AND FILIO2 FOR DETAILS).
Mixer

*IMPROVED BASED ON USER COMMENTS.       Mixer

VERSION 89-1
(JANUARY 1989)*PSYCHOANALYZED BY PROGRAM FREUD TO     Mixer

INSURE PROGRAM WILL NOT DO ANYTHING    Mixer

CRAZY.
Mixer

*UPDATED TO USE NEW PROGRAM CONVERT     Mixer

KEYWORDS.
Mixer

*ADDED
LIVERMORE CIVIC
COMPILER
Mixer

CONVENTIONS.
Mixer

VERSION 92-1
(JANUARY 1992)*UPDATED BASED ON USER COMMENTS
Mixer

*ADDED
PHOTON CROSS SECTIONS
Mixer

*ADDED FORTRAN SAVE OPTION
Mixer

*OUTPUT IN ENDF/B-VI FORMAT
Mixer

*COMPLETELY CONSISTENT I/O ROUTINES -   Mixer

TO MINIMIZE COMPUTER DEPENDENCE.       Mixer

*NOTE, CHANGE IN INPUT PARAMETER
Mixer

FORMAT.                                Mixer

VERSION 94-1
(JANUARY 1994)*VARIABLE ENDF/B DATA FILENAMES
Mixer

TO ALLOW ACCESS TO FILE STRUCTURES     Mixer

(WARNING - INPUT PARAMETER FORMAT      Mixer

HAS BEEN CHANGED)
Mixer

*CLOSE ALL FILES BEFORE TERMINATING     Mixer

(SEE, SUBROUTINE ENDIT)
Mixer

*INCREASED INCORE PAGE SIZE FROM
Mixer

1002 TO 4008.
Mixer

VERSION 96-1
(JANUARY 1996) *COMPLETE RE-WRITE
Mixer

*IMPROVED COMPUTER INDEPENDENCE
Mixer

*ALL DOUBLE PRECISION
Mixer

*ON SCREEN OUTPUT
Mixer

*UNIFORM
TREATMENT OF ENDF/B I/O       Mixer

*IMPROVED OUTPUT PRECISION
Mixer

*DEFINED SCRATCH FILE NAMES
Mixer

*INCREASED
INCORE PAGE SIZE FROM       Mixer

4008 TO 12000.
Mixer

VERSION 99-1
(MARCH 1999)   *CORRECTED
CHARACTER TO FLOATING       Mixer

POINT
READ FOR MORE DIGITS
Mixer

*UPDATED TEST FOR ENDF/B FORMAT
Mixer

VERSION BASED ON RECENT FORMAT CHANGE Mixer

*GENERAL IMPROVEMENTS BASED ON
Mixer

USER FEEDBACK
Mixer

VERSION 99-2
(JUNE 1999)    *ASSUME
ENDF/B-VI, NOT V, IF MISSING
Mixer

MF=1, MT-451.
Mixer

VERS. 2000-1
(FEBRUARY 2000)*GENERAL IMPROVEMENTS BASED ON
Mixer

USER FEEDBACK
Mixer

VERS. 2002-1
(MAY 2002)
*OPTIONAL INPUT PARAMETERS
Mixer

VERS. 2004-1
(MARCH 2004)   *ADDED INCLUDE
FOR COMMON
Mixer

*INCREASED INCORE PAGE SIZE FROM       Mixer

12000 TO 60000.
Mixer

VERS. 2005-1
(OCT. 2005)    *CORRECTED
MERGE ERROR
Mixer

VERS. 2007-1
(JAN. 2007)    *CHECKED
AGAINST ALL ENDF/B-VII
Mixer

*INCREASED INCORE PAGE SIZE FROM       Mixer

60,000 TO 240,000.
Mixer

Mixer

OWNED,
MAINTAINED AND DISTRIBUTED BY
Mixer

------------------------------------
Mixer

THE NUCLEAR DATA
SECTION
Mixer

INTERNATIONAL
ATOMIC ENERGY AGENCY
Mixer

P.O. BOX 100
Mixer

A-1400, VIENNA, AUSTRIA
Mixer

EUROPE
Mixer

Mixer

ORIGINALLY
WRITTEN BY
Mixer

------------------------------------
Mixer

DERMOTT E.
CULLEN
Mixer

UNIVERSITY OF CALIFORNIA
Mixer

LAWRENCE
LIVERMORE
NATIONAL LABORATORY
Mixer

L-159
Mixer

P.O. BOX 808
Mixer

LIVERMORE, CA
94550
Mixer

U.S.A.
Mixer

TELEPHONE  925-423-7359
Mixer

E. MAIL    [email-masked]
Mixer

WEBSITE
HTTP://WWW.LLNL.GOV/CULLEN1
Mixer

Mixer

PURPOSE
Mixer

-------
Mixer

THIS PROGRAM IS
DESIGNED TO CALCULATE THE ENERGY DEPENDENT CROSS   Mixer

SECTION FOR A
COMPOSITE MIXTURE OF UP TO 10 DIFFERENT MATERIALS.   Mixer

Mixer

THE PRESENT VERSION WILL ONLY
CALCULATE THE CROSS SECTION FOR ONE
Mixer

FINAL REACTION
(ENDF/B SECTION), E.G. TOTAL CROSS SECTION, BUT NOT Mixer

ANY OTHER
REACTION.
Mixer

Mixer

NOTE, THIS
PROGRAM WILL NOT COMBINE ALL REACTIONS FOR A MIXTURE    Mixer

OF MATERIALS
DURING A SINGLE RUN - ONLY ONE REACTION WILL BE       Mixer

CREATED PER RUN.
Mixer

Mixer

EVALUATED DATA
FORMAT
Mixer

---------------------                                              Mixer

THE CROSS
SECTIONS ARE READ FROM THE ENDF/B FORMAT AND THE
Mixer

COMPOSITE CROSS
SECTION IS CONVERTED TO AN EQUIVALENT BARNS/ATOM   Mixer

FORM AND OUTPUT
IN THE ENDF/B FORMAT WITH AN EQUIVALENT ATOMIC     Mixer

WEIGHT. THE USER
MUST SPECIFY THE COMPOSITION BY GIVING THE ZA,    Mixer

MT AND GRAMS/CC
OF EACH CONSTITUENT. IN ADDITION THE USER MUST     Mixer

IDENTIFY THE
COMPOSITE CROSS SECTION BY SPECIFYING THE ZA, MAT     Mixer

AND MT TO BE
USED IN THE ENDF/B FORMATTED OUTPUT.
Mixer

Mixer

SINCE ONLY THE
CROSS SECTIONS IN FILE 3 AND 23 ARE USED, AND THE   Mixer

FORMAT FOR FILE
3/23 IS THE SAME IN ALL VERSIONS ON ENDF/B, THIS   Mixer

PROGRAM MAY BE
USED WITH ANY VERSION OF ENDF/B DATA (I.E.,
Mixer

ENDF/B-I, II,
III, IV, V OR VI). DURING A SINGLE RUN IT MAY EVEN   Mixer

BE USED TO READ
AND COMBINE EVALUATIONS WHICH ARE IN DIFFERENT     Mixer

VERSIONS OF THE
ENDF/B FORMAT.
Mixer

Mixer

ENDF/B FORMATTED
OUTPUT WILL BE IN THE ENDF/B-VI FORMAT REGARDLESS Mixer

OF THE FORMAT OF
THE INPUT ENDF/B DATA. THIS WILL ONLY EFFECT THE  Mixer

HOLLERITH
SECTION (MF=1, MT=451). THE FORMAT OF CROSS SECTIONS     Mixer

(MF=3) IS THE
SAME IN ALL VERSION OF THE ENDF/B FORMAT.
Mixer

Mixer

IN ORDER TO
GUARANTEE PROPER OPERATION OF THIS PROGRAM THE DATA    Mixer

MUST BE PROPERLY
CODED IN THE ENDF/B FORMAT. NO ERROR CHECKING IS  Mixer

PERFORMED. IT IS
PARTICULARLY IMPORTANT THAT THE FOLLOWING DATA    Mixer

BE CORRECT
Mixer

Mixer

(1) ZA, MF, MT -
MUST BE CORRECT IN ORDER TO ALLOW PROGRAM TO      Mixer

SELECT THE APPROPRIATE SECTIONS TO BE COMBINED.
Mixer

(2) AWRE -
ATOMIC WEIGHT RATIO MUST BE CORRECT TO ALLOW PROGRAM    Mixer

TO CONVERT THE USER SPECIFIED GRAMS/CC INTO ATOMS/CC FOR       Mixer

PROPER ATOM RATIO MIXING.
Mixer

(3) (ENERGIES,
CROSS SECTIONS) - MUST BE CORRECT, LINEARLY
Mixer

========
Mixer

INTERPOLABLE, IN ASCENDING ENERGY ORDER OF (E, BARNS).
Mixer

============
Mixer

Mixer

TO CONVERT ENDF/B FORMATTED DATA TO THE REQUIRED INPUT FORM    Mixer

THE FOLLOWING PROGRAMS MAY BE USED,
Mixer

LINEAR - CONVERT TABULATED CROSS SECTIONS TO LINEARLY
Mixer

INTERPOLABLE FORM.
Mixer

RECENT - RECONSTRUCT RESONANCE CONTRIBUTION, ADD TO BACKGROUND
Mixer

CROSS SECTION AND OUTPUT THE COMBINATION IN LINEARLY  Mixer

INTERPOLABLE FORM.
Mixer

SIGMA1 - DOPPLER BROADEN CROSS SECTIONS TO ANY TEMPERATURE AND
Mixer

OUTPUT
THE RESULT IN LINEARLY INTERPOLABLE FORM.      Mixer

Mixer

DOCUMENTATION
Mixer

-------------
Mixer

THE FACT THAT
THIS PROGRAM HAS COMBINED THE DATA IS DOCUMENTED     Mixer

IN THE OUTPUT
ENDF/B FORMAT IN THE HOLLERITH SECTION BY FIRST      Mixer

IDENTIFYING THE
VERSION OF THIS PROGRAM THAT WAS USED, IN THE FORM Mixer

Mixer

********************( PROGRAM MIXER 2007-1) **********************
Mixer

Mixer

THIS IS FOLLOWED
BY THE TWO LINE IDENTIFICATION INPUT BY THE USER. Mixer

THIS IS FOLLOWED
BY COMPOSITION INPUT BY THE USER.
Mixer

Mixer

NEUTRON OR
PHOTON DATA
Mixer

----------------------
Mixer

THIS PROGRAM
WILL ALLOW YOU TO PROCESS EITHER NEUTRON OR PHOTON    Mixer

CROSS SECTIONS -
BUT YOU CANNOT MIX THE TWO TYPES TOGETHER. BY     Mixer

INPUT YOU CAN
SPECIFY THE OUTPUT MF = 3 (NEUTRONS) OR 23 (PHOTONS) Mixer

WHATEVER TYPE
YOU SPECIFIED FOR OUTPUT IS THE ONLY TYPE OF DATA    Mixer

WHICH WILL BE
PROCESSED BY THIS PROGRAM.
Mixer

Mixer

DEFINING THE
COMPOSITION
Mixer

------------------------
Mixer

THE USER MAY
SPECIFY UP TO 10 DIFFERENT SECTIONS OF DATA TO BE     Mixer

COMBINED, EACH
SECTION IDENTIFIED BY ZA AND MT NUMBER. THE
Mixer

AMOUNT OF EACH
MATERIAL IS SPECIFIED BY DEFINING THE NUMBER OF     Mixer

GRAMS/CC OF EACH
MATERIAL IN THE COMPOSITE MIXTURE. THIS CAN BE    Mixer

DERIVED FROM THE
VOLUME FRACTION SIMPLY BY MULTIPLYING THE STP     Mixer

DENSITY OF EACH
MATERIAL BY ITS VOLUME FRACTION. NOTE, DO NOT      Mixer

INPUT ATOM
FRACTIONS.
Mixer

Mixer

THE LIST OF
SECTIONS TO BE COMBINED MAY BE SPECIFIED IN ANY
Mixer

ORDER, I.E. THEY
NEED NOT BE IN ZA ORDER OR THE ORDER THAT THE     Mixer

EVALUATED DATA
APPEARS ON THE ENDF/B FORMATTED TAPE.
Mixer

Mixer

IF ANY REQUESTED
SECTION OF DATA IS NOT FOUND ON THE ORIGINAL      Mixer

ENDF/B FORMATTED
FILE, THE PROGRAM WILL PRINT A LIST OF THE
Mixer

MISSING SECTIONS
AND TERMINATE. IF ALL REQUESTED SECTIONS ARE      Mixer

FOUND THE
PROGRAM WILL PRODUCE A COMPOSITE SECTION USING THE       Mixer

UNION OF ALL ENERGIES FOUND IN ANY SECTION. THE COMPOSITE
SECTION  Mixer

WILL NOT BE
THINNED.
Mixer

Mixer

PRIOR TO LATER
USE IN ANY APPLICATION THE NUMBER OF ENERGY POINTS  Mixer

IN THE COMPOSITE
CROSS SECTION MAY BE MINIMIZED BY USING PROGRAM   Mixer

LINEAR,
UCRL-50400, VOL. 17, PART B TO THIN THE DATA.
Mixer

Mixer

ONLY LINEARLY
INTERPOLABLE DATA
Mixer

-------------------------------
Mixer

THE CROSS
SECTIONS TO BE COMBINED MUST BE IN LINEARLY INTERPOLABLE Mixer

TABULATED FORM (I. E., FILE 3 OR 23, INTERPOLATION LAW 2).
Mixer

Mixer

TO CONVERT
TABULATED CROSS SECTIONS TO LINEARLY INTERPOLABLE FORM  Mixer

SEE, PROGRAM
LINEAR, UCRL-50400, VOL. 17, PART A.
Mixer

Mixer

TO CONVERT
RESONANCE PARAMETERS TO LINEARLY INTERPOLABLE FORM SEE, Mixer

PROGRAM RECENT,
UCRL-50400, VOL. 17, PART C.
Mixer

Mixer

TO DOPPLER
BROADEN LINEARLY INTERPOLABLE DATA TO ANY TEMPERATURE   Mixer

SEE PROGRAM
SIGMA1, UCRL-50400, VOL. 17, PART B.
Mixer

Mixer

PAGING
SYSTEM
Mixer

-------------
Mixer

THERE IS NO
LIMIT TO THE THE NUMBER OF DATA POINTS IN EACH OF THE  Mixer

SECTIONS TO BE
COMBINED, NOR IS THERE A LIMIT TO THE NUMBER OF     Mixer

DATA POINTS IN
THE COMPOSITE MIXTURE CROSS SECTION.
Mixer

Mixer

ALL REQUIRED
SECTIONS OF DATA ARE READ FROM THE ORIGINAL ENDF/B    Mixer

FORMATTED FILE.
ANY SECTION OF 60000 OR FEWER POINTS WILL BE       Mixer

TOTALLY CORE
RESIDENT. LARGER SECTIONS ARE LOADED INTO A PAGING    Mixer

SYSTEM USING A
SCRATCH FILE WITH ONLY 60000 POINTS PER SECTION     Mixer

CORE RESIDENT AT
ANY ONE TIME. SIMILARLY THE COMPOSITE SECTION     Mixer

WILL BE TOTALLY
CORE RESIDENT IF IT CONTAINS 60000 OR FEWER POINTS Mixer

AND LARGER
COMPOSITE SECTIONS WILL BE LOADED INTO A PAGING
Mixer

SYSTEM WHERE
ONLY 60000 POINTS ARE CORE RESIDENT AT ANY TIME. SINC Mixer

A PAGING SYSTEM
MAY BE USED BY ANY SECTION OF DATA THERE IS NO     Mixer

LIMIT TO THE SIZE OF
EITHER THE ORIGINAL SECTIONS, NOR TO THE      Mixer

COMPOSITE
SECTION, E.G. A SECTION MAY CONTAIN 100,000 ENERGIES     Mixer

AND CROSS
SECTIONS TO DESCRIBE A GIVEN REACTION.
Mixer

Mixer

PAGE SIZE
Mixer

---------
Mixer

THE PAGE SIZE USED
IN THIS PROGRAM IS DEFINED BY THE PARAMETER     Mixer

NPAGE AND THE
DIMENSIONS OF THE ARRAYS XTAB AND YTAB. IN ORDER     Mixer

TO ADAPT THIS
PROGRAM FOR USE ON ANY COMPUTER THE PAGE SIZE MAY    Mixer

BE INCREASED OR
DECREASED BUT THE FOLLOWING RULES MUST BE FOLLOWED Mixer

====
Mixer

Mixer

(1) NPAGE - MUST
BE A MULTIPLE OF 3 IN ORDER TO ALLOW THE PROGRAM  Mixer

TO READ FULL CARDS OF ENDF/B DATA (3 POINTS PER LINE). FAILURE
Mixer

TO FOLLOW THIS RULE CAN LEAD TO LOSS OF DATA AND/OR PROGRAM    Mixer

ERRORS DURING EXECUTION.
Mixer

(3) YTAB  - THE DIMENSION OF YTAB MUST BE
(NPAGE,11).
Mixer

(4) XTAB  - THE DIMENSION OF XTAB MUST BE
(NPAGE,11).
Mixer

Mixer

DOPPLER
BROADENING
Mixer

------------------
Mixer

THE COMPOSITE
CROSS SECTION OUTPUT FROM THIS PROGRAM SHOULD NOT    Mixer

BE DOPPLER
BROADENED USING PROGRAM SIGMA1, OR THE EQUIVALENT. THE  Mixer

ATOMIC WEIGHT
USED TO IDENTIFY THE COMPOSITE MIXTURE IS BASED ON   Mixer

THE ATOM
FRACTION OF EACH CONSTITUENT AND CANNOT BE USED TO
Mixer

CHARACTERIZE THE
BROADENING OF ANY GIVEN RESONANCE IN THE MIXTURE  Mixer

DUE TO THE
CONTRIBUTION OF ONE CONSTITUENT. IN ORDER TO CONSIDER   Mixer

DOPPLER
BROADENING FIRST USE PROGRAM SIGMA1 TO BROADEN THE CROSS   Mixer

SECTION FOR EACH
OF THE CONSTITUENTS AND THEN COMBINE THE
Mixer

BROADENED DATA
USING PROGRAM MIXER.
Mixer

Mixer

EXAMPLE USE                                                        Mixer

-----------
Mixer

THE OUTPUT FROM
THIS PROGRAM HAS BEEN FOUND TO BE EXTREMELY
Mixer

USEFUL IN THE
FOLLOWING APPLICATIONS...
Mixer

Mixer

(1) CALCULATE A
COMPOSITE TOTAL CROSS SECTON FOR LATER USE AS      Mixer

A WEIGHTING FUNCTION IN SELF-SHIELDING THE CROSS SECTIONS      Mixer

OF EACH CONSTITUENT OF THE MIXTURE SEPARATELY.
Mixer

Mixer

PROGRAM GROUPIE CAN USE THE CALCULATED COMPOSITE TOTAL CROSS   Mixer

SECTION AS THE TOTAL CROSS SECTION FOR EACH CONSTITUENT OF     Mixer

THE MIXTURE IN ORDER TO CALCULATE
SELF-SHIELDED CROSS SECTION Mixer

FOR EACH CONSTITUENT OF THE MIXTURE.
Mixer

Mixer

(2) CALCULATE
COMPOSITE TOTAL AND FISSION CROSS SECTIONS IN
Mixer

ORDER TO CALCULATE THE TRANSMISSION AND SELF-INDICATION        Mixer

THROUGH COMPOSITE MATERIALS. GENERALLY IN THIS CASE THE
Mixer

TOTAL CROSS SECTION WILL BE CALCULATED FOR THE COMPOSITION     Mixer

OF THE SAMPLE AND THE FISSION CROSS SECTION WILL BE
Mixer

CALCULATED FOR THE COMPOSITION OF THE FISSION CHAMBER
Mixer

(WHICH GENERALLY WILL HAVE A DIFFERENT COMPOSITION THAN THE    Mixer

SAMPLE).
Mixer

Mixer

PROGRAM VIRGIN CAN USE THE OUTPUT FROM THIS PROGRAM TO
Mixer

PERFORM TRANSMISSION AND SELF-INDICATION CALCULATIONS.
Mixer

PROGRAM VIRGIN WILL ANALYTICALLY CALCULATE THE UNCOLLIDED      Mixer

(I.E. VIRGIN) FLUX TRANSMITTED AND REACTION RATE DUE TO ANY    Mixer

TABULATED LINEARLY INTERPOLABLE INCIDENT SPECTRUM. RESULTS     Mixer

WILL BE PRESENTLY FOR UP TO 10 DIFFERENT SAMPLE THICKNESSES    Mixer

AND BINNED INTO ENERGY GROUPS IN ORDER TO SIMULATE AN
Mixer

EXPERIMENTAL MEASUREMENT.
Mixer

Mixer

(3) THE OUTPUT
FROM THIS PROGRAM IS VERY USEFUL TO PLOT IN ORDER   Mixer

TO SEE THE IMPORTANCE OF SPECIFIC CROSS SECTION FEATURES IN    Mixer

THE COMPOSITE CROSS SECTION.
Mixer

Mixer

PROGRAM COMPLOT CAN BE USED TO PLOT THE OUTPUT FROM THIS       Mixer

PROGRAM AND IF REQUIRED EXAMINE ANY PARTICULAR ENERGY RANGE    Mixer

IN DETAIL. IN ORDER TO DO THIS THE (ZA, MT) EQUIVALENCE OPTION
Mixer

OF PROGRAM COMPLOT SHOULD BE USED. TO COMPARE ANY CONSTITUENT  Mixer

CROSS SECTION TO THE COMPOSITE CROSS SECTION THE INPUT TO      Mixer

COMPLOT SHOULD EQUATE THE (ZA,MT) OF THE COMPOSITE TO THE      Mixer

(ZA,MT) OF ONE CONSTITUENT AND THE MULTIPLIER INPUT TO
Mixer

COMPLOT SHOULD BE THE ATOM FRACTION FOR THE CONSTITUENT (THE   Mixer

ATOM FRACTIONS ARE DEFINED IN THE OUTPUT LISTING FROM PROGRAM  Mixer

MIXER).
Mixer

Mixer

INPUT FILES
Mixer

-----------
Mixer

UNIT  DESCRIPTION
Mixer

----  -----------
Mixer

2   INPUT CARDS (BCD -
80 CHARACTERS/RECORD)
Mixer

10   ORIGINAL EVALUATED DATA IN ENDF/B
FORMAT
Mixer

(BCD - 80 CHARACTERS/RECORD)
Mixer

Mixer

OUTPUT
FILES
Mixer

------------
Mixer

UNIT  DESCRIPTION
Mixer

----  -----------
Mixer

3   OUTPUT LISTING (BCD
- 120 CHARACTERS/RECORD)
Mixer

11   COMPOSITE EVALUATED DATA IN ENDF/B
FORMAT
Mixer

(BCD - 80 CHARACTERS/RECORD)
Mixer

Mixer

SCRATCH
FILES
Mixer

-------------
Mixer

UNIT  DESCRIPTION
Mixer

----  -----------
Mixer

12   SCRATCH FILE FOR EACH OF THE 10
SECTIONS WHICH
Mixer

13   WILL BE ADDED TOGETHER TO DEFINE
THE FINAL
Mixer

.   SECTION (BINARY -
60000 AND 480000 WORDS/RECORD)
Mixer

.
.
Mixer

.
.
Mixer

20 .
Mixer

21 .
Mixer

22   SCRATCH FILE FOR COMBINED
SECTION.
Mixer

(BINARY - 2004 WORDS/RECORD)
Mixer

Mixer

STANDARD FILE
NAMES (SEE SUBROUTINES FILIO1 AND FILIO2)
Mixer

----------------------------------------------------------------   Mixer

UNIT  FILE NAME
Mixer

----  ----------
Mixer

2   MIXER.INP
Mixer

3   MIXER.LST
Mixer

10   ENDFB.IN
Mixer

11   ENDFB.OUT
Mixer

12-22  (SCRATCH)
Mixer

Mixer

INPUT CARDS
Mixer

-----------
Mixer

LINE  COLS.  FORMAT  NAME    DESCRIPTION
Mixer

----  -----  ------  ------- ----------
Mixer

1-2   1-66 16A4,A2  TITLE   TWO LINE TITLE DESCRIBING
PROBLEM
Mixer

(THIS TITLE IS USED TO IDENTIFY THE   Mixer

OUTPUT LISTING AND IS ALSO WRITTEN    Mixer

IN MF=1, MT=451 (HOLLERITH SECTION)   Mixer

OF THE ENDF/B FORMATTED OUTPUT TO     Mixer

IDENTIFY THE COMPOSITE MIXTURE).      Mixer

3   1-60
ENDF/B INPUT DATA FILENAME
Mixer

(STANDARD OPTION = ENDFB.IN)
Mixer

4   1-60
ENDF/B OUTPUT DATA FILENAME
Mixer

(STANDARD
OPTION = ENDFB.OUT)
Mixer

5   1-11    I11   IZAOUT  ZA IDENTIFICATION FOR COMBINATION     Mixer

5  12-17    I6    MATOUT  MAT IDENTIFICATION FOR COMBINATION    Mixer

5  18-19    I2    MFOUT   MF IDENTIFICATION FOR
COMBINATION
Mixer

5  20-22    I3    MTOUT   MT IDENTIFICATION FOR
COMBINATION
Mixer

6-N   1-11    I11   IZAGET  ZA (1000*Z+A) OF MATERIAL
Mixer

6-N  12-22    I11   MTGET   MT OF REACTION
Mixer

6-N  23-33  E11.4   DENSE   DENSITY OF MATERIAL
(GRAMS/CC)
Mixer

Mixer

THE SIXTH LINE
IS REPEATED FOR EACH SECTION (FROM 2 TO 10).
Mixer

SINCE THE ENDF/B
FORMATTED OUTPUT IS IN BARNS/ATOM FORM A MINIMUM  Mixer

OF TWO SECTIONS
MUST BE COMBINED (I.E., IF ONLY ONE SECTION IS     Mixer

SPECIFIED THE
OUTPUT WOULD BE IDENTICAL TO THE INPUT AND AS SUCH   Mixer

THE PROGRAM WILL
CONSIDER THIS TO BE AN ERROR AND NOT PERFORM THE  Mixer

CALCULATION).
THE LIST OF SECTIONS IS TERMINATED BY A BLANK LINE.  Mixer

Mixer

THE LIST OF
SECTIONS TO BE COMBINED MAY BE SPECIFIED IN ANY
Mixer

ORDER, I.E. THEY
NEED NOT BE IN ZA ORDER OR THE ORDER THAT THE     Mixer

EVALUATED DATA
APPEARS ON THE ENDF/B FORMATTED TAPE.
Mixer

Mixer

EXAMPLE INPUT
NO. 1
Mixer

-------------------
Mixer

CREATE THE TOTAL
CROSS SECTION (MT=1) FOR STAINLESS STEEL AND      Mixer

IDENTIFY THE
COMBINED MATERIAL WITH ZA=26800 AND MAT=4000,
Mixer

THE COMPOSITION
BY VOLUME OF THE STEEL WILL BE...
Mixer

Mixer

THE DATA FROM
\ENDFB6\K300\LIBRARY.DAT AND WRITE DATA TO
Mixer

\MIXER\STEEL.DAT
Mixer

Mixer

IRON      - 74.8
PER-CENT
Mixer

CHROMIUM  - 16.0
Mixer

NICKEL    -  6.0                                                   Mixer

MANGANESE -  2.0
Mixer

SILICON   -  1.0
Mixer

CARBON    -  0.2
Mixer

Mixer

THE INPUT MUST
SPECIFY THE COMPOSITION BY GRAMS/CC. THIS IS
Mixer

DEFINED AS THE
PRODUCT OF THE STANDARD DENSITY (GRAMS/CC)
Mixer

TIMES THE VOLUME
FRACTION. NOTE, DO NOT USE ATOM FRACTIONS.
Mixer

FOR THIS EXAMPLE
THE FOLLOWING 12 INPUT CARDS ARE REQUIRED....     Mixer

Mixer

STAINLESS STEEL.
COMPOSITION BY PER-CENT VOLUME IS 74.8-IRON,      Mixer

16-CHROME,
6-NICKEL, 2-MANGANESE, 1-SILICON, 0.2-CARBON
Mixer

\ENDFB6\K300\LIBRARY.DAT
Mixer

\MIXER\STEEL.DAT
Mixer

26800  4000 3  1
Mixer

26000
1 5.88676    (NOTE,
GRAMS/CC INPUT FOR EACH
Mixer

24000
1 1.150448
CONSTITUENT, E.G. FOR IRON THE   Mixer

28000
1 0.533928    STP
DENSITY IS 7.87 GRAMS/CC.
Mixer

25055
1 0.1486
THE INPUT VALUE OF 5.88676 IS    Mixer

14000
1 0.0233
0.748 X 7.87,I.E.
VOLUME
Mixer

6012
1 0.0044958   FRACTION
TIMES STP DENSITY).
Mixer

(BLANK LINE TERMINATES INPUT LIST) Mixer

Mixer

EXAMPLE INPUT
NO. 2
Mixer

-------------------
Mixer

THE SAME EXAMPLE
AS THE ABOVE PROBLEM, ONLY USE THE STANDARD       Mixer

ENDF/B DATA
FILENAMES - ENDFB.IN AND ENDFB.OUT (THIS CAN BE
Mixer

DONE BY LEAVING
THE THIRD AND FOURTH INPUT LINES BLANK).
Mixer

FOR THIS EXAMPLE
THE FOLLOWING 12 INPUT CARDS ARE REQUIRED....     Mixer

Mixer

STAINLESS STEEL.
COMPOSITION BY PER-CENT VOLUME IS 74.8-IRON,      Mixer

16-CHROME,
6-NICKEL, 2-MANGANESE, 1-SILICON, 0.2-CARBON
Mixer

(NOTE - THIS
LINE IS REALLY BLANK)
Mixer

(NOTE - THIS
LINE IS REALLY BLANK)
Mixer

26800  4000 3  1
Mixer

26000
1 5.88676    (NOTE,
GRAMS/CC INPUT FOR EACH
Mixer

24000
1 1.150448
CONSTITUENT, E.G. FOR IRON THE   Mixer

28000
1 0.533928    STP
DENSITY IS 7.87 GRAMS/CC.
Mixer

25055
1 0.1486
THE INPUT VALUE OF 5.88676 IS    Mixer

14000
1 0.0233
0.748 X 7.87,I.E.
VOLUME
Mixer

6012
1 0.0044958   FRACTION
TIMES STP DENSITY).
Mixer

(BLANK LINE TERMINATES INPUT LIST) Mixer

Mixer

=======================================================================
Mixer

=======================================================================
Recent

Recent

PROGRAM
RECENT
Recent

VERSION 79-1 (OCTOBER
1979)  CDC-7600
Recent

VERSION 80-1
(MAY 1980)
IBM, CDC AND CRAY VERSION
Recent

VERSION 80-2
(DECEMBER 1980) IMPROVED TREATMENT OF UNRESOLVED      Recent

REGION TO COMPUTE
ALL REACTIONS AT
Recent

THE SAME TIME.
Recent

VERSION 81-1
(MARCH 1981)  IMPROVED BASED ON USER
COMMENTS.        Recent

VERSION 81-2
(AUGUST 1981) ADDED MONITOR MODE. ADDED SPEED OPTION  Recent

TO BYPASS BACKWARDS THINNING IF FILE 3  Recent

ALLOWABLE ERROR = 0.0 (NOTE THIS OPTION Recent

WILL RESULT IN ALL TABULATED POINTS     Recent

FROM THE EVALUATION BEING KEPT IN THE   Recent

OUTPUT FROM THIS PROGRAM).
Recent

VERSION 82-1
(JANUARY 1982) IMPROVED COMPUTER COMPATIBILITY.
Recent

VERSION 83-1
(JANUARY 1983)*MAJOR RE-DESIGN.
Recent

*PAGE SIZES INCREASED.
Recent

*ELIMINATED COMPUTER DEPENDENT CODING.  Recent

*NEW, MORE COMPATIBLE I/O UNIT NUMBERS. Recent

*ADDED OPTION TO KEEP ALL RECONSTRUCTED Recent

AND BACKGROUND ENERGY POINTS.
Recent

*ADDED STANDARD ALLOWABLE ERROR OPTIONS Recent

(CURRENTLY 0.1 PER-CENT RECONSTRUCTION Recent

AND 0.0 PER-CENT THINNING).
Recent

VERSION 83-2
(OCTOBER 1983) IMPROVED BASED ON USER COMMENTS.
Recent

VERSION 84-1
(JANUARY 1984) IMPROVED INTERVAL HALFING CONVERGENCE. Recent

VERSION 85-1
(APRIL 1985)  *A BRAND NEW PROGRAM
WHICH COMPLETELY   Recent

SUPERCEDES
ALL PREVIOUS VERSIONS OF
Recent

THIS PROGRAM.
Recent

*UPDATED FOR ENDF/B-VI FORMATS.
Recent

*ADDED GENERAL
REICH-MOORE FORMALISM
Recent

(WITH TWO FISSION CHANNELS).
Recent

*DECREASED RUNNING TIME.
Recent

*SPECIAL I/O ROUTINES TO GUARANTEE      Recent

ACCURACY OF ENERGY.
Recent

*DOUBLE PRECISION TREATMENT OF ENERGY   Recent

(REQUIRED FOR NARROW RESONANCES).      Recent

VERSION 85-2
(AUGUST 1985) *FORTRAN-77/H VERSION
Recent

VERSION 86-1
(JANUARY 1986)*ENERGY DEPENDENT SCATTERING RADIUS     Recent

VERSION 86-2
(JUNE 1986)   *IF FIRST CHANCE
FISSION (MT=19)
Recent

BACKGROUND IS PRESENT ADD RESONANCE    Recent

CONTRIBUTION OF FISSION TO IT.
Recent

VERSION 86-3
(OCTOBER 1986)*MULTI-LEVEL OR REICH-MOORE..CORRECT    Recent

POTENTIAL SCATTERING CROSS SECTION FOR Recent

MISSING AND/OR FICTICIOUS (L,J)
Recent

SEQUENCES.
Recent

VERSION 87-1
(JANUARY 1987)*IMPROVED COMBINING FILE 2+3
Recent

VERSION 87-2
(MARCH 1987)  *CORRECTED ADLER-ADLER
CALCULATIONS.    Recent

VERSION 88-1
(JULY 1988)   *UPDATED
REICH-MOORE ENDF/B-VI FORMAT
Recent

TO
BE THE SAME AS REICH-MOORE FORMAT
Recent

IN EARLIER VERSIONS OF ENDF/B FORMAT.  Recent

*CHECK FOR PRELIMINARY ENDF/B-VI
Recent

REICH-MOORE
FORMAT (NOW ABANDONED)
Recent

AND TERMINATE EXECUTION IF DATA IS     Recent

IN THIS FORMAT.
Recent

*CALCULATE
CHANNEL RADIUS OR SET IT
Recent

EQUAL TO THE SCATTERING RADIUS.
Recent

*IMPLEMENTED HYBRID R-FUNCTION WITH THE Recent

FOLLOWING RESTRICTIONS
Recent

- ONLY INELASTIC COMPETITION (NO
Recent

CHARGED PARTICLES)
Recent

- NO TABULATED FILE 2 BACKGROUND
Recent

- NO TABULATED OPTICAL MODEL PHASE     Recent

SHIFT
Recent

*PROGRAM EXIT IF GENERAL R-MATRIX IN    Recent

THE EVALUATION (THIS FORMALISM WILL    Recent

BE IMPLEMENTED ONLY AFTER THE AUTHOR   Recent

RECEIVES REAL EVALUATIONS WHICH USE    Recent

THIS FORMALISM...UNTIL THEN IT IS      Recent

IMPOSSIBLE TO ADEQUATELY TEST THAT     Recent

THE CODING FOR THIS FORMALISM IS       Recent

CORRECT).
Recent

*INCREASED MAXIMUM NUMBER OF RESONANCES Recent

FROM 1002 TO 4008.
Recent

*DOUBLE
PRECISION RESONANCE REGION      Recent

LIMITS.
Recent

*FILE 2 AND FILE 3 ENERGIES WHICH ARE   Recent

NEARLY
EQUAL ARE TREATED AS EQUAL      Recent

(I.E., SAME TO ABOUT 9 DIGITS).
Recent

*CHECK FILE 3 BACKGROUND CROSS SECTIONS Recent

IN
EDIT MODE.
Recent

*OPTION...INTERNALLY DEFINE FILENAMES   Recent

(SEE SUBROUTINE FILEIO FOR DETAILS).   Recent

VERSION 89-1
(JANUARY 1989)*PSYCHOANALYZED BY PROGRAM FREUD TO     Recent

INSURE PROGRAM WILL NOT DO ANYTHING    Recent

CRAZY.
Recent

*UPDATED TO USE NEW PROGRAM CONVERT     Recent

KEYWORDS.
Recent

*CORRECTED MULTILEVEL, REICH-MOORE AND  Recent

HYBRID R-FUNCTION POTENTIAL SCATTER    Recent

TO ACCOUNT FOR REPEATED J-VALUES FOR   Recent

THE SAME TARGET SPIN AND L-VALUE.      Recent

*ADDED LIVERMORE CIVIC COMPILER
Recent

CONVENTIONS.
Recent

*UPDATED TO USE NEW ENDF/B-VI
Recent

CONVENTION TO ALLOW UNRESOLVED
Recent

RESONANCE CONTRIBUTION TO ALREADY      Recent

BE INCLUDED IN THE FILE 3 CROSS
Recent

SECTIONS (INFINITELY DIULUTE
Recent

CONTRIBUTION).
Recent

VERSION 90-1
(JUNE 1990)   *UPDATED BASED ON
USER COMMENTS
Recent

*ADDED FORTRAN SAVE OPTION
Recent

*NEW
MORE CONSISTENT ENERGY OUTPUT      Recent

ROUTINE
Recent

VERSION 91-1
(JULY 1991)   *NEW UNIFORM
TREATMENT OF ALL RESONANCE Recent

FORMALISMS
(SEE, COMMENTS BELOW)       Recent

*NEW REICH-MOORE ALGORITHM
Recent

*MORE EXTENSIVE ERROR CHECKING AND      Recent

ERROR MESSAGE
EXPLANATIONS
Recent

VERSION 92-1
(JANUARY 1992)*MAJOR RESTRUCTING TO IMPROVE ACCURACY  Recent

AND COMPUTER INDEPENDENCE.
Recent

*INCREASED ENERGY POINT PAGE SIZE FROM  Recent

1002 TO 4008.
Recent

*NO MORE THAN 2 ENERGY POINTS WHERE     Recent

CROSS SECTION IS ZERO AT BEGINNING     Recent

OF A SECTION FOR EACH REACTION,E.G.,   Recent

THRESHOLD FISSION.
Recent

*PROCESS ONLY A PORTION OF RESONANCE    Recent

REGION - SEE EXPLANATION BELOW
Recent

*ALL ENERGIES INTERNALLY ROUNDED PRIOR  Recent

TO CALCULATIONS.
Recent

*COMPLETELY CONSISTENT I/O AND ROUNDING Recent

ROUTINES - TO MINIMIZE COMPUTER
Recent

DEPENDENCE.
Recent

VERSION 93-1
(MARCH 1993)  *UPDATED REICH-MOORE
TREATMENT TO USE   Recent

L DEPENDENT SCATTERING RADIUS (APL)    Recent

RATHER THAN SCATTERING RADIUS (AP)     Recent

(SEE,
ENDF/B-VI FORMATS AND
Recent

PROCEDURES MANUAL, PAGE 2.6)
Recent

*INCREASED PAGE SIZE FROM 4008 TO
Recent

20040
DATA POINTS.
Recent

*INCREASED MAXIMUM NUMBER OF RESONANCES Recent

FROM 4008 TO 20040.
Recent

VERSION 94-1
(JANUARY 1994)*VARIABLE ENDF/B DATA FILENAMES
Recent

TO ALLOW ACCESS TO FILE STRUCTURES     Recent

(WARNING - INPUT PARAMETER FORMAT      Recent

HAS BEEN CHANGED).
Recent

*CLOSE ALL FILES BEFORE TERMINATING     Recent

(SEE, SUBROUTINE ENDIT)
Recent

VERSION 94-2
(AUGUST 1994) *CORRECTED ADDJ FOR ENERGY DEPENDENT    Recent

(TABULATED) SCATTERING RADIUS CASE.    Recent

VERSION 96-1
(JANUARY 1996) *COMPLETE RE-WRITE
Recent

*IMPROVED COMPUTER INDEPENDENCE
Recent

*ALL DOUBLE PRECISION
Recent

*ON SCREEN OUTPUT
Recent

*UNIFORM TREATMENT OF ENDF/B I/O       Recent

*IMPROVED OUTPUT PRECISION
Recent

*ALWAYS INCLUDE THERMAL VALUE
Recent

*DEFINED SCRATCH FILE NAMES
Recent

VERSION 97-1
(APRIL 1997)   *OPTIONAL MAKE
NEGATIVE CROSS
Recent

SECTION = 0 FOR OUTPUT
Recent

*INCREASED PAGE SIZE FROM 20040 TO      Recent

120000
DATA POINTS.
Recent

*INCREASED MAXIMUM NUMBER OF RESONANCES Recent

FROM 20040 TO 120000.
Recent

VERSION 99-1
(MARCH 1999)   *CORRECTED
CHARACTER TO FLOATING
Recent

POINT READ FOR MORE DIGITS
Recent

*UPDATED TEST FOR ENDF/B FORMAT
Recent

VERSION
BASED ON RECENT FORMAT CHANGE Recent

*UPDATED CONSTANTS BASED ON CSEWG      Recent

SUBCOMMITTEE RECOMMENDATIONS
Recent

*GENERAL IMPROVEMENTS BASED ON
Recent

USER FEEDBACK
Recent

VERSION 99-2
(JUNE 1999)
*IMPLEMENTED NEW REICH-MOORE FORMALISM Recent

TO ALLOW DEFINITION OF (L,J,S) FOR    Recent

EACH SEQUENCE.
Recent

*ASSUME ENDF/B-VI, NOT V, IF MISSING   Recent

MF=1, MT-451.
Recent

VERS. 2000-1
(FEBRUARY 2000)*GENERAL IMPROVEMENTS BASED ON
Recent

USER FEEDBACK
Recent

VERS. 2002-1
(MAY 2002)
*OPTIONAL INPUT PARAMETERS             Recent

(SEPT. 2002)   *OUTPUT
RESONANCE WITH 9 DIGITS
Recent

*TO BE C AND C++ COMPATIBLE OUTPUT     Recent

VERS. 2004-1
(JAN. 2004)    *ADDED
INCLUDE 'recent.h'
Recent

*MADE ENDF/B-VII READY
Recent

*UPDATED FOR NEW REICH-MOORE LRF=7     Recent

PARAMETERS WITH COMPETITION
Recent

*ADDED
COULOMB PENETRATION FACTORS FOR Recent

LRF=7 COMPETITIVE CHANNELS.
Recent

*EXTENDED DEFINITIONS OF PENETRATION   Recent

FACTOR,
LEVEL SHIFT FACTOR, AND
Recent

POTENTIAL SCATTERING PHASE SHIFT      Recent

ABOVE L = 5 TO INFINITY.
Recent

*ADDED
QUICK CALCULATION - IF THE      Recent

INPUT ALLOWABLE ERROR IS 1.0 OR MORE  Recent

(100 % OR MORE) THERE IS NO ITERATION Recent

TO CONVERGENCE - CROSS SECTION ARE    Recent

QUICKLY CALCULATED ONLY AT A FIXED    Recent

SET OF ENERGY POINTS, BASED ON THE    Recent

ENERGY AND WIDTH OF ALL RESONANCES.   Recent

THIS CAN BE USED TO QUICKLY "SEE"     Recent

NEW EVALUATIONS THAT MAY CONTAIN      Recent

ERRORS, THAT WOULD OTHERWISE CAUSE    Recent

THIS CODE TO RUN FOR AN EXCESSIVELY   Recent

LONG TIME.
Recent

VERS. 2005-1
(JUNE 2005)    *ADDED
ENERGY DEPENDENT SCATTERING     Recent

RADIUS FOR ALL RESONANCE TYPES
Recent

(EARLIER ONLY BREIT-WIGNER ALLOWED).  Recent

VERS. 2007-1
(JAN. 2007)    *CHECKED
AGAINST ALL ENDF/B-VII.       Recent

*DECOUPLED PAGE SIZE FROM MAX. # OF    Recent

RESONANCES.
Recent

*INCREASED PAGE SIZE FROM 120,000 TO   Recent

750,000
DATA POINTS.
Recent

*KEPT MAX. # OF RESONANCE AT 120,000.  Recent

*CORRECTED ALL BACKGROUND = 0 CASE     Recent

Recent

OWNED,
MAINTAINED AND DISTRIBUTED BY
Recent

------------------------------------
Recent

THE NUCLEAR DATA
SECTION
Recent

INTERNATIONAL
ATOMIC ENERGY AGENCY
Recent

P.O. BOX
100
Recent

A-1400, VIENNA,
AUSTRIA                                            Recent

EUROPE
Recent

Recent

ORIGINALLY
WRITTEN BY
Recent

------------------------------------
Recent

DERMOTT E.
CULLEN
Recent

UNIVERSITY OF
CALIFORNIA
Recent

LAWRENCE
LIVERMORE NATIONAL LABORATORY
Recent

L-159
Recent

P.O. BOX
808
Recent

LIVERMORE, CA
94550
Recent

U.S.A.
Recent

TELEPHONE  925-423-7359
Recent

E. MAIL    [email-masked]
Recent

WEBSITE
HTTP://WWW.LLNL.GOV/CULLEN1
Recent

Recent

Acknowledgement
(Version 2004-1)
Recent

==================================================================
Recent

The author
thanks Nancy Larson, ORNL, for providing her SAMRML     Recent

code for
comparison to RECENT output for Reich-Moore evaluations,  Recent

in particular to
verify results for the new LFR=7 evaluations. I   Recent

also thank her
for providing guidance to help me understand and    Recent

implement this new
teatment for Reich-Moore parameters.
Recent

Recent

ACKNOWLEDGEMENT
(VERSION 92-1)
Recent

==================================================================
Recent

THE AUTHOR
THANKS SOL PEARLSTEIN (BROOKHAVEN NATIONAL LAB) FOR     Recent

SIGNIFICANTLY
CONTRIBUTING TOWARD IMPROVING THE ACCURACY AND
Recent

COMPUTER
INDEPENDENCE OF THIS CODE - THANKS, SOL
Recent

==================================================================
Recent

Recent

AUTHORS
MESSAGE
Recent

==================================================================
Recent

THE REPORT
DESCRIBED ABOVE IS THE LATEST PUBLISHED DOCUMENTATION   Recent

FOR THIS
PROGRAM. HOWEVER, THE COMMENTS BELOW SHOULD BE CONSIDERED Recent

THE LATEST
DOCUMENTATION INCLUDING ALL RECENT IMPROVEMENTS. PLEASE Recent

READ ALL OF
THESE COMMENTS BEFORE IMPLEMENTATION, PARTICULARLY     Recent

THE COMMENTS
CONCERNING MACHINE DEPENDENT CODING.
Recent

Recent

AT THE PRESENT
TIME WE ARE ATTEMPTING TO DEVELOP A SET OF COMPUTER Recent

INDEPENDENT
PROGRAMS THAT CAN EASILY BE IMPLEMENTED ON ANY ONE     Recent

OF A WIDE
VARIETY OF COMPUTERS. IN ORDER TO ASSIST IN THIS PROJECT Recent

IT WOULD BE
APPECIATED IF YOU WOULD NOTIFY THE AUTHOR OF ANY
Recent

COMPILER
DIAGNOSTICS, OPERATING PROBLEMS OR SUGGESTIONS ON HOW TO  Recent

IMPROVE THIS
PROGRAM. HOPEFULLY, IN THIS WAY FUTURE VERSIONS OF    Recent

THIS PROGRAM
WILL BE COMPLETELY COMPATIBLE FOR USE ON YOUR
Recent

COMPUTER.
Recent

Recent

PURPOSE
Recent

==================================================================
Recent

THIS PROGRAM IS
DESIGNED TO RECONSTRUCT THE RESONANCE CONTRIBUTION Recent

TO THE CROSS
SECTION IN LINEARLY INTERPOLABLE FORM, ADD IN ANY     Recent

LINEARLY
INTERPOLABLE BACKGROUND CROSS SECTION AND OUTPUT THE      Recent

RESULT IN THE
ENDF/B FORMAT. THE CROSS SECTIONS OUTPUT BY THIS     Recent

PROGRAM WILL BE
LINEARLY INTERPOLABLE OVER THE ENTIRE ENERGY RANGE Recent

Recent

THE RESONANCE
CONTRIBUTION IS CALCULATED FOR TOTAL (MT=1),
Recent

ELASTIC (MT=2),
CAPTURE (MT=102) AND FISSION (MT=18), ADDED
Recent

TO THE
BACKGROUND (IF ANY) AND OUTPUT. IN ADDITION, IF THERE
Recent

IS A FIRST
CHANCE FISSION (MT=19) BACKGROUND PRESENT THE RESONANCE Recent

CONTRIBUTION OF
FISSION WILL BE ADDED TO THE BACKGROUND AND
Recent

OUTPUT. IF THERE
IS NO FIRST CHANCE FISSION (MT=19) BACKGROUND     Recent

PRESENT THE
PROGRAM WILL NOT OUTPUT MT=19.
Recent

Recent

IN THE FOLLOWING
FOR SIMPLICITY THE ENDF/B TERMINOLOGY--ENDF/B     Recent

TAPE--WILL BE
USED. IN FACT THE ACTUAL MEDIUM MAY BE TAPE, CARDS,  Recent

DISK OR ANY
OTHER MEDIUM.
Recent

Recent

PROCESSING DATA
IN THE ENDF/B-VI FORMAT
Recent

==================================================================
Recent

IT HAS NOW BEEN
CONFIRMED (PRIVATE COMMUNICATION, CHARLES DUNFORD, Recent

APRIL, 1991)
THAT THE PROPER PROCEDURE TO FOLLOW WHEN THERE ARE    Recent

MISSING OR DUPLICATE
J VALUES IS TO IN ALL CASES ADD A SEQUENCE    Recent

WITH NO
RESONANCES TO ACCOUNT FOR THE CONTRIBUTION OF THE SEQUENCE Recent

TO THE POTENTIAL
SCATTERING CROSS SECTION.
Recent

Recent

THIS IS THE
PROCEDURE WHICH WAS FOLLOWED BY ALL VERSIONS OF RECENT Recent

SINCE 86-3 AND
WILL CONTINUE TO BE THE PROCEDURE.
Recent

Recent

INPUT ENDF/B
FORMAT AND CONVENTIONS
Recent

==================================================================
Recent

ENDF/B
FORMAT
Recent

-------------
Recent

THIS PROGRAM
ONLY USES THE ENDF/B BCD OR LINE IMAGE FORMAT (AS     Recent

OPPOSED TO THE
BINARY FORMAT) AND CAN HANDLE DATA IN ANY VERSION   Recent

OF THE ENDF/B
FORMAT (I.E., ENDF/B-I, II,III, IV, V OR VI FORMAT). Recent

Recent

IT IS ASSUMED
THAT THE DATA IS CORRECTLY CODED IN THE ENDF/B       Recent

FORMAT AND NO
ERROR CHECKING IS PERFORMED. IN PARTICULAR IT IS     Recent

ASSUMED THAT THE
MAT, MF AND MT ON EACH LINE IS CORRECT. SEQUENCE  Recent

NUMBERS (COLUMNS
76-80) ARE IGNORED ON INPUT, BUT WILL BE
Recent

CORRECTLY OUTPUT
ON ALL CARDS. THE FORMAT OF SECTION MF=1, MT=451  Recent

AND ALL SECTIONS
OF MF=2 AND 3 MUST BE CORRECT. THE PROGRAM COPIES Recent

ALL OTHER
SECTION OF DATA AS HOLLERITH AND AS SUCH IS INSENSITIVE  Recent

TO THE CORRECTNESS OR INCORRECTNESS OF
ALL OTHER SECTIONS.
Recent

Recent

ENDF/B FORMAT
VERSION
Recent

---------------------
Recent

THE FORMATS AND
CONVENTIONS FOR READING AND INTERPRETING THE DATA  Recent

VARIES FROM ONE
VERSION OF ENDF/B TO THE NEXT. HOWEVER, IF THE     Recent

HOLLERITH
SECTION (MF=1, MT=451) IS PRESENT IT IS POSSIBLE FOR     Recent

THIS PROGRAM TO
DISTINGUISH BETWEEN DATA IN THE ENDF/B-IV, V AND   Recent

VI FORMATS AND
TO USE THE APPROPRIATE CONVENTIONS FOR EACH
Recent

ENDF/B VERSION
(SEE, SUBROUTINE FILE1 FOR A DESCRIPTION OF HOW     Recent

THIS IS DONE).
IF THE HOLLERITH SECTION IS NOT PRESENT THE
Recent

PROGRAM WILL
ASSUME THE DATA IS IN THE ENDF/B-VI FORMAT AND USE    Recent

ALL CONVENTIONS
APPROPRIATE TO ENDF/B-V. USERS ARE ENCOURAGED TO   Recent

INSURE THAT THE
HOLLERITH SECTION (MF=1, MT=451) IS PRESENT IN     Recent

ALL
EVALUATIONS.
Recent

Recent

INPUT OF
ENERGIES
Recent

-----------------
Recent

ALL ENERGIES ARE
READ IN DOUBLE PRECISION (BY SPECIAL FORTRAN I/O  Recent

ROUTINES) AND
ARE TREATED IN DOUBLE PRECISION IN ALL CALCULATIONS. Recent

Recent

OUTPUT ENDF/B
FORMAT AND CONVENTIONS
Recent

==================================================================
Recent

CONTENTS OF
OUTPUT
Recent

------------------
Recent

ENTIRE EVALUATIONS ARE
OUTPUT, NOT JUST THE RECONSTRUCTED FILE     Recent

3 CROSS
SECTIONS, E.G. ANGULAR AND ENERGY DISTRIBUTIONS ARE
Recent

ALSO
INCLUDED.
Recent

Recent

DOCUMENTATION
Recent

-------------
Recent

THE FACT THAT
THIS PROGRAM HAS OPERATED ON THE DATA IS DOCUMENTED  Recent

BY THE ADDITION
OF COMMENT CARDS AT THE END OF EACH HOLLERITH      Recent

SECTION IN THE
FORM
Recent

Recent

***************** RECENT (VERSION 2007-1) ***************
Recent

RESONANCE
CONTRIBUTION RECONSTRUCTED TO WITHIN
0.100 PER-CENT
Recent

COMBINED DATA
NOT THINNED (ALL RESONANCE + BACKGROUND DATA KEPT)   Recent

Recent

THE ORDER OF ALL
SIMILAR COMMENTS (FROM LINEAR, SIGMA1 AND GROUPY) Recent

REPRESENTS A
COMPLETE HISTORY OF ALL OPERATIONS PERFORMED ON
Recent

THE DATA,
INCLUDING WHICH VERSION OF EACH PROGRAM WAS USED.
Recent

Recent

THESE COMMENT
CARDS ARE ONLY ADDED TO EXISTING HOLLERITH SECTIONS, Recent

I.E., THIS
PROGRAM WILL NOT CREATE A HOLLERITH SECTION. THE FORMAT Recent

OF THE HOLLERITH
SECTION IN ENDF/B-V DIFFERS FROM THE THAT OF      Recent

EARLIER VERSIONS
OF ENDF/B. BY READING AN EXISTING MF=1, MT=451    Recent

IT IS POSSIBLE
FOR THIS PROGRAM TO DETERMINE WHICH VERSION OF      Recent

THE ENDF/B
FORMAT THE DATA IS IN. WITHOUT HAVING A SECTION OF      Recent

MF=1, MT=451
PRESENT IT IS IMPOSSIBLE FOR THIS PROGRAM TO
Recent

DETERMINE WHICH
VERSION OF THE ENDF/B FORMAT THE DATA IS IN, AND   Recent

AS SUCH IT IS
IMPOSSIBLE FOR THE PROGRAM TO DETERMINE WHAT FORMAT  Recent

SHOULD BE USED
TO CREATE A HOLLERITH SECTION.
Recent

Recent

REACTION
INDEX
Recent

--------------
Recent

THIS PROGRAM DOES
NOT USE THE REACTION INDEX WHICH IS GIVEN IN     Recent

SECTION MF=1,
MT=451 OF EACH EVALUATION.
Recent

Recent

THIS PROGRAM
DOES NOT UPDATE THE REACTION INDEX IN MF=1, MT=451.   Recent

THIS CONVENTION
HAS BEEN ADOPTED BECAUSE MOST USERS DO NOT
Recent

REQUIRE A
CORRECT REACTION INDEX FOR THEIR APPLICATIONS AND IT WAS Recent

NOT CONSIDERED
WORTHWHILE TO INCLUDE THE OVERHEAD OF CONSTRUCTING  Recent

A CORRECT
REACTION INDEX IN THIS PROGRAM. HOWEVER, IF YOU REQUIRE  Recent

A REACTION INDEX
FOR YOUR APPLICATIONS, AFTER RUNNING THIS PROGRAM Recent

YOU MAY USE
PROGRAM DICTIN TO CREATE A CORRECT REACTION INDEX.     Recent

Recent

OUTPUT FORMAT OF
ENERGIES
Recent

-------------------------
Recent

IN THIS VERSION
OF RECENT ALL FILE 3 ENERGIES WILL BE OUTPUT IN    Recent

F (INSTEAD OF E)
FORMAT IN ORDER TO ALLOW ENERGIES TO BE WRITTEN   Recent

WITH UP TO 9
DIGITS OF ACCURACY. IN PREVIOUS VERSIONS THIS WAS AN  Recent

OUTPUT OPTION.
HOWEVER USE OF THIS OPTION TO COMPARE THE RESULTS   Recent

OF ENERGIES
WRITTEN IN THE NORMAL ENDF/B CONVENTION OF 6 DIGITS    Recent

TO THE 9 DIGIT
OUTPUT FROM THIS PROGRAM DEMONSTRATED THAT FAILURE  Recent

TO USE THE 9
DIGIT OUTPUT CAN LEAD TO LARGE ERRORS IN THE DATA     Recent

JUST DUE TO
TRANSLATION OF ENERGIES FROM THEIR INTERNAL (BINARY)   Recent

REPRESENTATION
TO THE ENDF/B FORMAT.
Recent

Recent

ACCURACY OF
ENERGY
Recent

------------------
Recent

IN ORDER TO ALLOW
ENERGIES TO BE ACCURATELY OUTPUT TO 9 DIGITS     Recent

ON SHORT WORD
LENGTH COMPUTERS (E.G. IBM) ALL ENERGIES AND
Recent

ENERGY DEPENDENT
TERMS ARE READ AND TREATED IN DOUBLE PRECISION.   Recent

Recent

OUTPUT OF
RESONANCE PARAMETERS
Recent

------------------------------
Recent

A SPECIAL
CONVENTION HAS BEEN INTRODUCED REGARDING RESONANCE
Recent

PARAMETERS. IN
ORDER TO ALLOW THE USER TO DOPPLER BROADEN AND/OR   Recent

SELF-SHIELD
CROSS SECTIONS THE RESONANCE PARAMETERS ARE ALSO
Recent

INCLUDED IN THE
OUTPUT WITH THE EVALUATION. IN ORDER TO AVOID THE  Recent

POSSIBILITY OF
ADDING THE RESONANCE CONTRIBUTION A SECOND TIME     Recent

TWO CONVENTIONS
HAVE BEEN ADOPTED TO INDICATE THAT THE RESONANCE   Recent

CONTRIBUTION HAS
ALREADY BEEN ADDED TO THE FILE 3 CROSS SECTIONS,  Recent

Recent

(1) WHEN THE
DATA IS PROCESSED BY THIS PROGRAM LRP (IN MF=1,
Recent

MT=451) IS SET
EQUAL TO 2. THIS IS A CONVENTION WHICH HAS BEEN     Recent

ADOPTED AS A
STANDARD CONVENTION IN ENDF/B-VI, BUT IS ONLY TO BE   Recent

USED FOR
PROCESSED DATA, AS OPPOSED TO THE ORIGINAL EVALUATIONS.   Recent

IN EVALUATIONS
WHICH CONTAIN MF=1, MT=451 LRP CAN BE USED TO       Recent

DETERMINE IF THE
MATERIAL HAS BEEN PROCESSED.
Recent

Recent

(2) THE LRU FLAG
IN EACH SECTION OF FILE 2 DATA IS CHANGED TO      Recent

LRU=LRU+3. FOR
EXAMPLE WHEN READING AN ENDF/B EVALUATION LRU=0     Recent

(NO RESONANCES),
=1 (RESOLVED) OR =2 (UNRESOLVED) INDICATES THAT   Recent

THE DATA IS IN
THE ORIGINAL ENDF/B FORM. LRU=3 (NO RESONANCES),    Recent

=4 (RESOLVED) OR
=5 (UNRESOLVED) INDICATES THAT THE RESONANCE      Recent

CONTRIBUTION HAS
ALREADY BEEN ADDED TO THE FILE 3 DATA. THIS
Recent

SECOND
CONVENTION HAS BEEN ADOPTED AS INSURANCE THAT THE RESONANCE Recent

CONTRIBUTION
WILL NOT BE ADDED TWICE, EVEN FOR EVALUATIONS WHICH   Recent

DO NOT CONTAIN
MF=1, MT=451 (EVALUATIONS WHICH CONTAIN MF=1,
Recent

MT=451 ARE
COVERED BY CONVENTION (1), DESCRIBED ABOVE).
Recent

Recent

UNIFORM
TREATMENT OF RESONANCE FORMALISMS
Recent

==================================================================
Recent

NORMALIZATION
Recent

=============
Recent

ALL OF THE
RESONANCE FORMALISMS INCLUDE A FACTOR OF,
Recent

Recent

PI*(FRACTIONAL
ABUNDANCE)/(K**2)
Recent

Recent

THIS FACTOR HAS
BEEN REMOVED FROM THE CALCULATION OF EACH TYPE     Recent

OF RESONANCE
FORMALISM AND IS APPLIED AS A FINAL NORMALIZATION     Recent

AFTER THE
CALCULATION, ONLY ONE PLACE IN THIS PROGRAM.
Recent

Recent

FOR SIMPLICITY
THIS TERM IS NOT INCLUDED IN THE FOLLOWING
Recent

DERIVATIONS - IN
ALL CASES THE ACTUAL CROSS SECTION IS A PRODUCT   Recent

OF THE ABOVE
FACTOR TIMES THE RESULTS PRESENTED BELOW.
Recent

Recent

SIMILARITIES
Recent

============
Recent

FOR THE RESOLVED
RESONANCE REGION, EXCEPT FOR SINGLE LEVEL BREIT   Recent

WIGNER,
PARAMETERS ALL OF THE FORMALISMS DEFINE THE CROSS SECTIONS Recent

IN AN EQUIVALENT
FORM,
Recent

Recent

TOTAL    = 2*GJ*REAL(1 - U)
Recent

= 2*GJ*(1 - REAL(U))
Recent

ELASTIC  =   GJ*(1 - U)**2                                         Recent

=   GJ*((1 - 2*REAL(U))
+ (REAL(U)**2 + IM(U)**2))
Recent

= 2*GJ*(1 - REAL(U)) - GJ*(1 - (REAL(U)**2 + IM(U)**2))   Recent

Recent

SINCE THE FIRST
TERM IS THE TOTAL, THE SECOND TERM MUST BE
Recent

ABSORPTION. SO
WE FIND,
Recent

Recent

ABSORPTION =
GJ*(1 - (REAL(U)**2 + IM(U)**2))
Recent

Recent

IN ALL CASES U
IS DEFINED IN THE FORM,
Recent

Recent

U        =
EXP(-I*2*PS)*((1-X) - I*Y)
Recent

Recent

WHERE (X) AND
(Y) ARE RELATED TO THE SYMMETRIC AND ANTI-SYMMETRIC  Recent

CONTRIBUTIONS OF
THE RESONANCES, RESPECTIVELY. ONLY THE DEFINITION Recent

OF (X) AND (Y)
WILL BE DIFFERENT FOR EACH RESONANCE FORMALISM.     Recent

BELOW WE WILL SHOW THAT WHAT
MIGHT APPEAR TO BE A STRANGE CHOICE
Recent

OF DEFINITION OF
THE SIGN OF (X) AND(Y) HAS BEEN SELECTED SO THAT  Recent

FOR BREIT-WIGNER
PARAMETERS (X) AND (Y) CORRESPOND EXACTLY TO THE  Recent

SYMMETRIC AND
ANTI-SYMMETRIC CONTRIBUTION OF THE RESONANCES.
Recent

Recent

U        =
(COS(2*PS) - I*SIN(2*PS))*((1-X) - I*Y)
Recent

=   ((1-X)*COS(2*PS) -
Y*SIN(2*PS))
Recent

=-I*((1-X)*SIN(2*PS) + Y*COS(2*PS))
Recent

Recent

REAL(U)  = ((1-X)*COS(2*PS) - Y*SIN(2*PS))
Recent

IM(U)    =-((1-X)*SIN(2*PS) +
Y*COS(2*PS))
Recent

Recent

R(U)**2  =((1-X)*COS(2*PS))**2 + (Y*SIN(2*PS))**2
Recent

-2*(1-X)*Y*COS(2*PS)*SIN(2*PS)
Recent

I(U)**2  =((1-X)*SIN(2*PS))**2 +
(Y*COS(2*PS))**2
Recent

+2*(1-X)*Y*COS(2*PS)*SIN(2*PS)                           Recent

Recent

THE TERMS
2*(1-X)*Y*COS(2*PS)*SIN(2*PS) CANCEL AND UPON USING      Recent

THE IDENTITY
COS(2*PS)**2 + SIN(2*PS)**2 = 1,
Recent

Recent

SUM      = (1-X)**2 +
(Y)**2
Recent

Recent

WE NOW HAVE ALL
THE QUANTITIES THAT WE NEED TO DEFINE THE CROSS    Recent

SECTIONS,
Recent

Recent

ELASTIC
Recent

=======
Recent

ELASTIC  =GJ*(1 - 2*REAL(U) + (REAL(U)**2 +
IM(U)**2))
Recent

=GJ*(1 -
2*((1-X)*COS(2*PS)-Y*SIN(2*PS))+(1-X)**2+(Y)**2) Recent

Recent

THIS CAN BE
WRITTEN AS A SUM OF 2 SQUARES,
Recent

Recent

ELASTIC  =GJ*(COS(2*PS) - (1-X))**2 + (SIN(2*PS)
+ Y)**2)
Recent

Recent

=GJ*((COS(2*PS))**2 - 2*(1-X)*COS(2*PS) + (1-X)**2) +     Recent

(SIN(2*PS))**2 + 2*Y*SIN(2*PS)    + (Y)**2)
Recent

Recent

AGAIN USING THE
IDENTITY COS(2*PS)**2 + SIN(2*PS)**2 = 1, WE CAN   Recent

SEE THAT THE
DEFINITION AS THE SUM OF 2 SQUARES IS IDENTICAL TO    Recent

THE PRECEDING
DEFINITION OF THE ELASTIC.
Recent

Recent

ELASTIC  =GJ*(COS(2*PS) - (1-X))**2 + (SIN(2*PS)
+ Y)**2)
Recent

=GJ*((COS(2*PS)-1) + X)**2 + (SIN(2*PS) + Y)**2)
Recent

Recent

USING THE
IDENTITY (1 - COS(2*PS))) = 2*SIN(PS)**2, WE OBTAIN      Recent

THE FINAL FORM
FOR THE ELASTIC,
Recent

Recent

ELASTIC
=GJ*(2*SIN(PS)**2 - X)**2 + (SIN(2*PS) + Y)**2)
Recent

Recent

ABSORPTION
Recent

==========
Recent

ABSORPTION =
GJ*(1 - (REAL(U)**2 + IM(U)**2))
Recent

= GJ*(1 - ((1-X)**2   +
(Y)**2)
Recent

=
GJ*(1 - (1 - 2*X + (X)**2 + (Y)**2)
Recent

= GJ*(2*X - (X)**2 + (Y)**2)
Recent

Recent

SINCE PHYSICALLY
THE ABSORPTION CANNOT BE NEGATIVE WE CAN SEE      Recent

THAT (X) MUST BE
POSITIVE AND 2*X MUST BE GREATER THAN
Recent

(X)**2 + (Y)**2,
FOR ALL OF THE FORMALISMS.
Recent

Recent

TOTAL
Recent

=====
Recent

IN THIS PROGRAM
THE TOTAL CROSS SECTION IS ALWAYS DEFINED TO BE    Recent

THE SUM OF ITS
PARTS - SO THE ABOVE DEFINITION IS NEVER EXPLICITLY Recent

USED. HOWEVER,
WE CAN LEARN SOMETHING BY EXAMINING THE DEFINITION, Recent

Recent

TOTAL    = 2*GJ*REAL(1 - U)
Recent

= 2*GJ*(1 - (((1-X)*COS(2*PS) - Y*SIN(2*PS)))
Recent

= 2*GJ*((1 - COS(2*PS))*(1-X) - (1-X) + Y*SIN(2*PS))      Recent

= 2*GJ*(2*SIN(PS)**2*(1-X)    - (1-X) + Y*SIN(2*PS))      Recent

Recent

= 4*GJ*SIN(PS)**2 +
Recent

2*GJ*((X-1) - 2*X*SIN(PS)**2 +
Y*SIN(2*PS))
Recent

Recent

THE IMPORTANT
POINT TO NOTE IS THAT THE DEFINITION OF THE TOTAL    Recent

DOES NOT
EXPLICITLY CONTAIN ANY DEPENDENCE ON X**2 AND Y**2 -      Recent

THE LEVEL-LEVEL
INTERFERENCE TERMS.
Recent

Recent

THIS IMPLIES
THAT IF A GIVEN SET OF RESONANCE PARAMETERS ARE USED  Recent

WITH THIS
DEFINITION THEY WILL PRODUCE EXACTLY THE SAME TOTAL      Recent

CROSS SECTION -
WHETHER WE CLAIM THE PARAMETERS HAVE BEEN
Recent

PRODUCED USING A
SINGLE OR MULTI-LEVEL FIT. THIS RESULT COULD      Recent

BE VERY
MISLEADING, IF THIS RESULT FOR THE TOTAL IS IMPLIED TO     Recent

MEAN THAT ONE
INTERPRETATION OR THE OTHER WILL NOT HAVE ANY
Recent

EFFECT ON THE
INDIVIDUAL CROSS SECTIONS.
Recent

Recent

STARTING FROM
EXACTLY THE SAME RESONANCE PARAMETERS, RELATIVE TO   Recent

THE RESULTS
OBTAINED USING THE SINGLE LEVEL FORMULA, MULTI-LEVEL   Recent

RESULTS WILL
TEND TO ALWAYS DECREASE THE ABSORPTION AND INCREASE   Recent

THE ELASTIC.
THIS CAN BE IMMEDIATELY SEEN FROM OUR GENERAL
Recent

MULTI-LEVEL
DEFINITION OF ABSORPTION,                              Recent

Recent

ABSORPTION
=GJ*(2*X - ((X)**2 + (Y)**2))
Recent

Recent

THE SINGLE LEVEL
ABSORPTION IS,
Recent

Recent

ABSORPTION
=GJ*(2*X)
Recent

Recent

THE DIFFERENCE
BETWEEN THE TWO IS -2*GJ*(X**2 + Y**2), SO THAT     Recent

REGARDLESS OF
HOW WE DEFINE (X) AND (Y) THE INCLUSION OF THIS      Recent

TERM WILL ALWAYS
DECREASE ABSORPTION. SINCE THE TOTAL CROSS
Recent

SECTION IS THE
SAME IN BOTH CASE, THIS MEANS THAT THE ELASTIC      Recent

HAS BEEN
INCREASED BY THIS AMOUNT.
Recent

Recent

AGAIN, THESE
RESULTS ARE BASED ON STARTING FROM EXACTLY THE SAME   Recent

PARAMETERS - IN
ANY ACTUAL CASE THE PARAMETERS BASED ON A SINGLE   Recent

OR MULTI-LEVEL
FIT WILL BE QUITE DIFFERENT - THE POINT THAT WE     Recent

WANT TO STRESS
HERE IS THAT YOU SHOULD NEVER USE PARAMETERS
Recent

WHICH HAVE BEEN
DEFINED BY A FIT USING ONE FORMALISM - IN THE      Recent

EQUATIONS FOR A
DIFFERENT FORMALISM - AND ASSUME THAT THE RESULTS  Recent

WILL BE
CONSISTENT - AND NEVER USE THE TOTAL CROSS SECTION TO      Recent

SEE WHETHER OR
NOT A SET OF SINGLE LEVEL PARAMETERS CAN BE USED    Recent

WITH A
MULTI-LEVEL FORMALISM.
Recent

Recent

POTENTIAL CROSS
SECTION
Recent

=======================
Recent

FAR FROM
RESONANCES (X) AND (Y) WILL BE SMALL AND THE ELASTIC      Recent

CROSS SECTION
REDUCES TO,
Recent

Recent

ELASTIC
=GJ*(2*SIN(PS)**2)**2
+ (SIN(2*PS))**2
Recent

=GJ*4*(SIN(PS)**4
+ SIN(2*PS)**2
Recent

Recent

USING THE
IDENTITY SIN(2*PS) = 2*SIN(PS)*COS(PS)
Recent

Recent

=4*GJ*(SIN(PS)**4
+ (SIN(PS)*COS(PS))**2)
Recent

=4*GJ*SIN(PS)**2*(SIN(PS)**2 + COS(PS)**2)
Recent

=4*GJ*SIN(PS)**2
Recent

Recent

WHICH IS THE POTENTIAL
CROSS SECTION. NOTE THAT THIS RESULT IS     Recent

INDEPENDENT OF
THE FORMALISM USED, AS IT MUST PHYSICALLY BE,
Recent

AND AS SUCH
ALTHOUGH AS YET WE HAVE NOT DEFINED IT, WE CAN
Recent

NOW SEE THAT IN
ALL CASES (PS) MUST BE THE PHASE SHIFT AND FOR     Recent

CONSISTENCY IT
MUST BE DEFINED USING EXACTLY THE SAME DEFINITION   Recent

IN ALL
CASES.
Recent

Recent

IN ADDITION
SINCE PHYSICALLY FOR EACH L VALUE WE EXPECT TO OBTAIN  Recent

A POTENTIAL
CROSS SECTION,
Recent

Recent

4*(2*L+1)*SIN(PS)**2
Recent

Recent

OBVIOUSLY FOR
CONSISTENCY WE MUST HAVE,
Recent

Recent

(2*L+1) = (SUM
OVER J) GJ
Recent

Recent

ONLY IN THIS
CASE WILL THE RESULTS BE CONSISTENT - THIS POINT WILL Recent

BE DISCUSSED IN
DETAIL BELOW.
Recent

Recent

WHAT ARE THIS
TERMS (X) AND (Y)
Recent

===============================
Recent

(X) AND (Y) CAN
BE EASILY IDENTIFIED BY CONSIDERING THE SINGLE     Recent

AND MULTI-LEVEL
BREIT WIGNER FORMALISMS. IN THESE CASES WE WILL    Recent

FIND THAT,
Recent

Recent

X        =
GAM(N)*GAM(T)/2/DEN
Recent

Y        =
GAM(N)*(E-ER)/DEN
Recent

DEN      = ((E-ER)**2 +
(GAM(T)/2)**2)
Recent

Recent

EXTREME CARE HAS
TO BE USED TO PROPERLY DEFINE (Y) SUCH THAT IT    Recent

IS NEGATIVE FOR
E LESS THAN ER AND POSITIVE FOR E GREATER THAN     Recent

ER. I WILL MERELY
MENTION THAT THE EQUATIONS FOR ALL FORMALISMS    Recent

IN ENDF-102 DO
NOT CONSISTENTLY USE (E - ER) - IN SOME CASES
Recent

THIS IS WRITTEN
AS (ER - E), WHICH CAN LEAD TO AN INCORRECT
Recent

SIGN IN THE
DEFINITION OF THE (Y) THAT WE REQUIRE.
Recent

Recent

THE INTERFERENCE
TERMS CAN BE WRITTEN IN TERMS OF,
Recent

1) LEVEL-SELF
INTERFERENCE  = THE CONTRIBUTION OF
EACH LEVEL
Recent

INTERFERRING WITH ITSELF
Recent

2) LEVEL-LEVEL
INTERFERENCE = THE CONTRIBUTION OF EACH LEVEL
Recent

INTERFERRRING WITH ALL OTHER LEVELS
Recent

Recent

WE WILL REFER TO
THESE TWO AS (L-S) AND (L-L),
Recent

Recent

X**2     =
(GAM(N)*(GAM(T)/2)**2/(DEN)**2      + (L-L)
Recent

= (GAM(N)**2*((GAM(T)/2)**2)/(DEN)**2 + (L-L)
Recent

Y**2     =
(GAM(N))**2*((E-ER))**2/(DEN)**2    + (L-L)
Recent

Recent

X**2+Y**2=
GAM(N)**2*DEN/(DEN)**2 = GAM(N)**2/DEN + (L-L)
Recent

Recent

TO SEE THE
EFFECT OF INCLUDING MULTI-LEVEL INTERFERENCE WE CAN     Recent

CONSIDER OUR
GENERAL EXPRESSION FOR ABSORPTION,
Recent

Recent

ABSORPTION
=GJ*(2*X - ((X)**2 + (Y)**2))
Recent

Recent

AND NOTE THAT
FOR BOTH SINGLE AND MULTI-LEVEL BREIT WIGNER THE     Recent

ENDF-102 SAYS TO
TREAT ABSORPTION IN A SINGLE LEVEL APPROXIMATION  Recent

I.E., IGNORE
LEVEL-LEVEL INTERFERENCE. IF ALL INTERFERENCE IS      Recent

IGNORED THIS IS
EQUIVALENT TO COMPLETELY IGNORING X**2 + Y**2 AND  Recent

DEFINING,
Recent

Recent

ABSORPTION
=GJ*2*X
Recent

=2*GJ*GAM(N)*GAM(T)/DEN
Recent

Recent

WHICH IS
INCORRECT - SINCE THIS SEEMS TO INDICATE EVERYTHING IS    Recent

ABSORBED. IN
ORDER TO OBTAIN THE CORRECT EXPRESSION WE CANNOT      Recent

COMPLETELY
IGNORE INTERFERENCE - WE CAN IGNORE LEVEL-LEVEL
Recent

INTERFERENCE,
BUT WE MUST INCLUDE LEVEL-SELF INTERFERENCE,
Recent

Recent

X**2+Y**2=
GAM(N)**2/DEN
Recent

Recent

ABSORPTION
=GJ*(2*X - ((X)**2 + (Y)**2))
Recent

=GJ*GAM(N)*(GAM(T)-GAM(N))/DEN
Recent

=GJ*GAM(N)*GAM(A)/DEN
Recent

Recent

SUMMARY
Recent

=======
Recent

AN IMPORTANT
POINT TO NOTE IS THE DEFINITION OF (X) AND (Y)
Recent

WHICH IN ALL
CASES WILL CORRESPOND TO THE SYMMETRIC AND
Recent

ANTI-SYMMETRIC
CONTRIBUTION OF THE RESONANCES. IN PARTICULAR
Recent

DEFINING (U) IN
TERMS OF (1-X) INSTEAD OF (X) IS EXTREMELY
Recent

IMPORTANT. NOTE,
THAT THE DEFINITION OF THE ELASTIC AND
Recent

ABSORPTION ONLY
INVOLVE (X), NOT (1-X). FAR FROM RESONANCES
Recent

(X) CAN BE
EXTREMELY SMALL, THEREFORE (1-X) WILL BE VERY CLOSE     Recent

TO (1). IF THE
CALCULATION PROCEEDS BY FIRST CALCULATING (1-X)     Recent

AND THEN
DEFINING (X) BY SUBTRACTING (1), EXTREME ROUND-OFF
Recent

PROBLEMS CAN
RESULT. THESE PROBLEMS CAN BE AVOIDED BY IN ALL
Recent

CASES DEFINING
(X) DIRECTLY, WITHOUT ANY DIFFERENCES.
Recent

Recent

IN EACH
FORMALISM THE DEFINITION OF (X) AND (Y) MAY BE DIFFERENT   Recent

BUT ONCE WE HAVE
DEFINED (X) AND (Y) WE CAN IMMEDIATELY WRITE      Recent

THE CROSS
SECTIONS USING A UNIFORM DEFINITION,
Recent

Recent

ELASTIC
=GJ*(2*SIN(PS)**2 - X)**2 + (SIN(2*PS) + Y)**2)
Recent

Recent

ABSORPTION
=-GJ*(2*X + (X)**2 + (Y)**2)
Recent

Recent

AND DEFINE THE
TOTAL AS THE SUM OF THESE 2 PARTS.
Recent

Recent

RELATIONSHIP TO
SINGLE LEVEL
Recent

============================
Recent

HOW DO THE
SINGLE AND MULTI-LEVEL FORMALISMS COMPARE. TO SEE,      Recent

STARTING FROM
OUR GENERAL DEFINITION OF THE ELASTIC IN THE FORM,   Recent

Recent

ELASTIC
=GJ*(2*SIN(PS)**2 + X)**2 + (SIN(2*PS) + Y)**2)
Recent

=GJ*(4*SIN(PS)**4 - 4*X*SIN(PS)**2 + X**2
Recent

+ SIN(2*PS)**2 +
2*Y*SIN(2*PS)  + Y**2)
Recent

Recent

=4*GJ*SIN(PS)**2 +
Recent

GJ*(X**2 + Y**2
Recent

-4*X*SIN(PS)**2
Recent

+2*Y*SIN(2*PS))
Recent

Recent

AND OUR SPECIFIC
DEFINITIONS OF (X) AND (Y) FOR MULTI-LEVEL BREIT- Recent

WIGNER
PARAMETERS,
Recent

Recent

X        =
GAM(N)*GAM(T)/2/DEN
Recent

Y        =
GAM(N)*(E-ER)/DEN
Recent

DEN      = ((E-ER)**2 +
(GAM(T)/2)**2)
Recent

Recent

X**2+Y**2=
GAM(N)**2/DEN + (L-L)
Recent

Recent

WE CAN RECOGNIZE
X**2 AND Y**2 AS THE INTERFERENCE - (L-S) + (L-L) Recent

TERMS IN THE
MULTI-LEVEL FORMALISM. IN ORDER TO OBTAIN THE SINGLE  Recent

LEVEL EQUATION
WE CAN ASSUME THAT EACH LEVEL DOES NOT INTERFERE    Recent

WITH ANY OTHER
LEVEL - THEREFORE THE (L-L) CONTRIBUTION IS ZERO.   Recent

Recent

ELASTIC
=4*GJ*SIN(PS)**2 +
Recent

GJ*GAM(N)*(GAM(N)
Recent

-2*GAM(T)*SIN(PS)**2
Recent

+2*(E-ER)*SIN(2*PS))/DEN
Recent

Recent

WHICH IS THE
FORM THAT IT APPEARS IN ENDF-102, EXCEPT FOR TWO      Recent

TYPOGRAPHICAL
ERRORS IN THE SECOND TERM,
Recent

Recent

-2*GAM(T)*SIN(PS)**2
Recent

Recent

WHICH IN
ENDF-102 IS WRITTEN,
Recent

Recent

-2*(GAM(T)-GAM(N))*SIN(2*PS)**2
Recent

Recent

PROGRAM
CONVENTIONS
Recent

==================================================================
Recent

MINIMUM INPUT
DATA
Recent

------------------
Recent

FOR EACH
MATERIAL TO BE PROCESSED THE MINIMUM INPUT DATA ARE THE   Recent

RESONANCE
PARAMETERS IN FILE 2. IF THERE ARE NO FILE 2 PARAMETERS  Recent

IN A GIVEN
MATERIAL THE ENTIRE MATERIAL WILL SIMPLY BE COPIED.     Recent

NEITHER THE
HOLLERITH SECTION (MF=1, MT=451) NOR THE BACKGROUND    Recent

CROSS SECTION
(SECTIONS OF MF=3) NEED BE PRESENT FOR THIS PROGRAM  Recent

TO EXECUTE
PROPERLY. HOWEVER, SINCE THE CONVENTIONS USED IN
Recent

INTERPRETING THE
RESONANCE PARAMETERS DEPENDS ON ENDF/B VERSION    Recent

USERS ARE
STRONGLY RECOMMENDED TO INSURE THAT MF=1, MT=451 IS      Recent

PRESENT IN EACH
MATERIAL TO ALLOW THE PROGRAM TO DETERMINE THE     Recent

ENDF/B FORMAT
VERSION.
Recent

Recent

RESONANCE
PARAMETERS
Recent

--------------------
Recent

RESONANCE
PARAMETERS MAY BE REPRESENTED USING ANY COMBINATION      Recent

OF THE REPRESENTATIONS
ALLOWED IN ENDF/B,
Recent

(1) RESOLVED
DATA
Recent

(A) SINGLE LEVEL BREIT-WIGNER
Recent

(B) MULTI-LEVEL BREIT-WIGNER
Recent

(C) ADLER-ADLER
Recent

(D) REICH-MOORE
Recent

(E) HYBRID R-FUNCTION                                          Recent

(2) UNRESOLVED
DATA
Recent

(A) ALL PARAMETERS ENERGY INDEPENDENT
Recent

(B) FISSION PARAMETERS ENERGY DEPENDENT
Recent

(C) ALL PARAMETERS ENERGY DEPENDENT
Recent

Recent

THE FOLLOWING
RESOLVED DATA FORMALISMS ARE NOT TREATED BY THIS     Recent

VERSION OF THE
CODE AND WILL ONLY BE IMPLEMENTED AFTER EVALUATIONS Recent

USING THESE
FORMALISMS ARE AVAILABLE TO THE AUTHOR OF THIS CODE    Recent

FOR TESTING IN
ORDER TO INSURE THAT THEY CAN BE HANDLED PROPERLY   Recent

(A) GENERAL R-MATRIX
Recent

Recent

CALCULATED CROSS
SECTIONS
Recent

-------------------------
Recent

THIS PROGRAM
WILL USE THE RESONANCE PARAMETERS TO CALCULATE THE    Recent

TOTAL, ELASTIC,
CAPTURE AND POSSIBLY FISSION CROSS SECTIONS. THE   Recent

COMPETITIVE
WIDTH WILL BE USED IN THESE CALCULATIONS, BUT THE      Recent

COMPETITIVE
CROSS SECTION ITSELF WILL NOT BE CALCULATED. THE
Recent

ENDF/B
CONVENTION IS THAT ALTHOUGH A COMPETITIVE WIDTH MAY BE      Recent

GIVEN, THE COMPETITIVE
CROSS SECTION MUST BE SEPARATELY TABULATED
Recent

AS A SECTION OF
FILE 3 DATA.
Recent

Recent

RESOLVED
REGION                                                    Recent

---------------
Recent

IN THE RESOLVED
REGION THE RESOLVED PARAMETERS ARE USED TO
Recent

CALCULATE COLD
(0 KELVIN), LINEARLY INTERPOLABLE, ENERGY DEPENDENT Recent

CROSS
SECTIONS.
Recent

Recent

SCATTERING
RADIUS
Recent

-----------------
Recent

FOR SINGLE OR
MULTI LEVEL BREIT-WIGNER PARAMETERS THE SCATTERING   Recent

RADIUS MAY BE
SPECIFIED IN EITHER ENERGY INDEPENDENT (CONSTANT)    Recent

OR ENERGY
DEPENDENT FORM (A TABLE OF ENERGY VS. RADIUS AND AN      Recent

ASSOCIATED
INTERPOLATION LAW). IN ALL OTHER CASE ONLY AN ENERGY    Recent

INDEPENDENT
SCATTERING RADIUS IS ALLOWED.
Recent

Recent

FOR ANY ONE
MATERIAL (I.E. MAT) IF ENERGY DEPENDENT SCATTERING     Recent

RADII ARE GIVEN
THE TOTAL NUMBER OF INTERPOLATION REGIONS AND      Recent

TABULATED VALUES
FOR THE ENTIRE MATERIAL CANNOT EXCEED,
Recent

200 -
INTERPOLATION REGIONS
Recent

500 - TABULATED
VALUES
Recent

IF THESE LIMITS ARE EXCEEDED THE PROGRAM
WILL PRINT AN ERROR
Recent

MESSAGE AND
TERMINATE.
Recent

Recent

IF YOU REQUIRE A
LARGER NUMBER OF INTERPOLATION REGION AND/OR      Recent

TABULATED
VALUES,
Recent

(1)
INTERPOLATION REGIONS - INCREASE THE DIMENSION OF NBTRHO AND   Recent

INTRHO IN
COMMON/TABRHO/ THROUGHOUT THE PROGRAM AND CHANGE MAXSEC  Recent

IN SUBROUTINE
RDAP (MAXSEC = MAXIMUM NUMBER OF INTERPOLATION
Recent

REGIONS).
Recent

(2) TABULATED
VALUES - INCREASE THE DIMENSION OF ERHOTB, RHOTAB    Recent

AND APTAB IN
COMMON/TABRHO/ THROUGHOUT THE PROGRAM AND CHANGE      Recent

MAXRHO IN
SUBROUTINE RDAP (MAXRHO = MAXIMUM NUMBER OF TABULATED    Recent

VALUES).
Recent

Recent

RESOLVED
REICH-MOORE AND MULTI-LEVEL BREIT-WIGNER PARAMETERS
Recent

------------------------------------------------------------
Recent

CROSS SECTIONS
FOR REICH-MOORE PARAMETERS ARE CALCULATED ACCORDING Recent

TO THE EQUATION
(1) - (8) OF SECTION D.1.3 OF ENDF-102. IN ORDER   Recent

TO CALCULATE
CROSS SECTIONS FROM MULTI-LEVEL PARAMETERS IN A
Recent

REASONABLE
AMOUNT OF TIME THIS PROGRAM EXPRESSES THE CROSS SECTION Recent

IN TERMS OF A
SINGLE SUM OVER RESONANCES (SEE, ENDF-102, SECTION   Recent

D.1.2, EQUATIONS
6-7), RATHER THAN AS A DOUBLE SUM (SEE, ENDF-102  Recent

SECTION D.1.2,
EQUATION 1-2). IN ORDER FOR THE ENDF-102 EQUATIONS  Recent

TO BE CORRECT
THE PARAMETERS MUST MEET THE FOLLOWING CONDITIONS,   Recent

Recent

(1) FOR EACH L STATE ALL
PHYSICALLY POSSIBLE J SEQUENCES MUST BE   Recent

PRESENT. ONLY IN THIS CASE WILL THE CONTRIBUTIONS OF THE       Recent

INDIVIDUAL J SEQUENCES ADD UP TO PRODUCE THE CORRECT POTENTIAL
Recent

SCATTERING CONTRIBUTION FOR THE L STATE (SEE, ENDF-102,
Recent

SECTION D.1.2, EQUATIONS 6-7). IF ANY J SEQUENCE IS MISSING    Recent

THE PROGRAM WILL PRINT A WARNING AND ADD THE J SEQUENCE WITH   Recent

NO RESONANCE PARAMETERS IN ORDER TO ALLOW THE POTENTIAL
Recent

SCATTERING TO BE CALCULATED CORRECTLY (THIS IS EQUIVALENT TO   Recent

ASSUMING THAT THE EVALUATOR REALIZES THAT ALL J SEQUENCES MUST
Recent

BE AND ARE PRESENT AND THAT THE EVALUATION STATES THAT THERE   Recent

ARE NO RESONANCES WITH CERTAIN PHYSICALLY POSSIBLE J VALUES...
Recent

IN THIS CASE POTENTIAL CONTRIBUTION MUST STILL BE CONSIDERED).
Recent

Recent

EXAMPLE
Recent

=======
Recent

AN EXAMPLE OF WHERE THIS OCCURS AND IS IMPORTANT TO CONSIDER   Recent

IS U-238 IN ENDF/B-IV AND V LIBRARIES WHERE FOR L=1 THERE IS   Recent

ONLY A J=1/2 SEQUENCE. NOT INCLUDING THE J=3/2 SEQUENCE LEADS  Recent

TO UNDERESTIMATING THE POTENTIAL SCATTERING AND PRODUCES
Recent

MINIMA IN THE ELASTIC CROSS SECTION WHICH ARE AN ORDER OF      Recent

MAGNITUDE LOWER THAN THE CROSS SECTIONS OBTAINED BE INCLUDING  Recent

THE J=3/2 SEQUENCE.
Recent

Recent

(2) FOR A GIVEN
TARGET SPIN AND L VALUE THERE MAY BE 2 POSSIBLE    Recent

MEANS OF OBTAINING THE SAME J VALUE. WHEN THIS OCCURS IN       Recent

ORDER TO CALCULATE THE CORRECT POTENTIAL SCATTERING CROSS      Recent

SECTION IT IS IMPORTANT TO INCLUDE THE EFFECT OF BOTH
Recent

POSSIBLE J SEQUENCES, EVEN THOUGH FROM THE ENDF/B DATA IT IS   Recent

NOT POSSIBLE TO DETERMINE WHICH OF THE 2 POSSIBLE SEQUENCES    Recent

ANY GIVEN RESONANCE BELONGS TO. IN THIS CASE THIS PROGRAM      Recent

TREAT ALL RESONANCES WITH THE SAME J VALUE AS BELONGING TO     Recent

THE SAME J SEQUENCE (TO ALLOW INTERFERENCE) AND WILL ADD AN    Recent

ADDITIONAL J SEQUENCE WITH NO RESONANCES IN ORDER TO ALLOW     Recent

THE POTENTIAL CROSS SECTION TO BE CALCULATED CORRECTLY. WHEN   Recent

THIS OCCURS A WARNING MESSAGE IS PRINTED, BUT BASED ON THE     Recent

ENDF/B DATA THERE IS NOTHING WRONG WITH THE DATA AND THERE IS  Recent

NOTHING THAT THE USER CAN DO TO CORRECT OR IN ANY WAY MODIFY   Recent

THE DATA TO ELIMINATE THE PROBLEM.
Recent

Recent

EXAMPLE
Recent

=======
Recent

FOR A TARGET SPIN =1 AND L=1 THE 2 RANGES OF PHYSICALLY
Recent

POSSIBLE J ARE 1/2, 3/2, 5/2 AND 1/2, 3/2. BY CHECKING THE     Recent

ENDF/B DATA IT IS POSSIBLE TO INSURE THAT THE 3 POSSIBLE
Recent

J VALUES (1/2, 3/2, 5/2) ARE PRESENT AND TO INCLUDE ALL 3      Recent

J SEQUENCES IN THE CALCULATIONS. HOWEVER, UNLESS ALL 5
Recent

POSSIBLE J SEQUENCES ARE INCLUDED THE STATISTICAL WEIGHTS      Recent

OF THE J SEQUENCES WILL NOT SUM UP TO 2*L+1 AND THE
Recent

POTENTIAL CROSS SECTION WILL BE UNDERESTIMATED. IN THIS
Recent

EXAMPLE THE SUM OF THE 3 J SEQUENCES 1/2, 3/2, 5/2 IS 2,       Recent

RATHER THAN 3 AS IT SHOULD BE FOR L=1, AND THE CONTRIBUTION    Recent

OF THE L=1 RESONANCES TO THE POTENTIAL SCATTERING CROSS
Recent

SECTION WILL ONLY BE 2/3 OF WHAT IT SHOULD BE, UNLESS THE      Recent

OTHER 2 J SEQUENCES (WITH
DUPLICATE J VALUES) ARE INCLUDED     Recent

IN THE CALCULATION.
Recent

Recent

(3) EACH RESONANCE
MUST HAVE AN ASSIGNED, PHYSICALLY POSSIBLE      Recent

J VALUE. PHYSICALLY IMPOSSIBLE OR AVERAGE J VALUES CANNOT BE   Recent

UNIQUELY INTERPRETED USING THE EQUATIONS IN ENDF-102 AND       Recent

THEIR USE WILL USUALLY RESULT IN PHYSICALLY UNRELIABLE CROSS   Recent

SECTIONS. THIS PROGRAM WILL CHECK ALL J VALUES AND IF ANY ARE  Recent

ARE FOUND TO BE PHYSICALLY IMPOSSIBLE (BASED ON TARGET SPIN    Recent

AND L VALUE) AN ERROR MESSAGE WILL BE PRINTED TO INDICATE THAT
Recent

THE RECONSTRUCTED CROSS SECTIONS WILL BE UNRELIABLE AND THE    Recent

PROGRAM WILL CONTINUE. IN AN ATTEMPT TO CALCULATE THE CORRECT  Recent

POTENTIAL SCATTERING CROSS SECTION THIS PROGRAM WILL SUBTRACT  Recent

THE POTENTIAL SCATTERING CONTRIBUTION DUE TO ALL FICTICIOUS J  Recent

SEQUENCES AND ADD THE CONTRIBUTION OF ALL PHYSICALLY POSSIBLE  Recent

J SEQUENCES (AS DESCRIBED ABOVE).
Recent

Recent

WARNING (LET THE USER BEWARE)
Recent

=============================
Recent

(A) IT CANNOT BE STRESSED ENOUGH THAT CROSS SECTIONS OBTAINED  Recent

USING PHYSICALLY IMPOSSIBLE J VALUES FOR REICH-MOORE AND   Recent

MULTI-LEVEL BREIT-WIGNER RESONANCE PARAMETERS WILL RESULT  Recent

IN UNRELIABLE CROSS SECTIONS. THE DECISION TO HAVE THIS    Recent

PROGRAM CONTINUE TO PROCESS WHEN THIS CONDITION IS FOUND   Recent

IS BASED ON AN ATTEMPT TO ALLOW THE USER TO AT LEAST HAVE  Recent

SOME
RESULTS (HOWEVER BAD THEY MAY BE) IF THERE IS NO      Recent

OTHER EVALUATED DATA AVAILABLE.
Recent

(B) EVEN THOUGH THE REICH-MOORE AND MULTI-LEVEL EQUATIONS ARE  Recent

DEFINED AS ABSOLUTE OR SQUARED CONTRIBUTIONS WHICH MUST    Recent

ALL BE PHYSICALLY POSSIBLE, ATTEMPTING TO CORRECT THE      Recent

POTENTIAL CROSS SECTION (AS DESCRIBED ABOVE) CAN LEAD TO   Recent

NEGATIVE ELASTIC CROSS SECTIONS. THIS IS BECAUSE BASED ON  Recent

THE INFORMATION AVAILABLE IN THE EVALUATION IT IS NOT      Recent

NOT POSSIBLE TO CORRECTLY ACCOUNT FOR THE INTERFERENCE     Recent

BETWEEN THE RESONANCE AND POTENTIAL CONTRIBUTIONS FOR EACH Recent

J SEQUENCE.
Recent

Recent

UNRESOLVED
RESONANCE REGION
Recent

---------------------------
Recent

IN THE
UNRESOLVED RESONANCE REGION THE UNRESOLVED PARAMETERS
Recent

ARE USED TO
CALCULATE INFINITELY DILUTE AVERAGE CROSS SECTIONS.    Recent

NOTE, IT IS
IMPORTANT TO UNDERSTAND THAT FROM THE DEFINITION OF    Recent

THE UNRESOLVED
PARAMETERS IT IS NOT POSSIBLE TO UNIQUELY CALCULATE Recent

ENERGY DEPENDENT
CROSS SECTIONS. ONLY AVERAGES OR DISTRIBUTIONS    Recent

MAY BE
CALCULATED.
Recent

Recent

UNRESOLVED
INTERPOLATION
Recent

------------------------
Recent

IN THE
UNRESOLVED RESONANCE REGION CROSS SECTIONS AT EACH ENERGY   Recent

ARE CALCULATED
BY INTERPOLATING PARAMETERS. THIS IS THE CONVENTION Recent

USED IN ENDF/B-IV AND EARLIER VERSIONS OF
ENDF/B. THE ENDF/B-V
Recent

CONVENTION OF
INTERPOLATING CROSS SECTIONS, NOT PARAMETERS, HAS    Recent

BEEN ABANDONED
AS IMPRACTICAL SINCE IT CAN LEAD TO THE SITUATION   Recent

WHERE EXACTLY
THE SAME PHYSICAL DATA CAN LEAD TO DIFFERENT RESULTS Recent

DEPENDING ON
WHICH OF THE THREE ENDF/B UNRESOLVED PARAMTER FORMATS Recent

IS USED. FOR
EXAMPLE, GIVEN A SET OF ENERGY INDEPENDENT UNRESOLVED Recent

PARAMETERS IT IS
POSSIBLE TO CODE THESE PARAMETERS IN EACH OF THE  Recent

THREE ENDF/B
UNRESOLVED PARAMETER FORMATS. SINCE PHYSICALLY WE     Recent

ONLY HAVE ONE
SET OF PARAMETERS WE WOULD EXPECT THE RESULTS TO BE  Recent

INDEPENDENT OF
HOW THEY ARE REPRESENTED IN ENDF/B. UNFORTUNATELY   Recent

USING THE
ENDF/B-V CONVENTION TO INTERPOLATE CROSS SECTIONS CAN    Recent

LEAD TO THREE
COMPLETELY DIFFERENT RESULTS. IN CONTRAST USING THE  Recent

ENDF/B-IV AND
EARLIER CONVENTION OF INTERPOLATING PARAMETERS LEADS Recent

TO COMPLETELY
CONSISTENT RESULTS.
Recent

Recent

INTERNAL
REPRESENTATION OF UNRESOLVED PARAMETERS                   Recent

------------------------------------------------
Recent

ANY OF THE THREE
POSSIBLE REPRESENTATIONS OF UNRESOLVED PARAMETERS Recent

CAN BE UNIQUELY
REPRESENTED IN THE ALL PARAMETERS ENERGY DEPENDENT Recent

REPRESENTATIONS
WITH THE APPROPRIATE (ENDF/B VERSION DEPENDENT)    Recent

INTERPOLATION
LAW. THIS IS DONE BY THE PROGRAM WHILE READING THE   Recent

UNRESOLVED
PARAMETERS AND ALL SUBSEQUENT CALCULATIONS NEED ONLY    Recent

CONSIDER THE ALL
PARAMETERS ENERGY DEPENDENT REPRESENTATION.
Recent

Recent

RESONANCE
RECONSTRUCTION STARTING ENERGY GRID
Recent

---------------------------------------------
Recent

AS IN ANY
ITERATIVE METHOD THE WAY TO SPEED CONVERGENCE IS TO TRY  Recent

TO START CLOSE
TO THE ANSWER. THIS PROGRAM ATTEMPTS TO DO THIS BY  Recent

STARTING FROM AN
ENERGY GRID WHICH IS A GOOD APPROXIMATION TO A    Recent

SIMPLE
BREIT-WIGNER LINE SHAPE,
Recent

Recent

SIGMA(X)=1.0/(1.0+X*X)
Recent

Recent

WHERE X IS THE
DISTANCE FROM THE PEAK IN HALF-WIDTHS
Recent

Recent

SUBROUTINE
SUBINT HAS A BUILT-IN TABLE OF NODES WHICH ARE THE      Recent

HALF-WIDTH
MULTIPLES TO APPROXIMATE THE SIMPLE BREIT-LINE SHAPE    Recent

TO WITHIN 1
PER-CENT OVER THE ENTIRE INTERVAL 0 TO 500 HALF-WIDTHS Recent

Recent

BETWEEN ANY TWO
RESOLVED RESONANCES THE STARTING GRID IS BASED ON  Recent

THE HALF-WIDTHS
OF THE TWO RESONANCES. FROM THE LOWER ENERGY
Recent

RESONANCE UP TO
THE MID-POINT BETWEEN THE RESONANCES (MID-POINT    Recent

IS DEFINED HERE
AS AN EQUAL NUMBER OF HALF-WIDTHS FROM EACH
Recent

RESONANCE) THE
HALF-WIDTH OF THE LOWER ENERGY RESONANCE IS USED.   Recent

FROM THE
MID-POINT UP TO THE HIGHER ENERGY RESONANCE THE HALF-     Recent

WIDTH OF THE
UPPER ENERGY RESONANCE IS USED.
Recent

Recent

WITH THIS
ALOGORITHM CLOSELY SPACED RESONANCES WILL HAVE ONLY      Recent

A FEW STARTING
NODES PER RESONANCE (E.G. U-235). WIDELY SPACED     Recent

RESONANCES WILL
HAVE MORE NODES PER RESONANCE (E.G. U-238). FOR    Recent

A MIX OF S, P, D ETC.
RESONANCES THIS ALOGORITHM GUARANTEES AN     Recent

ADEQUTE
DESCRIPTION OF THE PROFILE OF EVEN EXTREMELY NARROW
Recent

RESONANCES
(WHICH MAY IMMEDIATELY CONVERGENCE TO THE ACCURACY      Recent

REQUESTED, THUS
MINIMIZING ITERATION).
Recent

Recent

BACKGROUND CROSS
SECTIONS
Recent

-------------------------
Recent

THE PROGRAM WILL
SEARCH FOR BACKGROUND CROSS SECTIONS FOR TOTAL    Recent

(MT=1), ELASTIC
(MT=2), FISSION (MT=18), FIRST CHANCE FISSION      Recent

(MT=19) AND
CAPTURE (MT=102).
Recent

Recent

(1) THE
BACKGROUND CROSS SECTIONS (FILE 3) CAN BE PRESENT OR NOT   Recent

PRESENT FOR EACH REACTION.                                     Recent

(2) IF FOR A
GIVEN REACTION THE BACKGROUND CROSS SECTION IS
Recent

PRESENT, IT WILL BE ADDED TO THE RESONANCE CONTRIBUTION AND    Recent

THE RESULT WILL BE OUTPUT.
Recent

(3) IF FOR A
GIVEN REACTION THE BACKGROUND IS NOT PRESENT THE      Recent

PROGRAM WILL,
Recent

(A) IF THE INPUT TO THE PROGRAM SPECIFIES NO OUTPUT FOR
Recent

REACTIONS WITH NO BACKGROUND THERE WILL BE NO OUTPUT.      Recent

(B) IF THE INPUT TO THE PROGRAM SPECIFIES OUTPUT FOR REACTIONS
Recent

WITH NO BACKGROUND,
Recent

(I) THE RESONANCE CONTRIBUTION TO TOTAL, ELASTIC OR
Recent

CAPTURE WILL BE OUTPUT.
Recent

(II) IF ALL FISSION RESONANCE PARAMETERS ARE ZERO THE      Recent

FISSION CROSS SECTION (MT=18) WILL NOT BE OUTPUT.     Recent

OTHERWISE THE RESONANCE CONTRIBUTION OF THE FISSION   Recent

(MT=18) WILL BE OUTPUT.
Recent

(III) THERE
WILL BE NO OUTPUT FOR FIRST CHANCE FISSION     Recent

(MT=19).
Recent

Recent

COMBINING RESONANCES
AND BACKGROUND CROSS SECTIONS
Recent

--------------------------------------------------
Recent

IN ORDER TO BE
COMBINED WITH THE RESONANCE CONTRIBUTION THE
Recent

BACKGROUND CROSS
SECTIONS MUST BE GIVEN AT 0 KELVIN TEMPERATURE    Recent

AND MUST BE
LINEARLY INTERPOLABLE. IF THESE CONDITIONS ARE MET     Recent

THE RESONANCE
AND BACKGROUND CONTRIBUTIONS WILL BE ADDED TOGETHER  Recent

AND OUTPUT. IF
THESE CONDITIONS ARE NOT MET THE BACKGROUND CROSS   Recent

SECTION WILL BE
IGNORED AND ONLY THE RESONANCE CONTRIBUTION WILL   Recent

BE OUTPUT. IF
THE BACKGROUND HAS NOT BEEN ADDED TO THE RESONANCE   Recent

CONTRIBUTION
AFTER THIS PROGRAM FINISHES THE USER CAN MAKE THE     Recent

RESONANCE AND
BACKGROUND CONTRIBUTIONS COMPATIBLE BY,
Recent

Recent

(1) IF THE
BACKGROUND IS NOT LINEARLY INTERPOABLE, LINEARIZE THE   Recent

BACKGROUND (E.G., USE PROGRAM LINEAR).
Recent

(2) IF THE
BACKGROUND IS NOT GIVEN AT 0 KELVIN, DOPPLER BROADEN    Recent

THE RESONANCE (NOT BACKGROUND) CONTRIBUTION TO THE SAME        Recent

TEMPERATURE AS THE BACKGROUND (E.G., USE PROGRAM SIGMA1).      Recent

Recent

ONCE THE
RESONANCE AND BACKGROUND CONTRIBUTIONS HAVE BEEN MADE     Recent

COMPATIBLE THEY
CAN BE ADDED TOGETHER (E.G., USE PROGRAM MIXER).   Recent

Recent

THE
RECONSTRUCTION OF THE RESONANCE CONTRIBUTION TO THE CROSS      Recent

SECTION CAN BE
QUITE EXPENSIVE (IN TERMS OF COMPUTER TIME). SINCE  Recent

THE
RECONSTRUCTION IS PERFORMED BEFORE THE BACKGROUND CROSS
Recent

SECTIONS ARE
READ, THE ABOVE CONVENTIONS HAVE BEEN ADOPTED IN      Recent

ORDER TO AVOID
LOSE OF COMPUTER TIME INVOLVED IN RECONSTRUCTING    Recent

THE RESONANCE
CONTRIBUTION.
Recent

Recent

COMMON ENERGY
GRID                                                 Recent

------------------
Recent

THIS PROGRAM
WILL RECONSTRUCT THE RESONANCE CONTRIBUTION TO THE    Recent

TOTAL, ELASTIC,
FISSION AND CAPTURE CROSS SECTIONS ALL ON THE      Recent

SAME ENERGY
GRID. EACH REACTION WILL THEN BE COMBINED WITH ITS     Recent

BACKGROUND CROSS
SECTION (IF ANY) AND OUTPUT WITHOUT ANY FURTHER   Recent

THINNING. IF
THERE ARE NO BACKGROUND CROSS SECTIONS, OR IF THE     Recent

BACKGROUND CROSS
SECTION FOR ALL FOUR REACTIONS ARE GIVEN ON A     Recent

COMMON ENERGY
GRID, THE OUTPUT FROM THIS PROGRAM WILL BE ON A      Recent

COMMON ENERGY
GRID FOR ALL FOUR REACTIONS.                         Recent

Recent

THERMAL
ENERGY
Recent

--------------
Recent

IF THE RESONANCE
REGION SPANS THERMAL ENERGY (0.0253 EV) THIS      Recent

POINT IS ALWAYS
INCLUDED IN THE COMMON ENERGY GRID USED FOR ALL    Recent

REACTIONS AND
WILL ALWAYS APPEAR IN THE OUTPUT DATA.
Recent

Recent

SECTION
SIZE
Recent

------------
Recent

SINCE THIS PROGRAM
USES A LOGICAL PAGING SYSTEM THERE IS NO LIMIT  Recent

TO THE NUMBER OF
POINTS IN ANY SECTION, E.G., THE TOTAL CROSS      Recent

SECTION MAY BE
REPRESENTED BY 200,000 DATA POINTS.
Recent

Recent

SELECTION OF
DATA
Recent

-----------------
Recent

THE PROGRAM
SELECTS MATERIALS TO BE PROCESSED BASED EITHER ON      Recent

MAT (ENDF/B MAT
NO.) OR ZA. THE PROGRAM ALLOWS UP TO 100 MAT OR    Recent

ZA RANGES TO BE
SPECIFIED. THE PROGRAM WILL ASSUME THAT THE
Recent

ENDF/B TAPE IS
IN EITHER MAT OR ZA ORDER, WHICHEVER CRITERIA IS    Recent

USED TO SELECT
MATERIALS, AND WILL TERMINATE WHEN A MAT OR ZA      Recent

IS FOUND THAT IS
ABOVE THE RANGE OF ALL REQUESTS.
Recent

Recent

ALLOWABLE
ERROR
Recent

---------------
Recent

THE
RECONSTRUCTION OF LINEARLY INTERPOLABLE CROSS SECTIONS FROM    Recent

RESONANCE
PARAMETERS CANNOT BE PERFORMED EXACTLY. HOWEVER IT CAN   Recent

BE PERFORMED TO
VIRTUALLY ANY REQUIRED ACCURACY AND MOST
Recent

IMPORTANTLY CAN
BE PERFORMED TO A TOLERANCE THAT IS SMALL COMPARED Recent

TO THE
UNCERTAINTY IN THE CROSS SECTIONS THEMSELVES. AS SUCH THE   Recent

CONVERSION OF
CROSS SECTIONS TO LINEARLY INTERPOLABLE FORM CAN BE  Recent

PERFORMED WITH
ESSENTIALLY NO LOSS OF INFORMATION.
Recent

Recent

THE ALLOWABLE
ERROR MAY BE ENERGY INDEPENDENT (CONSTANT) OR ENERGY Recent

DEPENDENT. THE
ALLOWABLE ERROR IS DESCRIBED BY A TABULATED
Recent

FUNCTION OF UP TO 20
(ENERGY,ERROR) PAIRS AND LINEAR INTERPOLATION Recent

BETWEEN
TABULATED POINTS. IF ONLY ONE TABULATED POINT IS GIVEN THE Recent

ERROR WILL BE
CONSIDERED CONSTANT OVER THE ENTIRE ENERGY RANGE.    Recent

WITH THIS ENERGY
DEPENDENT ERROR ONE MAY OPTIMIZE THE OUTPUT FOR   Recent

ANY GIVEN
APPLICATION BY USING A SMALL ERROR IN THE ENERGY RANGE   Recent

OF INTEREST AND
A LESS STRINGENT ERROR IN OTHER ENERGY RANGES,     Recent

E.G., 0.1 PER-CENT
FROM 0 UP TO THE LOW EV RANGE AND A LESS
Recent

STRINGENT
TOLERANCE AT HIGHER ENERGIES.
Recent

Recent

DEFAULT
ALLOWABLE ERROR                                            Recent

-----------------------
Recent

IN ORDER TO
INSURE CONVERENCE OF THE RESONANCE RECONSTRUCTION THE  Recent

ALLOWABLE ERROR
MUST BE POSITIVE. IF THE USER INPUTS AN ERROR FOR  Recent

RESONANCE
RECONSTRUCTION THAT IS NOT POSITIVE IT WILL BE SET TO    Recent

THE DEFAULT
VALUE (CURRENTLY 0.1 PER-CENT) AND INDICATED AS SUCH   Recent

IN THE OUTPUT
LISTING.
Recent

Recent

INTERVAL HALVING
ALGORITHM
Recent

-------------------------
Recent

THIS PROGRAM
WILL START BY CALCULATING THE CROSS SECTIONS AT THE   Recent

ENERGIES
CORRESPONDING TO THE PEAK OF EACH RESONANCE, AS WELL AS   Recent

A FIXED NUMBER
OF HALF-WIDTHS ON EACH SIDE OF EACH RESONANCE.      Recent

STARTING FROM
THIS BASIC GRID OF POINTS THE PROGRAM WILL CONTINUE  Recent

TO HALF EACH
INTERVAL UNTIL THE CROSS SECTIONS FOR ALL REACTIONS   Recent

AT THE CENTER OF
THE INTERVAL CAN BE DEFINED BY LINEAR
Recent

INTERPOLATION
FROM THE ENDS OF THE INTERVAL TO WITHIN THE USER     Recent

SPECIFIED
ACCURACY CRITERIA.
Recent

Recent

DISTANT
RESONANCE TREATMENT
Recent

---------------------------
Recent

THE OPTION TO
TREAT DISTANT RESONANCES, WHICH WAS AVAILABLE IN     Recent

EARLIER VERSIONS
OF THIS PROGRAM, IS NO LONGER AVAILABLE, BECAUSE  Recent

IT WAS FOUND TO
PRODUCE UNRELIABLE RESULTS. IN THIS VERSION OF     Recent

THE PROGRAM ALL
RESONANCES ARE TREATED EXACTLY.
Recent

Recent

PROGRAM
OPERATION
Recent

==================================================================
Recent

EDIT MODE
Recent

---------
Recent

IT IS SUGGESTED
THAT BEFORE RUNNING THIS PROGRAM TO RECONSTRUCT    Recent

CROSS SECTIONS
FROM RESONANCE PARAMETERS (WHICH CAN BE QUITE
Recent

EXPENSIVE) THE
USER FIRST RUN THE PROGRAM IN THE EDIT MODE (SEE,   Recent

DESCRIPTION OF
INPUT PARAMETERS BELOW). IN THE EDIT MODE THE
Recent

PROGRAM WILL
READ, LIST AND EXTENSIVELY CHECK THE CONSISTENCY OF   Recent

ALL RESONANCE
PARAMETERS AND ENDF/B DEFINED RESONANCE FLAGS. THIS  Recent

IS A VERY
INEXPENSIVE MEANS OF CHECKING ALL DATA BEFORE INVESTING  Recent

A LARGE AMOUNT
OF MONEY IN RECONSTRUCTING CROSS SECTIONS. ANY AND  Recent

ALL DIGNOSTICS
RECEIVED FROM THE EDIT WILL SUGGEST HOW TO CORRECT  Recent

THE EVALUATED
DATA TO MAKE IT CONSISTENT BEFORE RECONSTRUCTING     Recent

CROSS SECTIONS.
IN ORDER TO OBTAIN MEANINGFUL RESULTS FROM THE     Recent

RECONSTRUCTION
ALL SUGGESTED CHANGES TO THE EVALUATION SHOULD BE   Recent

PERFORMED BEFORE
TRYING RECONSTRUCTION (OTHERWISE THE RESULT OF    Recent

RECONSTRUCTION
WILL NOT BE RELIABLE).
Recent

Recent

RECONSTRUCTION
MODE
Recent

-------------------
Recent

FOR EACH REQUESTED
MATERIAL
Recent

---------------------------
Recent

IF SECTION MF=1,
MT=451 IS PRESENT COMMENTS WILL BE ADD TO
Recent

DOCUMENT THAT
THE MATERIAL HAS BEEN PROCESSED. MF=1, MT=451 WILL   Recent

ALSO BE USED TO
DETERMINE THE VERSION OF THE ENDF/B FORMAT WHICH   Recent

WILL ALLOW THE
PROGRAM TO USE THE APPROPRIATE CONVENTIONS.
Recent

Recent

ALL OF THE FILE
2 RESONANCE PARAMETERS ARE FIRST READ AND THE      Recent

LINEARLY
INTERPOLABLE CONTRIBUTION OF THE RESONANCE PARAMETERS     Recent

TO THE TOTAL,
ELASTIC, CAPTURE AND FISSION CROSS SECTIONS IS
Recent

CALCULATED
SIMULTANEOUSLY USING A COMMON ENERGY GRID FOR ALL
Recent

FOUR
REACTIONS.
Recent

Recent

AFTER THE
RESONANCE CONTRIBUTION HAS BEEN RECONSTRUCTED EACH OF    Recent

THE FIVE
REACTIONS (MT=1, 2, 18, 19, 102) IS CONSIDERED SEPARATELY Recent

FOR COMBINATION
WILL THE BACKGROUND CROSS SECTION, IF ANY, AS      Recent

DESCRIBED
ABOVE.
Recent

Recent

OUTPUT WILL
INCLUDE THE ENTIRE EVALUATION, INCLUDING RESONANCES    Recent

PARAMETERS WITH
LRU MODIFIED (AS DESCRIBED ABOVE) TO INDICATE      Recent

THAT THE
RESONANCE CONTRIBUTION HAS ALREADY BEEN ADDED TO THE      Recent

FILE 3 CROSS
SECTIONS.
Recent

Recent

THE CYCLE OF
RECONSTRUCTING THE RESONANCE CONTRIBUTION AND ADDING  Recent

THE BACKGROUND
WILL BE REPEATED FOR EACH MATERIAL REQUESTED.
Recent

Recent

PROCESS ONLY A
PORTION OF RESONANCE REGION
Recent

==================================================================
Recent

MODERN
EVALUATIONS MAY BE EXTREMELY LARGE AND IT MAY NOT BE
Recent

POSSIBLE TO
PROCESS AN ENTIRE EVALUATION (I.E., ADD THE RESONANCE  Recent

CONTRIBUTION)
DURING A SINGLE COMPUTER RUN.
Recent

Recent

ALSO IN THE CASE
WHERE YOU ARE ONLY INTERESTED IN THE CROSS
Recent

SECTIONS OVER A
SMALL ENERGY RANGE, YOU MAY NOT WANT TO PROCESS    Recent

AN ENTIRE
EVALUATION, E.G., IF YOU ONLY WANT TO KNOW WHAT THE      Recent

CROSS SECTIONS
ARE NEAR THERMAL ENERGY, 0.0253 EV.
Recent

Recent

IN ORDER TO
ALLOW AN EVALUATION TO BE PROCESSED USING A NUMBER OF  Recent

SHORTER COMPUTER
RUNS AN OPTION HAS BEEN ADDED TO THIS PROGRAM TO  Recent

ALLOW THE USER
TO SPECIFY THE ENERGY RANGE TO BE PROCESSED.
Recent

Recent

USING THIS
OPTION YOU MAY START AT THE LOWEST ENERGY (ZERO UP TO   Recent

SOME ENERGY) AND
USE THE RESULTS OF THIS RUN AS INPUT TO THE
Recent

NEXT RUN, WHERE
YOU CAN SPECIFY THE NEXT ENERGY RANGE. THIS        Recent

CYCLE CAN BE
REPEATED UNTIL YOU HAVE PROCESSED THE ENTIRE
Recent

EVALUATION.
Recent

Recent

WARNING - THIS OPTION
SHOULD BE USED WITH EXTREME CARE - THIS      Recent

OPTION HAS BEEN
RELUCTANTLY ADDED - RELUCTANTLY BECAUSE IT CAN     Recent

BE EXTREMELY
DANGEROUS TO USE THIS OPTION UNLESS YOU CAREFULLY     Recent

CHECKED WHAT YOU
ARE DOING.
Recent

Recent

THE OPTION
SHOULD ONLY BE USED AS FOLLOWS,
Recent

1) YOU MUST
PROCESS USING ENERGY RANGES STARTING AT LOW ENERGY     Recent

AND WORKING YOUR WAY TOWARD HIGH ENERGY, E.G.,
Recent

0.0   TO  3.0+3
Recent

3.0+3 TO 10.0+3
Recent

10.0+3 TO 80.0+3, ETC.
Recent

2) FOR THE LAST
ENERGY RANGE THE LOWER ENERGY LIMIT MUST BE
Recent

NON-ZERO (WHERE TO START) AND THE UPPER ENERGY LIMIT MUST
Recent

BE ZERO (NO LIMIT)
Recent

80.0+3 TO  0.0
Recent

Recent

IF YOU ARE ONLY
INTERESTED IN THE CROSS SECTION OVER A NARROW      Recent

ENERGY INTERVAL
AND DO NOT INTENT TO MAKE ANY OTHER USE OF THE     Recent

RESULTS, YOU CAN
IGNORE THESE WARNINGS AND MERELY SPECIFY ANY      Recent

ENERGY INTERVAL
OVER WHICH YOU WISH CALCULATIONS TO BE
Recent

PERFORMED.
Recent

Recent

NORMALLY WHEN
THIS PROGRAM PROCESSES AN EVALUATION IT WILL SET     Recent

FLAGS IN THE
EVALUATION TO PREVENT THE SAME RESONANCE
Recent

CONTRIBUTION
FROM BEING ADDED TO THE CROSS SECTION MORE THAN
Recent

ONCE, SHOULD YOU USE
THE OUTPUT FROM THIS PROGRAM AS INPUT TO      Recent

THE
PROGRAM.
Recent

Recent

WHEN PROCESSING
ONLY PORTIONS OF THE RESONANCE REGION THIS
Recent

PROGRAM CANNOT
SET THESE FLAGS TO PROTECT AGAINST ADDING THE
Recent

RESONANCE
CONTRIBUTION MORE THAN ONCE - WHICH MAKES USE OF
Recent

THIS OPTION EXTREMELY
DANGEROUS.
Recent

Recent

ONLY YOU CAN
CHECK TO MAKE SURE THAT YOU HAVE CORRECTLY
Recent

INCLUDED EACH
ENERGY RANGE ONLY ONCE - SEE THE COMMENT LINES
Recent

AT THE END OF
SECTION, MF=1, MT=451, FOR A COMPLETE RECORD
Recent

OF EACH RUN
USING THIS PROGRAM. THIS SECTION WILL CONTAIN
Recent

LINES OF THE
FORM
Recent

Recent

***************** PROGRAM RECENT (VERSION 2007-1) *************    Recent

ONLY
PROCESS  0.00000+ 0 TO  3.00000+ 3 EV                         Recent

***************** PROGRAM RECENT (VERSION 2007-1) *************    Recent

ONLY
PROCESS  3.00000+ 3 TO  1.00000+ 4 EV
Recent

***************** PROGRAM RECENT (VERSION 2007-1) *************    Recent

ONLY
PROCESS  1.00000+ 4 TO  8.00000+ 4 EV
Recent

***************** PROGRAM RECENT (VERSION 2007-1) *************    Recent

ONLY
PROCESS  8.00000+ 4 TO  2.00000+ 7 EV
Recent

Recent

YOU SHOULD CHECK
TO INSURE THAT THERE ARE NO OVERLAPPING ENERGY    Recent

RANGES OR
MISSING ENERGY RANGES.
Recent

Recent

WHEN YOU
INDICATE BY INPUT THAT YOU ARE ABOUT TO PROCESS THE
Recent

LAST ENERGY
RANGE (SEE ABOVE, LOWER ENERGY LIMIT = NON-ZERO,
Recent

UPPER ENERGY
LIMIT = ZERO), THIS PROGRAM WILL ASSUME THAT
Recent

YOU HAVE NOW
COMPLETED ALL PROCESSING - AND ONLY THEN WILL
Recent

IT SET FLAGS IN
THE EVALUATION TO PREVENT THE RESONANCE
Recent

CONTRIBUTION FROM
BEING ADDED MORE THAN ONCE. FOR THIS REASON      Recent

YOU CANNOT
PROCESS STARTING WITH ENERGY INTERVALS AT HIGH
Recent

ENERGY AND
WORKING TOWARD LOW ENERGY - YOU MUST START AT LOW
Recent

ENERGY AND WORK
TOWARD HIGH ENERGY.
Recent

Recent

I/O FILES
Recent

==================================================================
Recent

INPUT FILES
Recent

-----------
Recent

UNIT  DESCRIPTION
Recent

----  -----------
Recent

2   INPUT LINE (BCD - 80
CHARACTERS/RECORD)
Recent

10   ORIGINAL ENDF/B DATA (BCD - 80
CHARACTERS/RECORD)
Recent

Recent

OUTPUT
FILES
Recent

------------
Recent

UNIT  DESCRIPTION
Recent

----  -----------
Recent

3   OUTPUT REPORT (BCD -
120 CHARACTERS/RECORD)
Recent

11   FINAL ENDF/B DATA (BCD - 80
CHARACTERS/RECORD)
Recent

Recent

SCRATCH
FILES
Recent

-------------
Recent

UNIT  DESCRIPTION
Recent

----  -----------
Recent

12   SCRATCH FILE FOR DATA
RECONSTRUCTED FROM RESONANCE
Recent

PARAMETERS (BINARY - 100200 WORDS/RECORD)
Recent

14   SCRATCH FILE FOR COMBINED FILE 2
AND 3 DATA
Recent

(BINARY - 40080 WORDS/RECORD)
Recent

Recent

OPTIONAL
STANDARD FILE NAMES (SEE SUBROUTINE FILEIO)
Recent

==================================================================
Recent

UNIT  FILE NAME
Recent

----  ----------
Recent

2   RECENT.INP
Recent

3   RECENT.LST
Recent

10   ENDFB.IN
Recent

11   ENDFB.OUT
Recent

12   (SCRATCH)
Recent

14   (SCRATCH)
Recent

Recent

INPUT CARDS
Recent

==================================================================
Recent

LINE  COLS.  FORMAT  DESCRIPTION
Recent

----  -----  ------  -----------
Recent

1    1-11    I11   RETRIEVAL CRITERIA (0=MAT,
1=ZA)
Recent

THIS OPTION DEFINED WHETHER COLUMNS 1-22 OF   Recent

SUBSEQUENT
INPUT CARDS SHOULD BE INTERPRETED
Recent

TO BE MAT OR ZA RANGES.
Recent

12-22   E11.4  FILE 2 MINIMUM ABSOLUTE CROSS SECTION
Recent

(IF
1.0E-10 OR LESS IS INPUT THE PROGRAM      Recent

WILL USE 1.0E-10)
Recent

23-33    I11   TREATMENT OF REACTIONS FOR WHICH BACKGROUND   Recent

CROSS SECTION IS NOT
GIVEN.
Recent

= 0 - IGNOR (I.E. NO OUTPUT)
Recent

= 1 - OUTPUT RESONANCE CONTRIBUTION.
Recent

THIS OPTION IS USEFUL WITH PARTIAL EVALUATION Recent

(E.G. ENDF/B-V DOSIMETRY LIBRARY) WHERE ONLY  Recent

ONE OR MORE OF THE REACTIONS ARE OF ACTUAL    Recent

INTEREST.
Recent

WARNING...THE USE OF THIS FIELD HAS BEEN      Recent

CHANGED. THIS FIELD WAS PREVIOUSLY USED TO    Recent

DEFINE THE PRECISION OF THE CALCULATION AND   Recent

OUTPUT. THE FORMER DEFINITION OF THIS FIELD   Recent

WAS...
Recent

MINIMUM ENERGY SPACING FLAG
Recent

= 0 - 6 DIGIT MINIMUM ENERGY SPACING.
Recent

STANDARD 6 DIGIT E11.4 OUTPUT.
Recent

= 1 - 9 DIGIT MINIMUM ENERGY SPACING.
Recent

STANDARD 6 DIGIT E11.4 OUTPUT.
Recent

= 2 - 9 DIGIT MINIMUM ENERGY SPACING.
Recent

VARIABLE 9 DIGIT F FORMAT OUTPUT.
Recent

FROM
EXPERIENCE IT HAS BEEN FOUND THAT
Recent

FAILURE TO SET THIS OPTION TO 2 CAN RESULT    Recent

IN LARGE ERRORS IN THE FINAL DATA. THEREFORE  Recent

INTERNALLY
THIS OPTION IS SET TO 2.
Recent

34-44    I11   OPERATING MODE
Recent

= 0 - CACULATE. MINIMUM OUTPUT LISTING
Recent

= 1 -
CACULATE. LIST ALL RESONANCE PARAMETERS Recent

= 2 - EDIT MODE. NO CALCULATION. LIST ALL     Recent

RESONANCE PARAMETERS.
Recent

NOTE, THE EDIT MODE (=2) IS THE SUGGESTED     Recent

MODE TO FIRST TEST THE CONSISTENCY OF THE     Recent

EVALUATED DATA, BEFORE RECONSTRUCTING CROSS   Recent

SECTIONS (SEE, COMMENTS ABOVE).
Recent

45-55    I11   NEGATIVE CROSS SECTIOIN TREATMENT
Recent

= 0 - O.K. - NO CHANGE
Recent

= 1 - SET = 0
Recent

56-66    I11   MONITOR MODE SELECTOR
Recent

= 0 - NORMAL OPERATION
Recent

= 1 - MONITOR PROGRESS OF RECONSTRUCTION OF   Recent

FILE 2 DATA AND COMBINING FILE 2 AND    Recent

FILE 3 DATA. EACH TIME A PAGE OF DATA   Recent

POINTS IS WRITTEN TO A SCRATCH FILE     Recent

PRINT OUT THE TOTAL NUMBER OF POINTS    Recent

ON SCRATCH AND THE LOWER AND UPPER      Recent

ENERGY LIMITS OF THE PAGE (THIS OPTION  Recent

MAY BE USED IN ORDER TO MONITOR THE     Recent

EXECUTION SPEED OF LONG RUNNING JOBS).  Recent

2    1-60    A60   ENDF/B INPUT DATA FILENAME
Recent

(STANDARD
OPTION = ENDFB.IN)
Recent

3    1-60    A60   ENDF/B OUTPUT DATA FILENAME
Recent

(STANDARD OPTION = ENDFB.OUT)
Recent

4-N    1-11    I11   MINIMUM MAT OR ZA (SEE COLS. 1-11,
LINE 1)    Recent

12-22    I11   MAXIMUM MAT OR ZA (SEE COLS. 1-11,
LINE 1)    Recent

UP TO 100 MAT OR ZA RANGES MAY BE SPECIFIED,  Recent

ONE RANGE PER LINE. THE LIST IS TERMINATED    Recent

BY A BLANK LINE. IF THE THE UPPER LIMIT OF    Recent

ANY REQUEST IS LESS THAN THE LOWER LIMIT THE  Recent

UPPER LIMIT WILL BE SET EQUAL TO THE LOWER    Recent

LIMIT. IF THE FIRST REQUEST LINE IS BLANK IT  Recent

WILL TERMINATE THE REQUEST LIST AND CAUSE ALL Recent

DATA TO BE RETRIEVED (SEE EXAMPLE INPUT).     Recent

23-33   E11.4  LOWER ENERGY LIMIT FOR PROCESSING.
Recent

34-44   E11.4  UPPER ENERGY LIMIT FOR PROCESSING.
Recent

*THE LOWER AND UPPER ENERGY LIMITS MUST BE     Recent

ZERO, OR BLANK, UNLESS YOU WISH TO ONLY
Recent

PROCESS A PORTION OF RESONANCE REGIONS.
Recent

*THESE ENERGY LIMITS ARE ONLY READ FROM THE    Recent

FIRST MAT/ZA REQUEST LINE
Recent

*IF BOTH ARE ZERO (OR BLANK) THE ENTIRE
Recent

RESONANCE REGION FOR EACH MATERIAL WILL BE    Recent

PROCESSED
Recent

*IF LIMITS ARE INPUT ONLY THAT PORTION OF THE  Recent

RESONANCE REGION FOR EACH MATERIAL WHICH      Recent

LIES
BETWEEN THESE LIMITS WILL BE PROCESSED   Recent

*SEE INSTRUCTIONS ABOVE BEFORE USING THIS      Recent

OPTION.
Recent

VARY   1-11   E11.4  ENERGY FOR FILE 2 ERROR LAW     (  SEE   )    Recent

12-22   E11.4  ERROR FOR FILE 2 ERROR LAW      (COMMENTS)    Recent

( BELOW  )    Recent

Recent

NOTE, THIS
VERSION OF THE PROGRAM DOES NOT THIN THE COMBINED FILE  Recent

FILE 2 + 3 DATA.
AS SUCH THE ERROR LAW FOR COMBINING FILE 2 + 3    Recent

WHICH WAS
REQUIRED IN EARLIER VERSIONS OF THIS CODE ARE NO LONGER  Recent

REQUIRED.
Recent

Recent

THE FILE 2 ERROR
LAW MAY BE ENERGY INDEPENDENT (DEFINED BY A
Recent

SINGLE ERROR) OR
ENERGY DEPENDENT (DEFINED BY UP TO 20 ENERGY,     Recent

ERROR PAIRS).
FOR THE ENERGY DEPENDENT CASE LINEAR INTERPOLATION   Recent

WILL BE USED TO
DEFINE THE ERROR AT ENERGIES BETWEEN THOSE AT      Recent

WHICH THE ERROR
IS TABULATED. THE ERROR LAW IS TERMINATED BY A     Recent

BLANK LINE. IF
ONLY ONE ENERGY, ERROR PAIR IS GIVEN THE LAW WILL   Recent

BE CONSIDERED TO
BE ENERGY INDEPENDENT. IF MORE THAN ONE PAIR      Recent

IS GIVEN IT BE
CONSIDERED TO BE ENERGY DEPENDENT (NOTE, THAT
Recent

FOR A CONSTANT
ERROR THE ENERGY INDEPENDENT FORM WILL RUN FASTER.  Recent

HOWEVER, FOR
SPECIFIC APPLICATIONS AN ENERGY DEPENDENT ERROR MAY   Recent

BY USED TO MAKE
THE PROGRAM RUN CONSIDERABLE FASTER).
Recent

Recent

ALL ENERGIES
MUST BE IN ASCENDING ENERGY ORDER. FOR CONVERGENCE    Recent

OF THE FILE 2
RECONSTRUCTION ALGORITHM ALL THE ERRORS MUST BE      Recent

POSITIVE. IF
ERROR IS NOT POSITIVE IT WILL BE SET EQUAL TO THE     Recent

STANDARD OPTION
(CURRENTLY 0.001, CORRRESPONDING TO 0.1 PER-CENT). Recent

IF THE FIRST
LINE OF THE ERROR LAW IS BLANK IT WILL TERMINATE THE  Recent

ERROR LAW AND
THE ERROR WILL BE TREATED AS ENERGY INDEPENDENT,     Recent

EQUAL TO THE
STANDARD OPTION (CURRENTLY, 0.1 PER-CENT). SEE,
Recent

EXAMPLE INPUT
4.                                                   Recent

Recent

EXAMPLE INPUT
NO. 1
Recent

-------------------
Recent

CONSIDER ALL
URANIUM ISOTOPES AND TH-232. CONSIDER CROSS SECTIONS  Recent

WHICH ARE LARGER
THAN 1.0E-8 BARNS IN ABSOLUTE VALUE. ONLY OUTPUT  Recent

REACTIONS FOR
WHICH A BACKGROUND IS GIVEN. LIST ALL PARAMETERS AND Recent

CALCULATE CROSS
SECTIONS. MONITOR THE EXECUTION PROGRESS OF THE    Recent

PROGRAM. BETWEEN
0 AND 100 EV USE 0.1 PER-CENT ACCURACY. BETWEEN   Recent

100 EV AND 1 KEV
VARY THE ACCURACY FROM 0.1 TO 1 PER-CENT. ABOVE   Recent

1 KEV USE 1
PER-CENT ACCURACY.
Recent

Recent

EXPLICITLY
SPECIFY THE STANDARD FILENAMES.
Recent

Recent

THE FOLLOWING 11
INPUT CARDS ARE REQUIRED.
Recent

Recent

1 1.00000-08
0
1
0
1
Recent

ENDFB.IN
Recent

ENDFB.OUT
Recent

92000      92999
Recent

90232
(UPPER LIMIT AUTOMATICALLY SET TO 90232)   Recent

(END REQUEST LIST)
Recent

0.00000+ 0 1.00000-03
Recent

1.00000+02 1.00000-03
Recent

1.00000+03 1.00000-02
Recent

1.00000+09 1.00000-02                                                  Recent

(END FILE 2 ERROR LAW)
Recent

Recent

EXAMPLE INPUT
NO. 2
Recent

-------------------
Recent

CONSIDER ALL
URANIUM ISOTOPES AND TH-232. CONSIDER CROSS SECTIONS  Recent

WHICH ARE LARGER
THAN 1.0E-8 BARNS IN ABSOLUTE VALUE. ONLY OUTPUT  Recent

REACTIONS FOR
WHICH A BACKGROUND IS GIVEN. CROSS SECTIONS WILL BE  Recent

CALCULATED, BUT
PARAMETERS WILL NOT BE LISTED. THE PROGRESS OF THE Recent

PROGRAM WILL NOT
BE MONITORED. USE 0.1 PER-CENT ACCURACY FOR ALL   Recent

ENERGIES. SINCE
0.1 PER-CENT IS THE STANDARD OPTION FOR THE ERROR  Recent

LAW THE FIRST
ERROR LAW LINE MAY BE LEFT BLANK.
Recent

Recent

LEAVE THE
DEFINITION OF THE FILENAMES BLANK - THE PROGRAM WILL     Recent

THEN USE THE
STANDARD FILENAMES.
Recent

Recent

THE FOLLOWING 7
INPUT CARDS ARE REQUIRED.
Recent

Recent

1 1.00000-08
0
0
0
0
Recent

Recent

Recent

92000      92999
Recent

90232                  (UPPER
LIMIT AUTOMATICALLY SET TO 90232)
Recent

(END REQUEST LIST)
Recent

(USE STANDARD OPTION FOR ERROR LAW)
Recent

Recent

EXAMPLE INPUT
NO. 3
Recent

-------------------
Recent

THE SAME AS
EXAMPLE INPUT NO. 2, ONLY IN THIS CASE ONLY CALCULATE  Recent

CROSS SECTIONS
OVER THE ENERGY RANGE 0.01 TO 0.1 EV - ACROSS THE   Recent

THERMAL ENERGY
RANGE. NOTE, THE ONLY DIFFERENCE BETWEEN THE INPUT  Recent

PARAMETERS IN
THIS CASE AND IN EXAMPLE NO. 2, IS THAT ON THE
Recent

SECOND INPUT
LINE WE HAVE ADDED THE ENERGY RANGE 0.01 TO 0.1 EV.   Recent

USE
\PREPRO94\LINEAR\ENDFB.OUT AS INPUT AND ENDFB.OUT AS OUTPUT -  Recent

SINCE ENDFB.OUT
IS THE STANDARD OUTPUT FILENAME THE NAME CAN BE    Recent

EITHER INCLUDED
IN THE INPUT OR LEFT BLANK.
Recent

Recent

THE FOLLOWING 7
INPUT CARDS ARE REQUIRED.
Recent

Recent

1 1.00000-08
0
0
0
0
Recent

\PREPRO94\LINEAR\ENDFB.OUT
Recent

ENDFB.OUT
Recent

92000      92999 1.00000- 2
1.00000- 1
Recent

90232
(UPPER LIMIT AUTOMATICALLY SET TO 90232)   Recent

(END REQUEST LIST)
Recent

(USE STANDARD OPTION FOR ERROR LAW)
Recent

Recent

EXAMPLE INPUT
NO. 4
Recent

-------------------
Recent

RECONSTRUCT ALL
DATA. OUTPUT ALL REACTIONS, REGARDING OF WHETHER   Recent

OR NOT THERE IS
A BACKGROUND CROSS SECTION. DO NOT MONITOR THE     Recent

PROGRESS OF THE
PROGRAM. RECONSTRUCT CROSS SECTIONS TO 1 PER-CENT  Recent

ACCURACY. USE
\ENDFB6\LINEAR\ZA092238 AS INPUT AND
Recent

\ENDFB6\RECENT\ZA092238 AS OUTPUT.
Recent

Recent

THE FOLLOWING 6
INPUT CARDS ARE REQUIRED.
Recent

Recent

0 0.0
1
0
0
0
Recent

\ENDFB6\ZA092238
Recent

\ENDFB6\RECENT\ZA092238
Recent

(RETRIEVE ALL DATA, END REQUEST LIST)
Recent

1.00000- 2
Recent

(END FILE 2 ERROR LAW)
Recent

Recent

EXAMPLE INPUT
NO. 5
Recent

-------------------
Recent

RECONSTRUCT ALL
DATA. ONLY OUTPUT REACTIONS FOR WHICH A BACKGROUND Recent

CROSS SECTION IS
GIVEN. DO NOT MONITOR THE PROGRESS OF THE PROGRAM Recent

RECONSTRUCT
CROSS SECTIONS TO 0.1 PER-CENT ACCURACY. USE ENDFB.IN  Recent

AS INPUT AND
ENDFB.OUT AS OUTPUT.
Recent

Recent

THIS CORRESPONDS
TO USING ALL OF THE STANDARD OPTONS BUILT-IN TO   Recent

THE PROGRAM AND
ALL INPUT CARDS MAY BE BLANK.
Recent

Recent

IN THIS CASE THE
FOLLOWING 5 INPUT CARDS ARE REQUIRED.
Recent

(ZEROES ARE INDICATED
ON THE FIRST LINE, BELOW, ONLY TO INDICATE   Recent

WHERE THE LINE
IS. THE ACTUAL INPUT LINE CAN BE COMPLETELY BLANK). Recent

Recent

0 0.0
0
0
0
0
Recent

(USE STANDARD INPUT FILENAME = ENDFB.IN)
Recent

(USE STANDARD OUTPUT FILENAME = ENDFB.OUT)
Recent

(RETRIEVE ALL DATA, END REQUEST LIST)
Recent

(0.1 ERROR, END FILE 2 ERROR LAW)
Recent

Recent

=======================================================================
Recent

=======================================================================
Relabel

Relabel

PROGRAM
RELABEL
Relabel

VERSION 69-1
(APRIL 1969)
Relabel

VERSION 73-1
(JUNE 1973)
Relabel

VERSION 77-1
(SEPTEMBER 1977)
Relabel

VERSION 80-1
(AUGUST 1980) IBM VERSION
Relabel

VERSION 83-1
(JANUARY 1983) COMBINED STATEMENT NUMBER SEQUENCE     Relabel

AND LINE I.D. INTO ONE PROGRAM.
Relabel

VERSION 86-1
(JANUARY 1986) FORTRAN-77/H VERSION
Relabel

VERSION 88-1
(JULY 1988)
*OPTION...INTERNALLY DEFINE ALL I/O     Relabel

FILE NAMES (SEE, SUBROUTINES FILIO1    Relabel

AND
FILIO2 FOR DETAILS).
Relabel

*IMPROVED BASED ON USER COMMENTS.       Relabel

VERSION 89-1
(JANUARY 1989)*PSYCHOANALYZED BY PROGRAM FREUD TO     Relabel

INSURE
PROGRAM WILL NOT DO ANYTHING
Relabel

CRAZY.
Relabel

*UPDATED TO USE NEW PROGRAM CONVERT     Relabel

KEYWORDS.
Relabel

*ADDED LIVERMORE
CIVIC COMPILER
Relabel

CONVENTIONS.
Relabel

VERSION 92-1
(JANUARY 1992)*ADDED FORTRAN SAVE OPTION
Relabel

VERSION 94-1
(JANUARY 1994)*COMPLETE RE-WRITE
Relabel

*OUTPUT MINIMUM NON-BLANK LENGTH FOR    Relabel

EACH LINE - NO SEQUENCE NUMBERS.       Relabel

*INCREASED MAXIMUM NUMBER OF LABELS     Relabel

PER ROUTINE FROM 1000 TO 50,000
Relabel

*CAN NOW PROCESS UPPER OR LOWER
CASE    Relabel

CODING.
Relabel

*SKIP IMBEDDED BLANKS IN KEYWORDS.      Relabel

*ADDED WRITE(XX,XX,ERR=YYY,END=ZZZ)
Relabel

*ADDED OPEN(XX,ERR=YYY,END=ZZZ)
Relabel

*ADDED CLOSE(XX,ERR=YYY,END=ZZZ)
Relabel

*INTEGER INSTEAD OF CHARACTERS IS NO    Relabel

LONGER SUPPORTED - ALL CHARACTERS      Relabel

MUST BE IDENTIFIED AS CHARACTERS.      Relabel

*VARIABLE FILENAMES TO ALLOW ACCESS     Relabel

FILE
STRUCTURES
Relabel

(WARNING - INPUT PARAMETER FORMAT      Relabel

HAS BEEN CHANGED)
Relabel

*CLOSE
ALL FILES BEFORE TERMINATING     Relabel

(SEE, SUBROUTINE ENDIT)
Relabel

VERSION 96-1
(JANUARY 1996) *COMPLETE RE-WRITE
Relabel

*IMPROVED
COMPUTER INDEPENDENCE
Relabel

*ALL DOUBLE PRECISION
Relabel

*ON SCREEN OUTPUT
Relabel

*IMPROVED OUTPUT PRECISION
Relabel

*DEFINED SCRATCH FILE NAMES
Relabel

*INCREASED THE NUMBER OF LABELS
Relabel

IN A ROUTINE FOR 5,000 TO 50,000      Relabel

VERSION 99-1
(MARCH 1999)   *GENERAL
IMPROVEMENTS BASED ON
Relabel

USER FEEDBACK
Relabel

VERS. 2000-1
(FEBRUARY 2000)*UPDATED TO IGNORE ( AND ) IN QUOTES   Relabel

*GENERAL IMPROVEMENTS BASED ON
Relabel

USER FEEDBACK
Relabel

VERS. 2002-1
(MAY 2002)
*OPTIONAL INPUT PARAMETERS             Relabel

*CORRECTED END=, ERR=, WHEN I/O UNIT   Relabel

NUMBER IS DIMENSIONED
Relabel

VERS. 2004-1
(MARCH 2004)   *ADDED INCLUDE
FOR COMMON
Relabel

*INCREASED THE NUMBER OF LABELS IN     Relabel

A ROUTINE FOR 50,000 TO 100,000       Relabel

Relabel

OWNED,
MAINTAINED AND DISTRIBUTED BY
Relabel

------------------------------------
Relabel

THE NUCLEAR DATA
SECTION
Relabel

INTERNATIONAL
ATOMIC ENERGY AGENCY
Relabel

P.O. BOX 100
Relabel

A-1400, VIENNA, AUSTRIA
Relabel

EUROPE
Relabel

Relabel

ORIGINALLY
WRITTEN BY
Relabel

------------------------------------
Relabel

DERMOTT E.
CULLEN
Relabel

UNIVERSITY OF CALIFORNIA
Relabel

LAWRENCE
LIVERMORE
NATIONAL LABORATORY                             Relabel

L-159
Relabel

P.O. BOX 808
Relabel

LIVERMORE, CA
94550
Relabel

U.S.A.
Relabel

TELEPHONE  925-423-7359
Relabel

E. MAIL    [email-masked]
Relabel

WEBSITE
HTTP://WWW.LLNL.GOV/CULLEN1
Relabel

Relabel

PURPOSE
Relabel

-------
Relabel

THIS PROGRAM IS
DESIGNED TO RE-LABEL A FORTRAN PROGRAM SO THAT     Relabel

STATEMENT LABELS
ARE IN INCREASING ORDER IN INCREMENTS OF 10       Relabel

WITHIN EACH
ROUTINE.
Relabel

Relabel

THE FOLLOWING
TYPES OF FORTRAN STATEMENTS ARE CONSIDERED,
Relabel

Relabel

GO TO NN
Relabel

GO TO
(NN,MM,.....,JJ,KK),LL (MULTI LINE O.K.)
Relabel

DO NN
Relabel

IF(......)
NN,MM,...JJ,KK
Relabel

IF(......) GO TO
NN
Relabel

IF(......) GO TO
(NN,MM,.....,JJ,KK),LL (MULTI LINE O.K.)
Relabel

IF(......)
READ(.....,END=NN,ERR=MM)
Relabel

IF(......)
WRITE(.....,END=NN,ERR=MM)
Relabel

READ(......,END=NN,ERR=MM)
Relabel

OPEN(......,END=NN,ERR=MM)
Relabel

Relabel

GO TO STATEMENTS
MAY APPEAR IN THE FORM 'GO TO' OR 'GOTO'. IF      Relabel

THERE IS ROOM ON
THE LINE 'GOTO' WILL BE CONVERTED TO 'GO TO'.     Relabel

WHETHER OR NOT
'GOTO' IS CONVERTED TO 'GO TO' IT WILL BE TREATED   Relabel

AS IDENTICAL TO
'GO TO' FOR SUBSEQUENT PROCESSING AND RELACEMENT   Relabel

OF STATEMENT
NUMBERS.
Relabel

Relabel

ALL OTHER
STATEMENT TYPES ARE NOT CHANGED. IN PARTICULAR ALL I/O   Relabel

STATEMENTS AND
ASSOCIATED FORMAT STATEMENTS ARE NOT CONVERTED.     Relabel

Relabel

WARNING
Relabel

-------
Relabel

THIS PROGRAM IS
ONLY DESIGNED TO MAINTAIN ENDF/B PRE-PROCESSING    Relabel

PROGRAMS, WHICH
ONLY USE A RESTRICTED SET OF FORTRAN STATEMENT     Relabel

TYPES THAT CAN
BE USED ON A VARIETY OF DIFFERENT TYPES OF
Relabel

COMPUTERS. THIS
PROGRAM IS NOT DESIGNED TO HANDLE ALL POSSIBLE     Relabel

TYPES OF FORTRAN
STATEMENTS.
Relabel

Relabel

THE FORTRAN
STATEMENTS DESCRIBED ABOVE AND TREATED BY THIS PROGRAM Relabel

DO NOT INCLUDE
ALL POSSIBLE FORTRAN STATEMENTS. AS SUCH THIS       Relabel

PROGRAM IS NOT
COMPLETELY GENERAL AND SHOULD ONLY BE USED WITH     Relabel

PROGRAMS THAT
ONLY USE THE FORTRAN STATEMENTS DESCRIBED ABOVE.     Relabel

Relabel

FAILURE TO
FOLLOW THESE INSTRUCTIONS CAN LEAD TO ERROR IN PROGRAMS Relabel

Relabel

OPTIONAL
STANDARD FILE NAMES (SEE SUBROUTINES FILIO1 AND FILIO2)   Relabel

----------------------------------------------------------------   Relabel

UNIT  FILE NAME    DESCRIPTION
Relabel

----  ----------   -----------
Relabel

2   RELABEL.INP  INPUT PARAMETERS
Relabel

3   RELABEL.LST  OUTPUT REPORT
Relabel

10   RELABEL.IN   PROGRAM TO READ
Relabel

11   RELABEL.OUT  PROGRAM TO WRITE
Relabel

12   (SCRATCH)
Relabel

Relabel

INPUT CARDS
Relabel

-----------
Relabel

LINE  COLUMNS  DEFINITION
Relabel

----  -------  ----------
Relabel

1   1-60    INPUT PROGRAM FILENAME
Relabel

(STANDARD OPTION = RELABEL.IN)
Relabel

2   1-60    OUTPUT PROGRAM FILENAME
Relabel

(STANDARD OPTION =
RELABEL.OUT)
Relabel

Relabel

LEAVE THE
DEFINITION OF THE FILENAMES BLANK - THE PROGRAM WILL     Relabel

THEN USE
STANDARD FILENAMES.
Relabel

Relabel

EXAMPLE INPUT
NO. 1
Relabel

-------------------
Relabel

TO READ
\PREPRO94\RECENT\RECENT.FOR AND
Relabel

WRITE   \PREPRO94\RECENT\RECENT.NEW THE
FOLLOWING 2 INPUT LINES
Relabel

ARE
REQUIRED,
Relabel

Relabel

\PREPRO94\RECENT\RECENT.FOR
Relabel

Relabel

EXAMPLE INPUT
NO. 2
Relabel

-------------------
Relabel

TO READ
RELABEL.IN AND WRITE RELABEL.OUT THE FOLOWING 2 INPUT      Relabel

LINES ARE
REQUIRED,
Relabel

Relabel

RELABEL.IN
Relabel

RELABEL.OUT
Relabel

Relabel

EXAMPLE INPUT
NO. 3
Relabel

-------------------
Relabel

TO READ
RELABEL.IN AND WRITE RELABEL.OUT, SINCE THESE ARE THE      Relabel

STANDARD OPTIONS
THE 2 INPUT LINES CAN BE COMPLETELY BLANK.
Relabel

Relabel

=======================================================================
Relabel

=======================================================================
Sigma1

Sigma1

PROGRAM
SIGMA1
Sigma1

==============
Sigma1

VERSION 73-1
(MARCH 1973)                                          Sigma1

VERSION 76-1
(FEBRUARY 1976)
Sigma1

VERSION 76-2
(OCTOBER 1976)
Sigma1

VERSION 77-1
(JANUARY 1977)
Sigma1

VERSION 78-1
(JULY 1978)
Sigma1

VERSION 79-1
(JULY 1979)    CDC-7600
AND CRAY-1 VERSION.
Sigma1

VERSION 80-1
(MAY 1980)     IBM,
CDC AND CRAY VERSION
Sigma1

VERSION 80-2
(DECEMBER 1980)IMPROVED BASED ON USER COMMENTS.
Sigma1

VERSION 81-1
(MARCH 1981)   DOUBLE PRECISION
IBM VERSION
Sigma1

VERSION 81-2
(AUGUST 1981)  IMPROVED IBM SPEED
AND STABILITY       Sigma1

VERSION 82-1
(JANUARY 1982) IMPROVED COMPUTER COMPATIBILITY
Sigma1

VERSION 83-1
(JANUARY 1983)*MAJOR RE-DESIGN.
Sigma1

*PAGE SIZE INCREASED - 1002 TO 2004.    Sigma1

*ELIMINATED COMPUTER DEPENDENT CODING.  Sigma1

*NEW, MORE COMPATIBLE I/O UNIT NUMBER.  Sigma1

*ADDED STANDARD ALLOWABLE ERROR OPTION  Sigma1

(CURRENTLY
0.1 PER-CENT).
Sigma1

*UNRESOLVED RESONANCE REGION COPIED.    Sigma1

*1/V EXTENSION OF CROSS SECTIONS
Sigma1

OUTSIDE
OF TABULATED ENERGY
RANGE AND  Sigma1

INTO UNRESOLVED ENERGY
RANGE.
Sigma1

VERSION 83-2
(OCTOBER 1983)*IMPROVED BASED ON USER COMMENTS.
Sigma1

VERSION 84-1
(APRIL 1984)  *IMPROVED NUMERICAL
STABILITY.
Sigma1

*PARTIAL EVALUATION TREATMENT.
Sigma1

VERSION 85-1
(APRIL 1985)  *ITERATE TO
CONVERGENCE (USING THE SAME Sigma1

ENERGY GRID FOR HOT CROSS SECTION AS   Sigma1

COLD CROSS SECTIONS WAS FOUND TO BE    Sigma1

INACCURATE).
Sigma1

*NEW FASTER HIGH ENERGY BROADENING.     Sigma1

*UPDATED FOR ENDF/B-VI FORMATS.
Sigma1

*SPECIAL I/O ROUTINES TO GUARANTEE      Sigma1

ACCURACY OF ENERGY.
Sigma1

*DOUBLE PRECISION TREATMENT OF ENERGY   Sigma1

(REQUIRED FOR NARROW RESONANCES).      Sigma1

VERSION 85-2
(AUGUST 1985) *FORTRAN-77/H VERSION
Sigma1

VERSION 86-1
(JANUARY 1986)*ENERGY DEPENDENT SCATTERING RADIUS     Sigma1

VERSION 88-1
(JULY 1988)
*OPTION...INTERNALLY DEFINE ALL I/O     Sigma1

FILE NAMES (SEE, SUBROUTINE FILEIO     Sigma1

FOR DETAILS).
Sigma1

*IMPROVED BASED ON USER COMMENTS.
Sigma1

VERSION 89-1
(JANUARY 1989)*PSYCHOANALYZED BY PROGRAM FREUD TO     Sigma1

INSURE
PROGRAM WILL NOT DO ANYTHING
Sigma1

CRAZY.
Sigma1

*UPDATED TO USE NEW PROGRAM CONVERT     Sigma1

KEYWORDS.
Sigma1

*ADDED LIVERMORE
CIVIC COMPILER
Sigma1

CONVENTIONS.
Sigma1

VERSION 90-1
(JUNE 1990)   *UPDATED BASED ON
USER COMMENTS
Sigma1

*ADDED FORTRAN SAVE OPTION
Sigma1

*NEW MORE CONSISTENT ENERGY OUTPUT      Sigma1

ROUTINES
Sigma1

VERSION 91-1
(JULY 1991)   *WARNING...INPUT
PARAMETER FORMAT       Sigma1

HAS BEEN CHANGED - SEE BELOW FOR
Sigma1

DETAILS.                               Sigma1

*ADDED CHARGED PARTICLE PROJECTILES     Sigma1

*OUTPUT ENERGY RANGE
IS ALWAYS AT
Sigma1

LEAST AS LARGE AS INPUT ENERGY RANGE.  Sigma1

*NO 1/V EXTENSION OF CROSS SECTIONS     Sigma1

FROM UNRESOLVED ENERGY
RANGE.
Sigma1

VERSION 92-1
(JANUARY 1992)*INSURE MINIMUM AND MAXIMUM CROSS
Sigma1

SECTIONS ARE ALWAYS KEPT (NOT THINNED) Sigma1

*MT=19 (FIRST CHANCE FISSION) TREATED   Sigma1

THE SAME AS FISSION.
Sigma1

*VARIABLE MINIMUM CROSS SECTION OF      Sigma1

INTEREST - TO ALLOW SMALL CROSS
Sigma1

SECTIONS NEAR THRESHOLDS TO BE
Sigma1

TREATED
PROPERLY.
Sigma1

*ALL ENERGIES INTERNALLY ROUNDED PRIOR  Sigma1

TO CALCULATIONS.
Sigma1

*COMPLETELY
CONSISTENT I/O AND ROUNDING Sigma1

ROUTINES - TO MINIMIZE COMPUTER
Sigma1

DEPENDENCE.
Sigma1

VERSION 92-2
(JULY 1992)   *CORRECTED BUG
ASSOCIATED WITH
Sigma1

THRESHOLD REACTIONS.
Sigma1

*UNRESOLVED REGION COPIED WITHOUT
Sigma1

THINNING (IT SHOULD BE
EXACTLY THE
Sigma1

SAME AT ALL TEMPERATURES).
Sigma1

*NO THINNING OF REACTIONS (MT) THAT     Sigma1

WERE NOT BROADENED.
Sigma1

VERSION 93-1
(APRIL 1993)  *INCREASED PAGE SIZE
FROM 2004
Sigma1

TO 24000 ENERGY PONTS.
Sigma1

VERSION 94-1
(JANUARY 1994)*VARIABLE ENDF/B DATA FILENAMES
Sigma1

TO ALLOW ACCESS TO FILE STRUCTURES     Sigma1

(WARNING - INPUT PARAMETER FORMAT      Sigma1

HAS BEEN CHANGED)
Sigma1

*CLOSE ALL FILES BEFORE TERMINATING     Sigma1

(SEE, SUBROUTINE ENDIT)
Sigma1

VERSION 96-1
(JANUARY 1996) *COMPLETE RE-WRITE
Sigma1

*IMPROVED COMPUTER INDEPENDENCE
Sigma1

*ALL DOUBLE PRECISION
Sigma1

*ON SCREEN OUTPUT
Sigma1

*UNIFORM TREATMENT OF ENDF/B I/O
Sigma1

*IMPROVED OUTPUT PRECISION
Sigma1

*DEFINED SCRATCH FILE NAMES
Sigma1

*ALWAYS
INCLUDE THERMAL VALUE
Sigma1

VERSION 97-1
(APRIL 1997)   *OPTIONALLY SET
NEGATIVE CROSS
Sigma1

SECTIONS = 0 ON INPUT AND
Sigma1

OUTPUT.
Sigma1

*INCREASED PAGE SIZE FROM 24000
Sigma1

TO 60000 ENERGY POINTS.
Sigma1

VERSION 99-1
(MARCH 1999)   *CORRECTED
CHARACTER TO FLOATING
Sigma1

POINT READ FOR MORE DIGITS
Sigma1

*UPDATED TEST FOR ENDF/B FORMAT
Sigma1

VERSION BASED ON RECENT FORMAT CHANGE Sigma1

*TREAT LOW ENERGY INITIAL CROSS
Sigma1

SECTIONS AS LOG-LOG INTERPOLABLE      Sigma1

*CONSTANT (RATHER THAN 1/V) EXTENSION  Sigma1

TO HIGHER ENERGY.
Sigma1

*UPDATED CONSTANTS BASED ON CSEWG      Sigma1

SUBCOMMITTEE RECOMMENDATIONS
Sigma1

*GENERAL IMPROVEMENTS BASED ON
Sigma1

USER FEEDBACK
Sigma1

VERSION 99-2
(JUNE 1999)    *EXTENDED
RANGE OF INTEGRALS FROM 4    Sigma1

TO 5 UNITS ON EACH SIDE OF ENERGY     Sigma1

POINT TO ALLOW FOR LARGER VARIATION   Sigma1

IN THE LOCAL CROSS SECTION
Sigma1

*ASSUME ENDF/B-VI, NOT V, IF MISSING   Sigma1

MF=1, MT-451.
Sigma1

VERSION 99-3
(OCTOBER 1999))*IMPROVED ERFC FUNCTION DEFINITION.    Sigma1

I
THANK BOB MACFARLANE (LANL) FOR     Sigma1

SUPPLYING A MORE ACCURATE ERFC
Sigma1

FUNCTION.
Sigma1

VERS. 2000-1 (FEBRUARY
2000)*CORRECTED LOW ENERGY INTERPOLATION    Sigma1

FOR NON-POSITIVE CROSS SECTIONS
Sigma1

*GENERAL IMPROVEMENTS BASED ON
Sigma1

USER
FEEDBACK
Sigma1

VERS. 2002-1
(MAY 2002)
*OPTIONAL INPUT PARAMETERS
Sigma1

VERS. 2004-1
(JAN. 2004)    *OPTIONALLY
IGNORE UNRESOLVED REGION
Sigma1

*CORRECTED PROBLEM AT THE RESOLVED/    Sigma1

UNRESOLVED ENERGY BOUNDARY.
Sigma1

*CORRECTED HIGH ENERGY CONSTANT CROSS  Sigma1

SECTION EXTENSION.
Sigma1

*TIGHTER CRITERIA FOR INITIAL ENERGY   Sigma1

POINT SPACING
Sigma1

*TEMPERATURE DEPENDENT ENERGY POINT    Sigma1

SPACING.
Sigma1

*ADDED NEW REICH-MOORE (LRF=7) TO      Sigma1

FILE2 TO ALLOW COPY TO FIND ANY       Sigma1

FOLLOWING UNRESOLVED PARAMETERS
Sigma1

VERS. 2005-1
(JUNE 2005)    *CORRECTED
ERROR IN EHOT3 EQUIVALENCE  Sigma1

TO EHOT - THIS ONLY EFFECTS VERY BIG  Sigma1

OUTPUT FILES.
Sigma1

VERS. 2007-1
(JAN. 2007)    *CHECKED
AGAINST ALL ENDF/B-VII.
Sigma1

*INCREASED PAGE SIZE FROM 60,000
Sigma1

TO
360,000 ENERGY POINTS.
Sigma1

Sigma1

Acknowledgement
2004
Sigma1

--------------------
Sigma1

Currently almost
all improvements to this code are based upon      Sigma1

feedback from
code users who report problems. This feedback
Sigma1

benefits ALL
users of this code, and ALL users are encouraged      Sigma1

to report
problems.
Sigma1

Sigma1

Improvements on
the 2004 version of this code based on user
Sigma1

feedback
including,
Sigma1

1) Bret
Beck  - reported a problem at the
resolved/unresolved      Sigma1

energy boundary.
Sigma1

2) S. Ganesan -
reported a problem for small temperature changes.  Sigma1

Sigma1

OWNED,
MAINTAINED AND DISTRIBUTED BY
Sigma1

------------------------------------
Sigma1

THE NUCLEAR DATA
SECTION
Sigma1

INTERNATIONAL
ATOMIC ENERGY AGENCY
Sigma1

P.O. BOX
100
Sigma1

A-1400, VIENNA,
AUSTRIA
Sigma1

EUROPE
Sigma1

Sigma1

ORIGINALLY
WRITTEN BY
Sigma1

------------------------------------
Sigma1

DERMOTT E. CULLEN
Sigma1

UNIVERSITY OF
CALIFORNIA
Sigma1

LAWRENCE
LIVERMORE NATIONAL LABORATORY
Sigma1

L-159                                                              Sigma1

P.O. BOX
808
Sigma1

LIVERMORE, CA
94550
Sigma1

U.S.A.
Sigma1

TELEPHONE  925-423-7359
Sigma1

E. MAIL    [email-masked]
Sigma1

WEBSITE    HTTP://WWW.LLNL.GOV/CULLEN1
Sigma1

Sigma1

AUTHORS
MESSAGE
Sigma1

---------------
Sigma1

THE REPORT
DESCRIBED ABOVE IS THE LATEST PUBLISHED DOCUMENTATION   Sigma1

FOR THIS
PROGRAM. HOWEVER, THE COMMENTS BELOW SHOULD BE CONSIDERED Sigma1

THE LATEST
DOCUMENTATION INCLUDING ALL RECENT IMPROVEMENTS. PLEASE Sigma1

READ ALL OF
THESE COMMENTS BEFORE IMPLEMENTATION, PARTICULARLY     Sigma1

THE COMMENTS
CONCERNING MACHINE DEPENDENT CODING.
Sigma1

Sigma1

AT THE PRESENT
TIME WE ARE ATTEMPTING TO DEVELOP A SET OF COMPUTER Sigma1

INDEPENDENT
PROGRAMS THAT CAN EASILY BE IMPLEMENTED ON ANY ONE     Sigma1

OF A WIDE
VARIETY OF COMPUTERS. IN ORDER TO ASSIST IN THIS PROJECT Sigma1

IT WOULD BE
APPECIATED IF YOU WOULD NOTIFY THE AUTHOR OF ANY
Sigma1

COMPILER
DIAGNOSTICS, OPERATING PROBLEMS OR SUGGESTIONS ON HOW TO  Sigma1

IMPROVE THIS
PROGRAM. HOPEFULLY, IN THIS WAY FUTURE VERSIONS OF    Sigma1

THIS PROGRAM WILL BE
COMPLETELY COMPATIBLE FOR USE ON YOUR
Sigma1

COMPUTER.
Sigma1

Sigma1

PURPOSE
Sigma1

-------
Sigma1

THIS PROGRAM IS
DESIGNED TO DOPPLER BROADEN NEUTRON INDUCED
Sigma1

CROSS SECTIONS.
EACH SECTION OF CROSS SECTIONS (FILE 3) IS READ    Sigma1

FROM THE ENDF/B
FORMAT. THE DATA IS DOPPLER BROADENED, THINNED     Sigma1

AND OUTPUT IN
THE ENDF/B FORMAT.
Sigma1

Sigma1

IN THE FOLLOWING
DISCUSSION FOR SIMPLICITY THE ENDF/B TERMINOLOGY  Sigma1

---ENDF/B
TAPE---WILL BE USED. IN FACT THE ACTUAL MEDIUM MAY BE    Sigma1

TAPE, CARDS,
DISK OR ANY OTHER MEDIUM.
Sigma1

Sigma1

ENDF/B
FORMAT
Sigma1

-------------
Sigma1

THIS PROGRAM
ONLY USES THE ENDF/B BCD OR CARD IMAGE FORMAT (AS     Sigma1

OPPOSED TO THE
BINARY FORMAT) AND CAN HANDLE DATA IN ANY VERSION   Sigma1

OF THE ENDF/B
FORMAT (I.E., ENDF/B-I, II, III, IV OR V FORMAT).    Sigma1

Sigma1

IT IS ASSUMED
THAT THE DATA IS CORRECTLY CODED IN THE ENDF/B
Sigma1

FORMAT AND NO
ERROR CHECKING IS PERFORMED. IN PARTICULAR IT IS     Sigma1

ASSUMED THAT THE
MAT, MF AND MT ON EACH CARD IS CORRECT. SEQUENCE  Sigma1

NUMBERS (COLUMNS
76-80) ARE IGNORED ON INPUT, BUT WILL BE
Sigma1

CORRECTLY OUTPUT
ON ALL CARDS. THE FORMAT OF SECTION MF=1, MT=451  Sigma1

AND ALL SECTIONS
OF MF=3 MUST BE CORRECT. THE PROGRAM COPIES ALL   Sigma1

OTHER SECTION OF
DATA AS HOLLERITH AND AS SUCH IS INSENSITIVE TO   Sigma1

THE CORRECTNESS
OR INCORRECTNESS OF ALL OTHER SECTIONS.
Sigma1

Sigma1

ALL CROSS
SECTIONS THAT ARE USED BY THIS PROGRAM MUST BE TABULATED Sigma1

AND LINEARLY
INTERPOLABLE IN ENERGY AND CROSS SECTION (ENDF/B      Sigma1

INTERPOLATION LAW
2). FILE 3 CROSS SECTIONS MAY BE MADE LINEARLY   Sigma1

INTERPOLABLE BY
USING PROGRAM LINEAR (UCRL-50400, VOL.17, PART A). Sigma1

FILE 2 RESONANCE
PARAMETERS MAY BE USED TO RECONSTRUCT ENERGY      Sigma1

DEPENDENT CROSS
SECTIONS AND ADD IN FILE 3 BACKGROUND CROSS
Sigma1

SECTIONS TO
DEFINE LINEARLY INTERPOLABLE CROSS SECTIONS BY USING   Sigma1

PROGRAM RECENT
(UCRL-50400, VOL. 17, PART C). IF THIS PROGRAM      Sigma1

FINDS THAT THE
FILE 3 CROSS SECTIONS ARE NOT LINEARLY INTERPOLABLE Sigma1

THIS PROGRAM
WILL TERMINATE EXECUTION.
Sigma1

Sigma1

UNRESOLVED
RESONANCE REGION
Sigma1

---------------------------
Sigma1

IN THE
UNRESOLVED RESONANCE REGION IT IS NOT POSSIBLE TO EXACTLY   Sigma1

DEFINE THE
ENERGY DEPENDENCE OF THE CROSS SECTIONS. THE AVERAGE    Sigma1

WIDTHS AND
SPACINGS GIVEN IN ENDF/B ARE ONLY ADEQUATE TO DEFINE    Sigma1

AVERAGE VALUES
OF THE CROSS SECTIONS. THEREFORE ALL CROSS SECTIONS Sigma1

IN THE ENDF/B
FORMAT FOR THE UNRESOLVED REGION ARE REALLY AVERAGE  Sigma1

VALUES WHICH
CANNOT BE DOPPLER BROADENED USING THE SIGMA1 METHOD   Sigma1

(WHICH REQUIRES
TABULATED, LINEARLY INTERPOLABLE, ENERGY DEPENDENT Sigma1

CROSS
SECTIONS.
Sigma1

Sigma1

THEREFORE,
Sigma1

(1) ALL
TABULATED POINTS WITHIN THE UNRESOLVED RESONANCE REGION    Sigma1

WILL BE COPIED,
WITHOUT MODIFICATION OR BROADENING. ADOPTION OF    Sigma1

THIS CONVENTION
WILL ALLOW SUBSEQUENT PROGRAMS TO PROPERLY DEFINE  Sigma1

SELF-SHIELDED,
DOPPLER BROADENED CROSS SECTIONS IN THE UNRESOLVED  Sigma1

RESONANCE REGION.
Sigma1

(2) CROSS
SECTIONS WILL BE EXTENDED AS 1/V ABOVE THE UPPER ENERGY  Sigma1

LIMIT OF THE
RESOLVED RESONANCE REGION AND BELOW THE LOWER ENERGY  Sigma1

LIMIT OF THE
CONTINUUUM REGION (I.E. INTO THE UNRESOLVED
Sigma1

RESONANCE
REGION). THIS CONVENTION WILL GUARANTEE A SMOOTH
Sigma1

BEHAVIOR CLOSE
TO THE UNRESOLVED RESONANCE REGION BOUNDARIES.      Sigma1

Sigma1

OUTPUT
FORMAT
Sigma1

-------------
Sigma1

IN THIS VERSION
OF SIGMA1 ALL FILE 3 ENERGIES WILL BE OUTPUT IN    Sigma1

F (INSTEAD OF E)
FORMAT IN ORDER TO ALLOW ENERGIES TO BE WRITTEN   Sigma1

WITH UP TO 9
DIGITS OF ACCURACY. IN PREVIOUS VERSIONS THIS WAS AN  Sigma1

OUTPUT OPTION.
HOWEVER USE OF THIS OPTION TO COMPARE THE RESULTS   Sigma1

OF ENERGIES
WRITTEN IN THE NORMAL ENDF/B CONVENTION OF 6 DIGITS    Sigma1

TO THE 9 DIGIT
OUTPUT FROM THIS PROGRAM DEMONSTRATED THAT FAILURE  Sigma1

TO USE THE 9
DIGIT OUTPUT CAN LEAD TO LARGE ERRORS IN THE DATA     Sigma1

JUST DUE TO
TRANSLATION OF THE ENERGIES TO THE ENDF/B FORMAT.      Sigma1

Sigma1

CONTENTS OF
OUTPUT
Sigma1

------------------
Sigma1

ENTIRE
EVALUATIONS ARE OUTPUT, NOT JUST THE BROADENED FILE 3
Sigma1

CROSS SECTIONS,
E.G. ANGULAR AND ENERGY DISTRIBUTIONS ARE ALSO     Sigma1

INCLUDED.
Sigma1

Sigma1

DOCUMENTATION
Sigma1

-------------
Sigma1

THE FACT THAT
THIS PROGRAM HAS OPERATED ON THE DATA IS DOCUMENTED  Sigma1

BY THE ADDITION
OF THREE COMMENTS CARDS AT THE END OF EACH
Sigma1

HOLLERITH
SECTION IN THE FORM
Sigma1

Sigma1

***************** PROGRAM SIGMA1 (2007-1) ***************
Sigma1

DATA DOPPLER
BROADENED TO 300.0   KELVIN
AND
Sigma1

DATA THINNED TO
WITHIN AN ACCURACY OF  0.1
PER-CENT
Sigma1

Sigma1

THE ORDER OF ALL
SIMILAR COMMENTS (FROM LINEAR,RECENT AND GROUPY)  Sigma1

REPRESENTS A
COMPLETE HISTORY OF ALL OPERATIONS PERFORMED ON
Sigma1

THE DATA.
Sigma1

Sigma1

THESE COMMENT
CARDS ARE ONLY ADDED TO EXISTING HOLLERITH SECTIONS, Sigma1

I.E., THIS
PROGRAM WILL NOT CREATE A HOLLERITH SECTION. THE FORMAT Sigma1

OF THE HOLLERITH
SECTION IN ENDF/B-V DIFFERS FROM THE THAT OF      Sigma1

EARLIER VERSIONS
OF ENDF/B. BY READING AN EXISTING MF=1, MT=451    Sigma1

IT IS POSSIBLE
FOR THIS PROGRAM TO DETERMINE WHICH VERSION OF      Sigma1

THE ENDF/B
FORMAT THE DATA IS IN. WITHOUT HAVING A SECTION OF      Sigma1

MF=1, MT=451
PRESENT IT IS IMPOSSIBLE FOR THIS PROGRAM TO
Sigma1

DETERMINE WHICH
VERSION OF THE ENDF/B FORMAT THE DATA IS IN, AND   Sigma1

AS SUCH IT IS
IMPOSSIBLE FOR THE PROGRAM TO DETERMINE WHAT FORMAT  Sigma1

SHOULD BE USED TO
CREATE A HOLLERITH SECTION.
Sigma1

Sigma1

REACTION
INDEX
Sigma1

--------------
Sigma1

THIS PROGRAM
DOES NOT USE THE REACTION INDEX WHICH IS GIVEN IN     Sigma1

SECTION MF=1,
MT=451 OF EACH EVALUATION.
Sigma1

Sigma1

THIS PROGRAM
DOES NOT UPDATE THE REACTION INDEX IN MF=1, MT=451.   Sigma1

THIS CONVENTION
HAS BEEN ADOPTED BECAUSE MOST USERS DO NOT
Sigma1

REQUIRE A
CORRECT REACTION INDEX FOR THEIR APPLICATIONS AND IT WAS Sigma1

NOT CONSIDERED
WORTHWHILE TO INCLUDE THE OVERHEAD OF CONSTRUCTING  Sigma1

A CORRECT
REACTION INDEX IN THIS PROGRAM. HOWEVER, IF YOU REQUIRE  Sigma1

A REACTION INDEX
FOR YOUR APPLICATIONS, AFTER RUNNING THIS PROGRAM Sigma1

YOU MAY USE
PROGRAM DICTIN TO CREATE A CORRECT REACTION INDEX.     Sigma1

Sigma1

SECTION
SIZE
Sigma1

------------
Sigma1

SINCE THIS
PROGRAM USES A LOGICAL PAGING SYSTEM THERE IS NO LIMIT  Sigma1

TO THE NUMBER OF
POINTS IN ANY SECTION, E.G., THE TOTAL CROSS      Sigma1

SECTION MAY BE
REPRESENTED BY 200,000 DATA POINTS.
Sigma1

Sigma1

SELECTION OF
DATA
Sigma1

-----------------
Sigma1

THE PROGRAM
SELECTS MATERIALS TO BE BROADENED BASED EITHER ON      Sigma1

MAT (ENDF/B MAT
NO.) OR ZA. THE PROGRAM ALLOWS UP TO 100 MAT OR    Sigma1

ZA RANGES TO BE
SPECIFIED. THE PROGRAM WILL ASSUME THAT THE
Sigma1

ENDF/B TAPE IS
IN EITHER MAT OR ZA ORDER, WHICHEVER CRITERIA IS    Sigma1

USED TO SELECT
MATERIALS, AND WILL TERMINATE WHEN A MAT OR ZA      Sigma1

IS FOUND THAT IS
ABOVE THE RANGE OF ALL REQUESTS.
Sigma1

Sigma1

ENERGY GRID OF
BROADENED DATA
Sigma1

-----------------------------
Sigma1

THE ENERGY GRID
FOR THE DOPPLER BROADENED CROSS SECTIONS IS
Sigma1

SELECTED TO
INSURE THAT THE BROADENED DATA IS LINEAR-LINEAR
Sigma1

INTERPOLABLE. AS
SUCH THE ENERGY GRID FOR THE BROADENED DATA
Sigma1

MAY NOT BE THE
SAME AS THE ENERGY GRID FOR THE ORIGINAL
Sigma1

UNBROADENED
DATA. GENERALLY AFTER BROADENING THERE WILL BE
Sigma1

FEWER DATA
POINTS IN THE RESONANCE REGION, BUT AT LOW ENERGY
Sigma1

THERE MAY BE
MORE POINTS, DUE TO THE 1/V LOW ENERGY EFFECT
Sigma1

CREATED BY
DOPPLER BROADENING.
Sigma1

Sigma1

EFFECTIVE
TEMERATURE INCREASE
Sigma1

-----------------------------
Sigma1

IF THE ORIGINAL
DATA IS NOT AT ZERO KELVIN THE PROGRAM WILL
Sigma1

BROADEN THE DATA
BY THE EFFECTIVE TEMPERATURE DIFFENCE TO THE      Sigma1

FINAL
TEMPERATURE. IF THE DATA IS ALREADY AT A TEMPERATURE THAT    Sigma1

IS HIGHER THAN
THE FINAL TEMPERATURE DOPPLER BROADENING IS         Sigma1

NATURALLY NOT
PERFORMED AND THE TEMPERATURE IN THE SECTION IS LEFT Sigma1

AT ITS ORIGINAL
VALUE.
Sigma1

Sigma1

MULTIPLE FINAL
TEMPERATURES
Sigma1

---------------------------
Sigma1

THE PRESENT
VERSION ONLY DOPPLER BROADENS TO ONE FINAL TEMPERATURE Sigma1

(IF THERE IS
SUFFICIENT INTEREST EXPRESSED BY USERS FUTURE
Sigma1

VERSION MAY
BROADEN TO MULTIPLE TEMPERATURES. PLEASE
Sigma1

CONTACT THE
AUTHOR IF YOU ARE INTERESTED IN A MULTIPLE
Sigma1

TEMPERATURE OPTION).
Sigma1

Sigma1

PROGRAM
OPERATION
Sigma1

-----------------                                                  Sigma1

EACH SECTION OF
FILE 3 DATA IS CONSIDERED SEPERATELY. THE DATA     Sigma1

IS READ AND
DOPPLER BROADENED A PAGE AT A TIME (ONE PAGE IS
Sigma1

60000 DATA
POINTS). UP TO THREE PAGES OF DATA MAY BE IN THE CORE   Sigma1

AT ANY GIVEN
TIME, THE PAGE BEING BROADENED, THE PAGE BELOW IT     Sigma1

IN ENERGY AND
THE PAGE ABOVE IT IN ENERGY. AFTER A PAGE HAS BEEN   Sigma1

BROADENED IT IS
THINNED, IF THE ENTIRE SECTION CONTAINS ONLY
Sigma1

ONE PAGE OR
LESS, IT WILL STILL BE CORE RESIDENT AND WILL BE
Sigma1

WRITTEN DIRECTLY
FROM CORE TO THE OUTPUT TAPE. IF THE BROADENED,   Sigma1

THINNED SECTION
IS LARGER THAN A PAGE, AFTER A PAGE HAS BEEN
Sigma1

BROADENED AND
THINNED IT IS WRITTEN TO A SCRATCH FILE. AFTER THE   Sigma1

ENTIRE SECTION
HAS BEEN BROADENED AND THINNED THE DATA IS READ     Sigma1

FROM SCRATCH TO
CORE, ONE PAGE AT A TIME, THE OUTPUT TO THE OUTPUT Sigma1

TAPE.
Sigma1

Sigma1

ALLOWABLE
ERROR
Sigma1

---------------
Sigma1

AFTER DOPPLER
BROADENING THE CROSS SECTION IN THE RESONANCE REGION Sigma1

WILL GENERALLY
BE MUCH SMOOTHER THAN THE UNBROADENED DATA AND CAN  Sigma1

BE REPRESENTED
TO THE SAME ACCURACY BY A SMALLER NUMBER OF ENERGY  Sigma1

POINTS.
THEREFORE AFTER DOPPLER BROADENING THE DATA CAN BE THINNED Sigma1

WITH ESSENTIALLY
NO LOSE OF INFORMATION.
Sigma1

Sigma1

THE ALLOWABLE
ERROR MAY BE ENERGY INDEPENDENT (CONSTANT) OR ENERGY Sigma1

DEPENDENT. THE
ALLOWABLE ERROR IS DESCRIBED BY A TABULATED
Sigma1

FUNCTION OF UP
TO 20 (ENERGY,ERROR) PAIRS AND LINEAR INTERPOLATION Sigma1

BETWEEN
TABULATED POINTS. IF ONLY ONE TABULATED POINT IS GIVEN THE Sigma1

ERROR WILL BE
CONSIDERED CONSTANT OVER THE ENTIRE ENERGY RANGE.    Sigma1

WITH THIS ENERGY
DEPENDENT ERROR ONE MAY OPTIMIZE THE OUTPUT FOR   Sigma1

ANY GIVEN
APPLICATION BY USING A SMALL ERROR IN THE ENERGY RANGE   Sigma1

OF INTEREST AND
A LESS STRINGENT ERROR IN OTHER ENERGY RANGES.     Sigma1

Sigma1

INPUT FILES
Sigma1

-----------
Sigma1

UNIT  DESCRIPTION
Sigma1

----  -----------
Sigma1

2  INPUT CARDS (BCD - 80
CHARACTERS/RECORD)
Sigma1

10  ORIGINAL ENDF/B DATA (BCD
- 80 CHARACTERS/RECORD)            Sigma1

Sigma1

OUTPUT
FILES
Sigma1

------------
Sigma1

UNIT  DESCRIPTION
Sigma1

----  -----------
Sigma1

3  OUTPUT REPORT (BCD - 120
CHARACTERS/RECORD)
Sigma1

11  FINAL ENDF/B DATA (BCD - 80
CHARACTERS/RECORD)
Sigma1

Sigma1

SCRATCH
FILES
Sigma1

-------------
Sigma1

UNIT  DESCRIPTION
Sigma1

----  -----------
Sigma1

12  SCRATCH FILE FOR
BROADENED DATA
Sigma1

(BINARY - 180000 WORDS/RECORD - DOUBLE PRECISION/
Sigma1

42000 WORDS/RECORD - SINLGE PRECISION)
Sigma1

Sigma1

OPTIONAL
STANDARD FILE NAMES (SEE SUBROUTINE FILEIO)
Sigma1

----------------------------------------------------
Sigma1

UNIT  FILE NAME
Sigma1

----  ----------
Sigma1

2   SIGMA1.INP
Sigma1

3   SIGMA1.LST
Sigma1

10   ENDFB.IN
Sigma1

11   ENDFB.OUT
Sigma1

12   (SCRATCH)
Sigma1

Sigma1

INPUT CARDS
Sigma1

-----------
Sigma1

CARD  COLS.  DESCRIPTION
Sigma1

----  -----  -----------
Sigma1

1   1-11  SELECTION CRITERIA (0=MAT, 1=ZA)
Sigma1

12-22  MONITOR MODE SELECTOR
Sigma1

= 0 - NORMAL OPERATION
Sigma1

= 1 - MONITOR PROGRESS OF DOPPLER BROADENING OF DATA. Sigma1

EACH
TIME A PAGE OF DATA POINTS IS WRITTEN TO   Sigma1

THE SCRATCH FILE PRINT OUT THE TOTAL NUMBER OF  Sigma1

POINTS ON SCRATCH AND THE LOWER AND UPPER
Sigma1

ENERGY LIMITS OF THE PAGE
(THIS OPTION MAY BE
Sigma1

USED IN ORDER TO MONITOR THE EXECUTION SPEED    Sigma1

OF LONG RUNNING JOBS).
Sigma1

23-33  KELVIN TEMPERATURE
Sigma1

34-44  MINIMUM CROSS SECTION
OF INTEREST
Sigma1

(DEFAULT VALUE = 1.0E-10 BARNS).
Sigma1

45-55  NEGATIVE CROSS SECTION
TREATMENT
Sigma1

= 0 - O.K. - NO CHANGE
Sigma1

= 1 - SET = 0
Sigma1

56-66  UNRESOLVED RESONANCE
REGION TREATMENT
Sigma1

= 0 - COPY (NO BROADENING)
Sigma1

= 1 - IGNORE (BROADEN)
Sigma1

2   1-60  ENDF/B INPUT DATA FILENAME
Sigma1

(STANDARD OPTION = ENDFB.IN)
Sigma1

3   1-60  ENDF/B OUTPUT DATA FILENAME
Sigma1

(STANDARD OPTION = ENDFB.OUT)
Sigma1

4-N   1-11  LOWER MAT OR ZA LIMIT
Sigma1

12-22  UPPER MAT OR ZA
LIMIT
Sigma1

UP TO 100 MAT OR ZA RANGES MAY BE SPECIFIED, ONE      Sigma1

RANGE
PER CARD. THE LIST OF RANGES IS TERMINATED BY   Sigma1

A BLANK CARD. IF THE UPPER LIMIT IS LESS THAN THE     Sigma1

LOWER LIMIT THE UPPER LIMIT WILL BE SET EQUAL TO THE  Sigma1

LOWER
LIMIT. IF THE FIRST REQUEST CARD IS BLANK IT    Sigma1

WILL TERMINATE THE LIST OF REQUESTS AND CAUSE ALL     Sigma1

DATA TO BE RETRIEVED (SEE EXAMPLE INPUT).
Sigma1

VARY  1-11  ENERGY FOR ERROR LAW
Sigma1

12-22  ERROR FOR ERROR
LAW
Sigma1

THE ACCEPTABLE LINEARIZING ERROR CAN BE GIVEN AS AN   Sigma1

ENERGY DEPENDENT FUNCTION SPECIFIED BY UP TO 20
Sigma1

(ENERGY,ERROR) PAIRS AND LINEAR INTERPOLATION
Sigma1

TABULATE POINTS. ENERGIES MUST BE IN ASCENDING ORDER. Sigma1

THE ERROR LAW IS TERMINATED BY A BLANK CARD. IF THE   Sigma1

FIRST ERROR LAW CARD IS BLANK IT WILL TERMINATE THE   Sigma1

ERROR LAW AND THE ERROR WILL BE TREATED AS ENERGY     Sigma1

INDEPENDENT, EQUAL TO ZERO, WHICH INDICATES THAT THE  Sigma1

BROADENED DATA SHOULD NOT BE THINNED.
Sigma1

Sigma1

EXAMPLE INPUT
NO. 1
Sigma1

-------------------
Sigma1

BROADEN ALL
URANIUM ISOTOPES AND THORIUM-232 TO 300 KELVIN. FROM   Sigma1

0 TO 100 EV THIN
OUTPUT DATA TO 0.1 PER-CENT ACCURACY. FROM 100 EV Sigma1

TO 1 KEV VARY
THE ERROR BETWEEN 0.1 AND 1 PER-CENT. ABOVE 1 KEV    Sigma1

USE 1 PER-CENT
ACCURACY.
Sigma1

Sigma1

EXPLICITLY
SPECIFY THE STANDARD FILENAMES.
Sigma1

Sigma1

THE FOLLOWING 11
CARDS ARE REQUIRED
Sigma1

Sigma1

1
0 3.00000+ 2
Sigma1

ENDFB.IN
Sigma1

ENDFB.OUT                                                              Sigma1

92000      92999
Sigma1

90232
(UPPER LIMIT WILL AUTOMATICALLY BE DEFINED)   Sigma1

(BLANK CARD INDICATES END OF REQUEST LIST)    Sigma1

0.00000+ 0 1.00000-03
Sigma1

1.00000+ 2 1.00000-03
Sigma1

1.00000+ 3 1.00000-02
Sigma1

1.00000+ 9 1.00000-02
Sigma1

(BLANK CARD INDICATES END OF ERROR LAW)
Sigma1

Sigma1

EXAMPLE INPUT
NO. 2
Sigma1

-------------------
Sigma1

BROADEN ALL DATA
TO 300 KELVIN AND DO NOT THIN THE BROADEN DATA.   Sigma1

ALL OF THE
STANDARD OPTION MAY BE INVOKED MERELY BY SPECIFYING     Sigma1

THE KELVIN
TEMPERATURE ON THE FIRST CARD. ALL OTHER FIELDS MAY     Sigma1

BE LEFT
BLANK.
Sigma1

Sigma1

LEAVE THE
DEFINITION OF THE FILENAMES BLANK - THE PROGRAM WILL     Sigma1

THEN USE
STANDARD FILENAMES.
Sigma1

Sigma1

THE FOLLOWING 5
CARDS ARE REQUIRED
Sigma1

Sigma1

3.00000+
2
Sigma1

(USE STANDARD FILENAME = ENDFB.IN)
Sigma1

(USE STANDARD FILENAME = ENDFB.OUT)
Sigma1

(RETRIEVE
ALL DATA, TERMINATE REQUEST LIST)      Sigma1

(0.0 ALLOWABLE ERROR, TERMINATE ERROR LAW)
Sigma1

Sigma1

EXAMPLE INPUT
NO. 3                                                Sigma1

-------------------
Sigma1

THE SAME AS
ABOVE, ONLY DEFINE THE MINIMUM CROSS SECTION OF
Sigma1

INTEREST TO BE
1.0E-30 BARNS (INSTEAD OF THE DEFAULT VALUE OF      Sigma1

1.0E-10).
Sigma1

Sigma1

READ ENDF/B DATA
FROM \ENDFB6\RECENT\ZA092238 AND WRITE ENDF/B     Sigma1

DATA TO
\ENDFB\SIGMA1\ZA092238
Sigma1

Sigma1

THE FOLLOWING 5
CARDS ARE REQUIRED
Sigma1

Sigma1

3.00000+ 2 1.00000-30
Sigma1

\ENDFB6\RECENT\ZA092238
Sigma1

\ENDFB6\SIGMA1\ZA092238
Sigma1

(RETRIEVE ALL DATA, TERMINATE REQUEST LIST)      Sigma1

(0.0 ALLOWABLE ERROR, TERMINATE ERROR LAW)       Sigma1

Sigma1

=======================================================================
Sigma1

=======================================================================
Sixpak

Sixpak

PROGRAM
SIXPAK
Sixpak

==================================================================
Sixpak

VERSION 92-1
(JANUARY 1992)
Sixpak

VERSION 92-2
(FEBRUARY 1992)*INCREASED CORE ALLOCATION TO
Sixpak

ACCOMMODATE JEF AND EFF EVALUATIONS.  Sixpak

VERSION 92-3
(APRIL 1992)   *ADDED
ADDITIONAL DATA TESTS.
Sixpak

VERSION 92-4
(SEPT. 1992)   *CORRECTED
KALBACH-MANN CALCULATIONS.  Sixpak

*FOR PHOTON PRODUCTION OUTPUT MF=12    Sixpak

(MULTIPLICITY), MF=14 (ISOTROPIC      Sixpak

ANGULAR DISTRIBUTIONS) AND MF=15      Sixpak

(SPECTRA) - PREVIOUSLY ONLY MF=15.    Sixpak

*FIRST ORDER CORRECTIONS TRANSFORMING  Sixpak

CENTER-OF-MASS SPECTRA TO LAB SYSTEM  Sixpak

FOR OUTPUT IN MF=5
Sixpak

*CORRECTED ISOTROPIC ANGULAR
Sixpak

DISTRIBUTION FLAG (LI)
Sixpak

VERSION 94-1
(JANUARY 1994) *VARIABLE ENDF/B INPUT DATA FILENAME   Sixpak

TO ALLOW ACCESS TO FILE STRUCTURES    Sixpak

(WARNING - INPUT PARAMETER FORMAT     Sixpak

HAS BEEN CHANGED)
Sixpak

*CLOSE ALL FILES BEFORE TERMINATING    Sixpak

(SEE, SUBROUTINE ENDIT)
Sixpak

*INCREASED MAXIMUM TABLE SIZE FROM     Sixpak

2000 TO 6000.
Sixpak

VERSION 96-1 (JANUARY 1996) *COMPLETE
RE-WRITE
Sixpak

*IMPROVED COMPUTER INDEPENDENCE
Sixpak

*ALL DOUBLE PRECISION
Sixpak

*ON
SCREEN OUTPUT
Sixpak

*UNIFORM TREATMENT OF ENDF/B I/O
Sixpak

*IMPROVED OUTPUT PRECISION
Sixpak

VERSION 99-1
(MARCH 1999)   *CORRECTED
CHARACTER TO FLOATING
Sixpak

POINT READ FOR MORE DIGITS
Sixpak

*UPDATED TEST FOR ENDF/B FORMAT
Sixpak

VERSION BASED ON RECENT FORMAT CHANGE Sixpak

*GENERAL IMPROVEMENTS BASED ON
Sixpak

USER FEEDBACK
Sixpak

VERSION 99-2
(JUNE 1999)    *ASSUME ENDF/B-VI,
NOT V, IF MISSING   Sixpak

MF=1, MT-451.
Sixpak

VERS. 2000-1
(FEBRUARY 2000)*GENERAL IMPROVEMENTS BASED ON
Sixpak

USER FEEDBACK                         Sixpak

VERS. 2002-1
(JANUARY 2002) *CORRECTED ANGULAR DISTRIBUTION (MF=4) Sixpak

OUTPUT TO INSURE USED FIELDS ARE 0    Sixpak

(MAY 2002)
*OPTIONAL INPUT PARAMETERS             Sixpak

(NOV. 2002)
*EXTENDED TO ALLOW CHARGED PARTICLE    Sixpak

ANGULAR DISTRIBUTION IN MF=4 -
Sixpak

WARNING - STRICTLY SPEAKING THIS IS   Sixpak

NOT LEGAL, SINCE MF=4 IS SUPPOSED TO  Sixpak

BE USED ONLY FOR NEUTRON ANGULAR      Sixpak

DISTRIBUTIONS - BUT WHERE MT MAKES    Sixpak

IT
OBVIOUS THAT THE OUTGOING PARTICLE Sixpak

IS NOT A NEUTRON HOPEFULLY IT WILL    Sixpak

NOT CAUSE A PROBLEM IF MF=4 IS USED   Sixpak

FOR
CHARGED PARTICLES.
Sixpak

VERS. 2004-1
(MARCH 2004)   *ADDED INCLUDE
FOR COMMON
Sixpak

*INCREASED MAXIMUM TABLE SIZE FROM     Sixpak

6,000
TO 12,000.
Sixpak

*ADDED DUMMY A FOR ELEMENTS
Sixpak

*CORRECTED OUTPUT INTERPOLATON LAWS    Sixpak

VERS. 2007-1
(JAN.  2007)   *CHECKED AGAINST ALL ENDF/B-VII.
Sixpak

*INCREASED MAXIMUM TABLE SIZE FROM     Sixpak

12,000 TO 120,000.
Sixpak

Sixpak

OWNED,
MAINTAINED AND DISTRIBUTED BY
Sixpak

------------------------------------
Sixpak

THE NUCLEAR DATA
SECTION
Sixpak

INTERNATIONAL
ATOMIC ENERGY AGENCY
Sixpak

P.O. BOX 100
Sixpak

A-1400, VIENNA, AUSTRIA
Sixpak

EUROPE
Sixpak

Sixpak

ORIGINALLY
WRITTEN BY
Sixpak

------------------------------------
Sixpak

DERMOTT E.
CULLEN
Sixpak

UNIVERSITY OF CALIFORNIA
Sixpak

LAWRENCE
LIVERMORE
NATIONAL LABORATORY
Sixpak

L-159
Sixpak

P.O. BOX 808
Sixpak

LIVERMORE, CA
94550
Sixpak

U.S.A.
Sixpak

TELEPHONE  925-423-7359
Sixpak

E. MAIL    [email-masked]
Sixpak

WEBSITE
HTTP://WWW.LLNL.GOV/CULLEN1
Sixpak

Sixpak

COLLABORATION
Sixpak

==================================================================
Sixpak

DEVELOPED IN
COLLABORATION WITH,
Sixpak

Sixpak

*THE NATIONAL
NUCLEAR DATA CENTER, BROOKHAVEN NATIONAL LAB
Sixpak

Sixpak

*THE NUCLEAR
DATA SECTION, IAEA, VIENNA,
AUSTRIA
Sixpak

Sixpak

*CENTRO TECNICO
AEROSPACIAL, SAO JOSE DOS CAMPOS,
BRAZIL
Sixpak

Sixpak

AS A PART OF AN
INTERNATIONAL PROJECT ON THE EXCHANGE OF
Sixpak

NUCLEAR
DATA
Sixpak

Sixpak

ACKNOWLEDGEMENT
(VERSION 92-1)
Sixpak

==================================================================
Sixpak

THE AUTHOR
THANKS SOL PEARLSTEIN (BROOKHAVEN NATIONAL LAB) FOR     Sixpak

SIGNIFICANTLY
CONTRIBUTING TOWARD IMPROVING THE ACCURACY AND
Sixpak

COMPUTER
INDEPENDENCE OF THIS CODE - THANKS, SOL
Sixpak

Sixpak

ACKNOWLEDGEMENT
(VERSION 92-4)
Sixpak

==================================================================
Sixpak

THE AUTHOR
THANKS BOB MACFARLANE (LOS ALAMOS) FOR SUGGESTING HOW   Sixpak

TO PROPERLY OUTPUT
THE PHOTON PRODUCTION DATA TO PUT IT INTO
Sixpak

EXACTLY THE FORM
NEEDED FOR USE IN PROCESSING CODES.
Sixpak

Sixpak

THE AUTHOR
THANKS CHRIS DEAN (WINFRITH) FOR POINTING OUT ERRORS    Sixpak

IN THE EARLIER
TREATMENT OF THE KALBACH-MANN FORMALISM AND IN      Sixpak

THE DEFINITION
OF THE ISOTROPIC ANGULAR DISTRIBUTION FLAG (LI).    Sixpak

Sixpak

AUTHORS
MESSAGE
Sixpak

==================================================================
Sixpak

THE COMMENTS
BELOW SHOULD BE CONSIDERED THE LATEST DOCUMENTATION   Sixpak

INCLUDING ALL
RECENT IMPROVEMENTS. PLEASE READ ALL OF THESE
Sixpak

COMMENTS BEFORE
IMPLEMENTING AND USING THESE CODES.
Sixpak

Sixpak

AT THE PRESENT
TIME WE ARE ATTEMPTING TO DEVELOP A SET OF COMPUTER Sixpak

INDEPENDENT
PROGRAMS THAT CAN EASILY BE IMPLEMENTED ON ANY ONE     Sixpak

OF A WIDE
VARIETY OF COMPUTERS. IN ORDER TO ASSIST IN THIS PROJECT Sixpak

IT WOULD BE
APPECIATED IF YOU WOULD NOTIFY THE AUTHOR OF ANY
Sixpak

COMPILER
DIAGNOSTICS, OPERATING PROBLEMS OR SUGGESTIONS ON HOW TO  Sixpak

IMPROVE THIS
PROGRAM. HOPEFULLY, IN THIS WAY FUTURE VERSIONS OF    Sixpak

THIS PROGRAM
WILL BE COMPLETELY COMPATIBLE FOR USE ON YOUR
Sixpak

COMPUTER.
Sixpak

Sixpak

PURPOSE
Sixpak

==================================================================
Sixpak

1) CHECK ALL
DOUBLE-DIFFERENTIAL DATA (MF=6)
Sixpak

Sixpak

2) OUTPUT
EQUIVALENT MF = 4, 5, 12, 14 AND 15 DATA.
Sixpak

Sixpak

DATA
CHECKING                                                      Sixpak

==================================================================
Sixpak

ALL OF THE
ENDF/B-VI MF=6 DATA IS CHECKED - FOR DETAILS SEE BELOW. Sixpak

Sixpak

THE MF=6 DATA IS
NOT CORRECTED AND OUTPUT IN THE ENDF/B FORMAT.    Sixpak

IT IS MERELY
CHECKED. IF ERRORS ARE FOUND IT IS UP TO THE USER     Sixpak

TO TAKE
CORRECTIVE ACTION ON THE MF=6 DATA.
Sixpak

Sixpak

IN CONTRAST WHEN
PROBLEMS ARE FOUND IN DATA WHICH WILL BE OUTPUT   Sixpak

IN THE ENDF/B
FORMAT (MF=4, 5, 12, 14 AND 15), WHENEVER POSSIBLE   Sixpak

CORRECTIVE
ACTION WILL BE TAKEN.
Sixpak

Sixpak

FURTHER CHECKS
AND CORRECTIONS
Sixpak

==================================================================
Sixpak

ONCE THE DATA
HAS BEEN OUTPUT IN MF = 4, 5, 12, 14 AND 15 FORMATS  Sixpak

FURTHER
CORRECTIVE ACTION CAN BE TAKEN AS FOLLOWS,
Sixpak

Sixpak

PROGRAM
LEGEND
Sixpak

==============
Sixpak

CAN BE USED TO CORRECT ANGULAR
DISTRIBUTIONS WHICH ARE NEGATIVE,
Sixpak

TO CONVERT FROM
LEGENDRE COEFFICIENTS TO TABULATED ANGULAR
Sixpak

DISTRIBUTIONS
AND GENERALLY PERFORM MORE EXTENSIVE TESTS OF
Sixpak

ALL MF=4 DATA.
Sixpak

Sixpak

PROGRAM
EVALPLOT
Sixpak

================                                                   Sixpak

VERSION 92-1 AND
LATER VERSIONS CAN PLOT ALL OF THE MF=4, 5 AND 15 Sixpak

DATA OUTPUT BY
THIS CODE. EARLIER VERSIONS CAN PLOT MF=4 AND 5.    Sixpak

GRAPHICS IS AN
EXCELLENT WAY TO CHECK THIS DATA.
Sixpak

Sixpak

PROGRAM
PLOTTAB
Sixpak

===============
Sixpak

THIS IS A
GENERAL PLOTTING PROGRAM AND THERE IS AN INTERFACE IN    Sixpak

THIS CODE TO
PRODUCE OUTPUT FOR ANY MF=6 DATA IN THE PLOTTAB
Sixpak

INPUT FORMAT.
THIS PROGRAM CAN BE USED TO CHECK ALL OF THE MF=6    Sixpak

DATA AS WELL AS
THE EQUIVALENT MF=4, 5, 12, 14 AND 15 DATA - AS    Sixpak

WELL AS
COMPARING THE ORIGINAL MF=6 AND EQUIVALENT DATA.
Sixpak

Sixpak

DATA OUTPUT
Sixpak

==================================================================
Sixpak

THE ENDF/B MF=4,
5, 12, 14 AND 15 FORMATS ONLY ALLOW FOR NEUTRONS  Sixpak

INCIDENTS
Sixpak

Sixpak

THE ENDF/B MF=4
AND 5 FORMATS ONLY ALLOW FOR NEUTRONS OUTGOING.    Sixpak

Sixpak

THE ENDF/B
MF=12, 14 AND 15 ONLY ALLOWS FOR PHOTONS OUTGOING.      Sixpak

Sixpak

THESE ARE THE
ONLY COMBINATIONS OF DATA OUTPUT BY THIS CODE.
Sixpak

Sixpak

ALL OTHER
COMBINATIONS OF INCIDENT AND OUTGOING PARTICLES ARE      Sixpak

CHECKED, BUT THE
RESULTS CANNOT BE OUTPUT IN THE ENDF/B FORMAT.    Sixpak

HOWEVER, USING
THE PLOTTAB INTERFACE BUILT INTO THIS CODE THIS     Sixpak

DATA CAN, AND
HAS BEEN, OUTPUT AND CHECKED.
Sixpak

Sixpak

THE NEUTRON DATA
IN MF=4 CAN BE IN THE FORM OF EITHER TABULATED    Sixpak

ANGULAR
DISTRIBUTIONS OR LEGENDRE COEFFICIENTS.
Sixpak

Sixpak

THE NEUTRON
(MF=5) OR PHOTON (MF=15) SPECTRA ARE BOTH IN EXACTLY   Sixpak

THE SAME FORMAT
= ARBITRARY TABULATED FUNCTIONS - ENDF/B OPTION    Sixpak

LF=1.
Sixpak

Sixpak

ENDF/B DATA
OUTPUT ORDER
Sixpak

==================================================================
Sixpak

ENDF/B DATA IS
OUTPUT IN ASCENDING MAT, MF, MT ORDER. IN ORDER TO  Sixpak

ALLOW THIS
PROGRAM TO PRODUCE ALL OUTPUT IN A SINGLE PASS THROUGH  Sixpak

THE MF=6 DATA,
OUTPUT FOR EACH (MAT, MT) IS OUTPUT TO SEPERATE     Sixpak

FILES FOR MF=4,
5, 12, 14 AND 15.
Sixpak

Sixpak

FOR SUBSEQUENT
USE THE ENDF/B FORMATTED DATA OUTPUT BY THIS CODE   Sixpak

CAN BE MERGED TOGETHER
USING PROGRAM MERGER (CONTAIN THE AUTHOR    Sixpak

OF THIS CODE FOR
A COPY OF MERGER), E.G., MERGE MF=12, 14 AND 15   Sixpak

DATA IN ORDER TO
THEN CALCULATE PHOTON PRODUCTION DATA OR MF=4     Sixpak

AND 5 CAN BE
MERGED TOGETHER TO CALCULATE NEUTRON TRANSFER - OR    Sixpak

ALL OF THEM CAN
BE MERGED TOGETHER TO PERFORM NEUTRON AND PHOTON   Sixpak

CALCULATIONS.
Sixpak

Sixpak

CORRELATED
(MF=6) VS. UNCORRELATED (MF=4 AND 5) DATA
Sixpak

==================================================================
Sixpak

THE ENDF/B
DOUBLE DIFFERENTAL = CORRELATED - DATA IN MF=6
Sixpak

REPRESENTS DATA
IN THE FORM,
Sixpak

Sixpak

F(E,EP,COS) =
SIG(E)*Y(E)*G0(E,EP)*F(E,EP,COS)
Sixpak

Sixpak

SIG(E)      = MF=3 CROSS
SECTIONS
Sixpak

Y(E)        =
YIELD (MULTIPLICITY)
Sixpak

G0(E,EP)    = ENERGY SPECTRUM
Sixpak

F(E,EP,COS) =
ANGULAR DISTRIBUTION
Sixpak

Sixpak

IN A SITUATION
WHERE YOU HAVE MONOENERGETIC AND MONODIRECTIONAL    Sixpak

NEUTRONS
INCIDENT YOU WILL BE ABLE TO OBSERVE CORRELATION EFFECTS  Sixpak

IN THE NEUTRON
SPECTRUM AND ANGULAR DISTRIBUTION.
Sixpak

Sixpak

EVEN IN
SITUATIONS WHERE YOU HAVE A NARROW SPECTRUM OF NEUTRONS    Sixpak

THAT ARE HIGHLY
DIRECTIONALLY ORIENTED YOU MAY BE ABLE TO OBSERVE  Sixpak

THESE
CORRELATION EFFECTS, E.G., A NARROW 14 MEV FUSION SOURCE     Sixpak

INCIDENT ON THE
FIRST WALL OF A CTR DEVICE.
Sixpak

Sixpak

FOR SUCH
SITUATIONS USE OF THE CORRELATED (MF=6) DATA IS REQUIRED  Sixpak

IN
CALCULATIONS.
Sixpak

Sixpak

HOWEVER, IN MANY
APPLICATIONS WHERE THERE IS A BROAD SPECTRUM OF   Sixpak

NEUTRONS AND THE
NEUTRON FLUX IS NOT HIGHLY DIRECTIONALLY
Sixpak

ORIENTED, THE
NEUTRON MULTIPLICATION, SPECTRUM AND ORIENTATION     Sixpak

CAN BE FAIRLY
ACCURATELY CALCULATED WITHOUT CONSIDERING
Sixpak

CORRELATION
EFFECTS.
Sixpak

Sixpak

THE UNCORRELATED
DATA PRODUCED BY THIS CODE REPLACES THE
Sixpak

CORRELATED
DATA,
Sixpak

Sixpak

F(E,EP,COS) =
SIG(E)*Y(E)*G0(E,EP)*F(E,EP,COS)
Sixpak

Sixpak

BY THE
UNCORRELATED DATA,
Sixpak

Sixpak

F(E,EP,COS) =
SIG(E)*Y(E)*G0(E,EP)*F0(E,COS)
Sixpak

Sixpak

BY INTEGRATING
G0(E,EP)*F(E,EP,COS) OVER SECONDARY ENERGY (EP)     Sixpak

TO DEFINE AN
AVERAGE ANGULAR DISTRIBUTION, F0(E,COS).
Sixpak

Sixpak

WHAT IS LOST IN
THIS PROCESS IS THE CORRELATION BETWEEN EP AND COS Sixpak

SO THAT IN A
TRANSPORT CALCULATION ALL MOMENTS OF THE FLUX WILL    Sixpak

HAVE THE SAME
SPECTRUM, G0(E,EP) AND EACH WILL BE EFFECTED BY THE  Sixpak

AVERAGE ANGULAR
DISTRIBUTION.
Sixpak

Sixpak

FOR APPLICATIONS
TO HIGH ENERGY FUSION APPLICATIONS CORRELATED     Sixpak

DATA SHOULD BE
USED. HOWEVER, FOR LOWER ENERGY APPLICATIONS,
Sixpak

SUCH AS FISSION
REACTORS, IT SHOULD BE ADEQUATE TO USE THE
Sixpak

UNCORRELATED
DATA - IN THIS CASE THE MOST IMPORTANT EFFECT
Sixpak

WILL BE THE
OVERALL NEUTRON MULTIPLICATION AND SPECTRUM.
Sixpak

Sixpak

AN IMPORTANT
CONSIDERATION IN DESIGNING THIS PROGRAM IS THAT
Sixpak

MANY COMPUTER
CODES - DATA PROCESSING AND TRANSPORT CODES -
Sixpak

CANNOT USE THE
CORRELATED (MF=6) DATA - NOR ARE THEY INTENDED      Sixpak

FOR HIGH ENERGY
USE. FOR THESE CODES THE UNCORRELATED DATA
Sixpak

PRODUCED BY THIS
CODE SHOULD BE ADEQUATE TO MEET THEIR NEEDS.      Sixpak

Sixpak

WARNING - IT
CANNOT BE STRESSED ENOUGH THAT THE OUTPUT OF THIS     Sixpak

CODE SHOULD ONLY
BE USED FOR LOW ENERGY APPLICATIONS - FAILURE     Sixpak

TO HEED THIS
WARNING CAN LEAD TO COMPLETELY UNRELIABLE RESULTS.    Sixpak

Sixpak

ENDF/B
FORMAT
Sixpak

==================================================================
Sixpak

THIS PROGRAM
ONLY USES THE ENDF/B BCD OR CARD IMAGE FORMAT (AS     Sixpak

OPPOSED TO THE
BINARY FORMAT) AND CAN HANDLE DATA IN ANY VERSION   Sixpak

OF THE ENDF/B
FORMAT (I.E., ENDF/B-I, II,III, IV, V OR VI FORMAT). Sixpak

Sixpak

IT IS ASSUMED
THAT THE DATA IS CORRECTLY CODED IN THE ENDF/B
Sixpak

FORMAT AND NO
ERROR CHECKING IS PERFORMED. IN PARTICULAR IT IS     Sixpak

ASSUMED THAT THE MAT,
MF AND MT ON EACH LINE IS CORRECT. SEQUENCE  Sixpak

NUMBERS (COLUMNS
76-80) ARE IGNORED ON INPUT, BUT WILL BE
Sixpak

CORRECTLY OUTPUT
ON ALL LINES. THE FORMAT OF SECTION MF=1, MT=451  Sixpak

AND ALL SECTIONS
OF MF=6 MUST BE CORRECT. THE PROGRAM SKIPS ALL    Sixpak

OTHER SECTIONS
OF DATA AND AS SUCH IS INSENSITIVE TO THE FORMAT    Sixpak

OF ALL OTHER
SECTIONS.
Sixpak

Sixpak

CONTENTS OF
OUTPUT
Sixpak

==================================================================
Sixpak

5 ENDF/B
FORMATTED OUTPUT FILES ARE PRODUCED FOR NEUTRON INCIDENT  Sixpak

DATA,
Sixpak

Sixpak

1) ENDFB.MF4 -
ANGULAR DISTRIBUTIONS AND LEGENDRE COEFFICIENTS     Sixpak

FOR NEUTRONS
Sixpak

2) ENDFB.MF5 -
TABULATED NEUTRON ENERGY SPECTRA
Sixpak

3) ENDFB.M12 -
PHOTON EMISSION MULTIPLICITY                        Sixpak

4) ENDFB.M14 -
PHOTON EMISSION ANGULAR DISTRIBUTIONS (ALWAYS
Sixpak

ISOTROPIC)
Sixpak

5) ENDFB.M15 -
TABULATED PHOTON EMISSION SPECTRA
Sixpak

Sixpak

EMITTED PARTICLE
YIELD
Sixpak

================================================================== Sixpak

NEUTRONS
Sixpak

========
Sixpak

IN MF=6 THE
YIELD FOR EACH REACTION IS THE ACTUAL MULTIPLICITY OF  Sixpak

THE REACTION, E.G.,
(N,2N) = 2. IN USING MF=4 AND 5 DATA THE
Sixpak

ENDF/B
CONVENTION IS THAT THE MULTIPLICITY IS IMPLIED BY THE
Sixpak

MT NUMBER, E.G.,
MT=16 = (N,2N) = 2.
Sixpak

Sixpak

THE ONLY EXCEPT
IN ENDF/B-VI IS MT=201 = TOTAL NEUTRON PRODUCTION  Sixpak

WHERE AN ACTUAL
ENERGY DEPENDENT YIELD IS INCLUDED IN MF=6.
Sixpak

HOWEVER, IN THIS
CASE THE MF=3 CROSS SECTION INCLUDES THE
Sixpak

MULTIPLICITY (S.
PEARLSTEIN, PRIVATE COMMUNICATION, JAN. 1992),    Sixpak

SIG(MT=201) =
2*SIG(N,2N)+3*SIG(N,3N).....ETC.
Sixpak

Sixpak

SO THAT FOR ALL
ENDF/B-VI DATA AS OF JANUARY 1992 THE MF=4 AND 5   Sixpak

DATA OUTPUT BY
THIS CODE CAN BE USED IN CONJUNCTION WITH THE MF=3  Sixpak

CROSS SECTIONS -
WITHOUT ANY REFERENCE TO THE MF=6 YIELD.
Sixpak

Sixpak

PHOTONS
Sixpak

=======
Sixpak

UNLIKE THE
NEUTRONS WHERE WITH ONLY ONE EXCEPTION (MT=201) THE     Sixpak

MF=6 YIELD IS
ENERGY INDEPENDENT, IN THE CASE OF PHOTON EMISSION   Sixpak

ALMOST ALL OF
THE PHOTONS HAVE AN ENERGY DEPENDENT YIELD.
Sixpak

Sixpak

THIS PROGRAM
WILL OUTPUT THE PHOTON MULTIPLICITY IN MF=12 AND      Sixpak

INDICATE THAT
THERE IS A NORMALIZED DISTRIBUTION IN MF=15
Sixpak

(LF=1 IN
MF=12).
Sixpak

Sixpak

THIS PROGRAM
WILL OUTPUT THE NORMALIZED PHOTON SPECTRA IN MF=15.   Sixpak

CONTINUOUS
ENERGY SPECTRA AND DISCRETE PHOTONS WILL ALL BE OUTPUT  Sixpak

AS NORMALIZED
SPECTRA.
Sixpak

Sixpak

THIS PROGRAM
WILL ALSO OUTPUT MF=14 PHOTON ANGULAR DISTRIBUTION    Sixpak

DATA, ALWAYS
USING THE ISOTROPIC FLAG TO MINIMIZE OUTPUT.
Sixpak

Sixpak

WARNING OF ENERGY
DEPENDENT YIELD
Sixpak

=================================
Sixpak

THIS PROGRAM
WILL PRINT A WARNING MESSAGE IF A SECTION OF DATA     Sixpak

BEING OUTPUT IN
THE ENDF/B FORMAT HAS AN ENERGY DEPENDENT MF=6     Sixpak

YIELD AND THE
EMITTED PARTICLE IS A NEUTRON - SINCE THE ENDF/B     Sixpak

CONVENTION IS
THAT FOR EACH MT NUMBER THE MULTIPLICITY IS IMPLIED  Sixpak

WE DO NOT EXPECT
AN ENERGY DEPENDENT MULTIPLICITY FOR NEUTRON      Sixpak

EMISSION.
Sixpak

Sixpak

USING THE
OUTPUT
Sixpak

==================================================================
Sixpak

NOTE, THAT IN
USING THIS DATA, STARTING FROM THE RELATIONSHIP,     Sixpak

Sixpak

F(E,EP,COS) =
SIG(E)*Y(E)*G0(E,EP)*F0(E,COS)
Sixpak

Sixpak

USING THE ENDF/B
CONVENTION THAT THE MULTIPLICITY IS EITHER        Sixpak

IMPLIED BY THE
MT NUMBER (E.G., MT=16 = N,2N - MULTIPLICITY = 2)   Sixpak

OR INCLUDED IN
THE CROSS SECTION (E.G., MT=201 = TOTAL NEUTRON     Sixpak

PRODUCTION) ALL
THE INFORMATION REQUIRED FOR A CALCULATION IS      Sixpak

AVAILABLE
IN,
Sixpak

Sixpak

MF=3       -
SIG(E)
Sixpak

MF=4       -
F0(E,COS) - FOR OUTGOING NEUTRONS
Sixpak

MF=5       -
G0(E,EP)  - FOR OUTGOING NEUTRONS
Sixpak

MF=12      - Y(E)      - FOR OUTGOING
PHOTONS
Sixpak

MF=14      - F0(E,COS) -
FOR OUTGOING PHOTONS (ALWAYS ISOTROPIC)   Sixpak

MF=15      - G0(E,EP)  - FOR OUTGOING PHOTONS
Sixpak

Sixpak

DOCUMENTATION
Sixpak

==================================================================
Sixpak

ONLY SECTIONS OF
MF=4, 5, 12, 14, 15 ARE OUTPUT ON A ENDF/B FILE.  Sixpak

THE ONLY
DOCUMENTATION IS THE ENDF/B TAPE LABEL (FIRST RECORD OF   Sixpak

EACH FILE) WHICH
IDENTIFIES THE DATA AS SIXPAK OUTPUT.
Sixpak

Sixpak

REACTION
INDEX
Sixpak

==================================================================
Sixpak

THIS PROGRAM
DOES NOT USE THE REACTION INDEX WHICH IS GIVEN IN     Sixpak

SECTION MF=1,
MT=451 OF EACH EVALUATION.
Sixpak

Sixpak

SECTION
SIZE
Sixpak

==================================================================
Sixpak

ALL OF THE DATA
IN ENDF/B-VI, MF=6 ARE QUITE SMALL TABLES. AS SUCH Sixpak

THIS PROGRAM
ONLY ALLOWS TABLES OF UP TO 12000 POINTS (12,000 X,   Sixpak

Y VALUES). THIS
SIZE IS MORE THAN ADEQUATE TO HANDLE ALL OF THE    Sixpak

CURRENT
ENDF/B-VI DATA, AND IT CAN BE EASILY INCREASED TO HANDLE   Sixpak

ANY NEWER DATA
AS IT BECOMES AVAILABLE.
Sixpak

Sixpak

PLEASE CONTACT
THE AUTHOR IF YOU HAVE AN EVALUATION WHICH EXCEEDS  Sixpak

THIS LIMIT.
Sixpak

Sixpak

SELECTION OF
DATA
Sixpak

==================================================================
Sixpak

THE PROGRAM
SELECTS DATA TO BE PROCESSED BASED ON MAT/MT RANGES    Sixpak

(MF=6 ASSUMED).
THIS PROGRAM ALLOWS UP TO 100 MAT/MT RANGES TO BE  Sixpak

SPECIFIED BY
INPUT PARAMETERS. THE PROGRAM WILL ASSUME THAT THE    Sixpak

ENDF/B TAPE IS
IN MAT ORDER. THE PROGRAM WILL TERMINATE EXECUTION  Sixpak

WHEN A MAT IS
FOUND THAT IS ABOVE ALL REQUESTED MAT RANGES.
Sixpak

Sixpak

PROGRAM
OPERATION
Sixpak

==================================================================
Sixpak

EACH SECTION
(MT) OF MF=6 DATA IS SUBDIVIDED INTO SUBSECTIONS -    Sixpak

ONE SUBSECTION
FOR EACH EMITTED PARTICLE.
Sixpak

Sixpak

EACH SUBSECTION
OF DATA IS CONSIDERED SEPARATELY. EACH SUBSECTION  Sixpak

OF ENDF/B MF=6
DATA TO PROCESS IS IN THE FORM,
Sixpak

Sixpak

F(E,EP,COS) =
SIG(E)*Y(E)*G0(E,EP)*F(E,EP,COS)
Sixpak

Sixpak

SIG(E)      = MF=3 CROSS
SECTIONS
Sixpak

Y(E)        =
YIELD (MULTIPLICITY)
Sixpak

G0(E,EP)    = ENERGY SPECTRUM
Sixpak

F(E,EP,COS) =
ANGULAR DISTRIBUTION
Sixpak

Sixpak

G0(E,EP) = 1
WHEN INTEGRATED OVER EP (SECONDARY ENERGY)
Sixpak

G0(E,EP)*F(E,EP,COS) = 1 WHEN INTEGRATED OVER EP AND COS
Sixpak

Sixpak

THIS PROGRAM
WILL DEFINE THE ZEROTH ORDER MOMENTS OF THE
Sixpak

ENERGY AND
ANGULAR DISTRIBUTIONS,
Sixpak

Sixpak

G0(E,EP)  = G0(E,EP)*F(E,EP,COS) INTEGRATED OVER
COS
Sixpak

F0(E,COS) =
G0(E,EP)*F(E,EP,COS) INTEGRATED OVER EP
Sixpak

Sixpak

FOR NEUTRON
INDUCED REACTIONS THE ENDF/B FORMATTED OUTPUT WILL BE  Sixpak

Sixpak

F0(E,COS)- IN
ENDFB.MF4 FOR NEUTRONS OUT OF A REACTION
Sixpak

G0(E,EP) - IN
ENDFB.MF5 FOR NEUTRONS OUT OF A REACTION
Sixpak

- IN ENDFB.M15 FOR PHOTONS OUT OF A REACTION
Sixpak

Sixpak

FOR NEUTRONS
INCIDENT AND NEUTRONS EMITTED THIS DATA WILL BE
Sixpak

OUTPUT IN MF=4
AND 5 FORMATS.
Sixpak

Sixpak

FOR NEUTRONS
INCIDENT AND PHOTONS EMITTED THIS DATA WILL BE
Sixpak

OUTPUT IN MF=15
FORMAT - THE SPECTRA ARE OUTPUT AND THE
Sixpak

ANGULAR
DISTRIBUTION IS IGNORED.
Sixpak

Sixpak

ALL PHOTON
EMISSION IN THE ENDF/B-VI LIBRARY AS OF JANUARY 1992    Sixpak

IS ISOTROPIC AND
AS SUCH NO DISTRIBUTION OF PHOTON ANGULAR
Sixpak

DISTRIBUTIONS NEED BE
OUTPUT - IT IS ALWAYS ISOTROPIC.
Sixpak

Sixpak

FOR ALL OTHER
COMBINATIONS INCIDENT AND EMITTED PARTICLES
Sixpak

THERE WILL BE NO
ENDF/B FORMATTED OUTPUT.
Sixpak

Sixpak

VARIATIONS FROM
ENDF/B MANUAL
Sixpak

==================================================================
Sixpak

LAW=1, LANG=2 =
KALBACH-MANN
Sixpak

============================
Sixpak

FOR THE
DISTRIBUTIONS,                                             Sixpak

Sixpak

F(MU,E,EP) =
G0(E,EP)*A*(COSH(MU*A)+R(E,EP)*SINH(MU*A))
Sixpak

Sixpak

G0(E,EP) = 1 -
WHEN INTEGRATED OVER EP.
Sixpak

Sixpak

A*(COSH(MU*A)+R(E,EP)*SINH(MU*A)) = 2 - WHEN INTEGRATD OVER MU     Sixpak

Sixpak

THIS MEANS AS
DEFINED IN THE ENDF/B MANUAL THE DISTRIBUTIONS
Sixpak

ARE NORMALIZED
TO 2, INSTEAD OF 1. IN ORDER TO OBTAIN CORRECTLY    Sixpak

NORMALIZED
DISTRIBUTIONS THE DISTRIBUTION SHOULD BE DEFINED
Sixpak

TO INCLUDE A
FACTOR OF 1/2 MULTIPLYING THE ANGULAR PART OF
Sixpak

THE
DISTRIBUTION.
Sixpak

Sixpak

F(MU,E,EP) =
G0(E,EP)*0.5*A*(COSH(MU*A)+R(E,EP)*SINH(MU*A))
Sixpak

Sixpak

THIS IS THE FORM
USED IN THIS CODE
Sixpak

Sixpak

LAW=1, ND NOT 0
= DISCRETE SECONDARY ENERGY DISTRIBUTION
Sixpak

========================================================
Sixpak

THE ENDF/B
MANUAL SAYS THESE ARE FLAGGED WITH NEGATIVE ENERGIES.   Sixpak

IN ENDF/B-VI ALL
OF THESE HAVE POSITIVE ENERGY. THIS CODE DOES     Sixpak

NOT CONSIDER THE
ENDF/B-VI DATA TO BE IN ERROR.
Sixpak

Sixpak

WITH THE
CONVENTION ACTUALLY USED IN ENDF/B-VI ALL SECONDARY
Sixpak

ENERGIES SHOULD
BE NON-NEGATIVE AND IN ASCENDING ENERGY ORDER      Sixpak

FOR EACH
INCIDENT ENERGY.
Sixpak

Sixpak

FROM THE ENDF/B
MANUAL IT IS NOT OBVIOUS WHAT G0(E,EP) SHOULD BE   Sixpak

FOR DISCRETE
PHOTONS - PHYSICALLY THIS IS A DELTA FUNCTION. IN     Sixpak

ENDF/B-VI IT IS
ENTERED AS 1.0 = INTERPRETING IT AS INTEGRATED     Sixpak

OVER SECONDARY
ENERGY - IN WHICH CASE THE DELTA FUNCTION = 1.0.    Sixpak

Sixpak

LIMITATIONS
Sixpak

==================================================================
Sixpak

CHECKING
DATA
Sixpak

==================================================================
Sixpak

THIS PROGRAM
CHECKS ALL ENDF/B-VI MF=6 DATA. THE FOLLOWING CHECKS  Sixpak

ARE
PERFORMED.
Sixpak

Sixpak

PARAMETERS
Sixpak

==========
Sixpak

ALL PARAMETERS
ARE CHECKED FOR CONSISTENCY. IF PARAMETERS ARE      Sixpak

NOT CONSISTENT
THE PROGRAM MAY NOT BE ABLE TO PERFORM THE
Sixpak

FOLLOWING TESTS
AND WILL MERELY SKIP A SECTION OF DATA.
Sixpak

Sixpak

INTERPOLATION
LAWS
Sixpak

==================
Sixpak

ALL INTEGRATIONS
ARE PERFORMED USING THE INTERPOLATION LAW GIVEN   Sixpak

FOR SECONDARY
ENERGY AND/OR COSINE. INTEGRATIONS ARE NOT
Sixpak

PERFORMED OVER
INCIDENT - ONLY INTEGRATION OVER SECONDARY ENERGY   Sixpak

AND/OR COSINE
ARE PERFORMED AT EACH INCIDENT ENERGY. THEREFORE     Sixpak

THE
INTERPOLATION LAW FOR INCIDENT ENERGY IS NOT USED BY THIS      Sixpak

CODE.
Sixpak

Sixpak

ALL
INTERPOLATION LAWS ARE CHECKED. ALL DATA ASSOCIATED WITH
Sixpak

INTERPOLATION
LAWS ARE CHECKED, E.G., NO NON-NEGATIVE VALUES
Sixpak

REQUIRING LOG
INTERPOLATION. IN ORDER TO PERFORM REQUIRED
Sixpak

INTEGRALS OVER
COS AND EP IT IS IMPERATIVE THAT THE INTERPOLATION  Sixpak

LAWS BE
COMPATIBLE WITH THE DATA.
Sixpak

Sixpak

ENDF/B-VI ALLOWS
NEW INTERPOLATION LAWS FOR CORRESPONDING POINT    Sixpak

AND UNIT BASE
TRANSFORMATION INTERPOLATION. NONE OF THESE NEW      Sixpak

INTERPOLATION
LAWS ARE USED IN THE ENDF/B-VI LIBRARY AS OF
Sixpak

JANUARY 1992 TO
INTERPOLATE IN SECONDARY ENERGY OR COSINE.
Sixpak

THEREFORE THIS
PROGRAM CAN PERFORM ALL OF THE REQUIRED INTEGRALS   Sixpak

OVER SECONDARY
ENERGY AND/OR COSINE USING ONLY THE OLDER
Sixpak

INTERPOLATION
CODES. THIS PROGRAM ONLY PERFORMS INTEGRALS FOR      Sixpak

EACH INCIDENT
ENERGY, SO THAT INTERPOLATION IN INCIDENT ENERGY     Sixpak

IS NOT PERFORMED BY THIS PROGRAM.
Sixpak

Sixpak

NEW
INTERPOLATION SCHEMES ARE USED FOR INCIDENT ENERGY - FOR
Sixpak

EXAMPLE, CORRESPONDING
POINT INTERPOLATION IS SPECIFIED TO ALLOW   Sixpak

INTERPOLATION IN
G0(E,EP) TO SIMULATE CASES WHERE THE INPUT ENERGY Sixpak

LIMIT IS DEFINED
BY E-EP = A DIAGONAL CURVE ACROSS (E,EP) SPACE.   Sixpak

THIS
INTERPOLATION CODE CANNOT BE SPECIFIED IN THE MF=5 OUTPUT     Sixpak

OF THIS CODE -
MF=5 ONLY ALLOWS THE OLDER INTERPOLATION LAWS
Sixpak

INT=1 THROUGH 5.
THEREFORE THIS PROGRAM WILL USE THE CLOSEST
Sixpak

CORRESPONDING
INTERPOLATION CODE FOR OUTPUT TO MF=5. FOR USE
Sixpak

WHERE THE OUTPUT
OF THIS CODE = LOW ENERGY APPLICATIONS - THIS     Sixpak

SHOULD HAVE
LITTLE EFFECT ON RESULTS.
Sixpak

Sixpak

FOR CONSISTENCY
WITH EARLIER VERSIONS OF ENDF/B IN CREATING THE    Sixpak

ENDF/B OUTPUT,
IF ANY INPUT INTERPOLATION LAW IS NOT IN THE
Sixpak

RANGE 1-5, IT
WILL FIRST BE TESTED TO SEE IF MOD(10) IT IS
Sixpak

IN THIS RANGE,
FINALLY IF EVEN THIS DOESN'T WORK IT IS SET
Sixpak

EQUAL TO 2
(LINEARLY INTERPOLATION). THIS METHOD WILL EFFECTIVELY  Sixpak

REPLACE
CORRESPONDING POINT AND UNIT BASE TRANSFORMATION BY THE    Sixpak

CLOSEST RELATED
INTERPOLATION LAW 1 THROUGH 5 - AGAIN NOTE, AS     Sixpak

OF JANUARY 1992
NONE OF THESE NEW LAWS ARE USED IN ENDF/B-VI. IF   Sixpak

THIS MUST BE
DONE FOR INTERPOLATION IN SECONDARY ENERGY OR COSINE  Sixpak

AN ERROR MESSAGE
WILL BE PRINTED - SINCE THIS WOULD EFFECT THE     Sixpak

ACCURACY OF THE
INTEGRALS PERFORMED BY THIS PROGRAM. IF THIS MUST  Sixpak

BE DONE FOR
INCIDENT ENERGY NO MESSAGE IS PRINTED - SINCE THIS     Sixpak

WILL NOT EFFECT THE ACCURACY
OF THE INTEGRALS PERFORMED BY THIS    Sixpak

PROGRAM.
Sixpak

Sixpak

SPECTRA AND
ANGULAR DISTRIBUTIONS
Sixpak

=================================
Sixpak

ALL SPECTRA AND
ANGULAR DISTRIBUTIONS ARE CHECKED TO INSURE
Sixpak

THEY ARE
NORMALIZED AND DO NOT INCLUDE ANY NEGATIVE VALUES.
Sixpak

Sixpak

LEGENDRE
COEFFICIENTS
Sixpak

=====================                                              Sixpak

THE
NORMALIZATION, F0, CANNOT BE NEGATIVE.
Sixpak

Sixpak

LEGENDRE
COEFFICIENTS IN NORMAL FORM ARE CHECKED TO INSURE
Sixpak

THEY ARE IN THE
RANGE -1 TO +1 = THE LEGENDRE EXPANSION OF A
Sixpak

DELTA FUNCTION
AT COS=+1 OR -1 - COEFFICIENTS SHOULD NOT
Sixpak

EXCEED WHAT YOU
GET FROM A DELTA FUNCTION.                         Sixpak

Sixpak

ANGULAR
DISTRIBUTIONS ARE CHECKED AT COS = -1, 0 AND +1.
Sixpak

Sixpak

CREATING ENDF/B
OUTPUT
Sixpak

==================================================================
Sixpak

THIS PROGRAM CAN
CREATE EQUIVALENT MF =4, 5, 12, 14, 15 DATA FOR   Sixpak

ALL OF THE DATA
INCLUDED IN ENDF/B-VI AS OF JANUARY 1992, EXCEPT   Sixpak

FOR 1 SECTION OF
LAW=6 DATA (SEE DETAILS BELOW).
Sixpak

Sixpak

THIS PROGRAM HAS NOT
BEEN TESTED ON OTHER DATA LIBRARIES, E.G.,    Sixpak

JEF, JENDL,
ETC.
Sixpak

Sixpak

THE PROGRAM HAS
THE FOLLOWING LIMITATION AS FAR AS CREATING
Sixpak

ENDF/B FORMATTED
OUTPUT.
Sixpak

Sixpak

ISOTROPIC PHOTON
EMISSION
Sixpak

=========================
Sixpak

FOR PHOTON
EMISSION THE DISTRIBUTIONS ARE ASSUMED TO BE ISOTROPIC  Sixpak

AND ONLY THE
MULTIPLICITY IS OUTPUT IN MF=12, ISOTROPIC ANGULAR    Sixpak

DISTRIBUTIONS IN
MF=14 AND THE SPECTRA IN MF=15. ALL ENDF/B-VI     Sixpak

MF=6 DATA AS OF
JANUARY 1992 INCLUDE ONLY ISOTROPIC PHOTON
Sixpak

EMISSION - SO
THAT THIS IS NOT A LIMITATION ON TRANSLATING
Sixpak

ENDF/B-VI
DATA.
Sixpak

Sixpak

EITHER TABULATED
OR LEGENDRE COEFFICIENTS
Sixpak

=========================================
Sixpak

FOR LAW=2 THE
REPRESENTATION, EITHER TABULATED OR LEGENDRE
Sixpak

COEFFICIENTS,
CAN BE SPECIFIED FOR EACH INCIDENT ENERGY.
Sixpak

Sixpak

IN ORDER TO
OBTAIN CORRECT ENDF/B OUTPUT THE REPRESENTATION
Sixpak

MUST BE THE SAME
FOR ALL INCIDENT ENERGIES = MF=4 DATA CAN ONLY    Sixpak

BE TABULATED OR
LEGENDRE OVER THE ENTIRE ENERGY RANGE.
Sixpak

Sixpak

YIELD AND OUTPUT
NORMALIZATION
Sixpak

==============================
Sixpak

THE YIELD
INCLUDED WITH EACH SECTION OF DATA IS NOT USED FOR
Sixpak

OUTPUT FOR
NEUTRONS, BUT IS INCLUDED IN THE OUTPUT FOR PHOTONS.    Sixpak

IN ALL CASES THE
ANGULAR DISTRIBUTIONS AND SPECTRA OUTPUT ARE      Sixpak

NORMALIZED TO
UNITY.
Sixpak

Sixpak

LAW=0                                                              Sixpak

=====
Sixpak

NO OUTPUT -
INCIDENT NEUTRON - EMITTED PHOTON OR NEUTRON
Sixpak

REACTIONS ARE NOT EXPECTED.
Sixpak

Sixpak

LAW=1
Sixpak

=====
Sixpak

FOR EACH
INCIDENT ENERGY DISCRETE AND CONTINUOUS EMISSION SPECTRA  Sixpak

CANNOT BE MIXED
TOGETHER - THEY MUST BE ALL EITHER DISCRETE OR     Sixpak

CONTINUOUS. IF
DISCRETE EMISSION IS GIVEN ONLY 1 SECONDARY
Sixpak

ENERGY (NEP=1)
MAY BE GIVEN = A NORMALIZED DISTRIBUTION FOR A      Sixpak

SINGLE DISCRETE
EMISSION ENERGY. ALL OF THE ENDF/B-VI DATA AS      Sixpak

OF JANUARY 1992
CONFORM TO THESE LIMITATIONS.                      Sixpak

Sixpak

SINCE THE FLAG
NA, TO INDICATE ISOTROPIC DISTRIBUTIONS, IS ONLY    Sixpak

GIVEN FOR EACH
SECONDARY ENERGY (EP) THE PROGRAM CANNOT DECIDE     Sixpak

IN ADVANCE
WHETHER OR NOT THE DISTRIBUTION WILL BE ISOTROPIC
Sixpak

AT ALL INCIDENT
ENERGIES. THEREFORE ISOTROPIC DISTRIBUTIONS
Sixpak

WILL BE OUTPUT
EITHER: LANG = 1 - AS 1 LEGENDRE COEFFICIENT = 0.0  Sixpak

OR LANG = NOT 1
- AS A 2 POINT ANGULAR DISTRIBUTION AT COS = -1.0  Sixpak

AND +1.0 WITH
BOTH VALUES EQUAL TO 0.5 (A NORMALIZED ISOTROPIC     Sixpak

DISTRIBUTION).
Sixpak

Sixpak

DISCRETE PHOTONS
ARE OUTPUT IN MF=15 AS 3 POINT DISTRIBUTIONS      Sixpak

WITH SECONDARY
ENERGY POINTS AT EP-DEP, EP, EP+DEP, WHERE
Sixpak

DEP=0.001*EP.
THE VALUES AT EP-DEP AND EP+DEP ARE 0.0, AND
Sixpak

AT EP THE VALUE
IS 1000.0/EP TO NORMALIZE THE DISTRIBUTION.
Sixpak

Sixpak

LAW=2
Sixpak

=====
Sixpak

NO LIMITATION ON
REPRESENTATIONS.
Sixpak

Sixpak

LAW=3
Sixpak

=====
Sixpak

NO LIMITATION ON
REPRESENTATIONS.                                  Sixpak

Sixpak

LAW=4
Sixpak

=====
Sixpak

NO OUTPUT -
INCIDENT NEUTRON - EMITTED PHOTON OR NEUTRON
Sixpak

REACTIONS ARE NOT EXPECTED.
Sixpak

Sixpak

LAW=5
Sixpak

=====
Sixpak

NO OUTPUT -
INCIDENT NEUTRON - EMITTED PHOTON OR NEUTRON
Sixpak

REACTIONS ARE NOT EXPECTED.
Sixpak

Sixpak

LAW=6
Sixpak

=====
Sixpak

NO OUTPUT -
ENDF/B-VI ONLY INCLUDES 1 SECTION OF THIS TYPE OF DATA Sixpak

FOR (N,D) 2N,P.
Sixpak

Sixpak

LAW=7
Sixpak

=====
Sixpak

FOR EACH
INCIDENT ENERGY THE REPRESENTATION MUST BE EITHER,
Sixpak

Sixpak

1) SQUARE = FOR
EACH INCIDENT COSINE EXACTLY THE SAME SECONDARY    Sixpak

ENERGIES.                                              Sixpak

Sixpak

2) LINEAR = FOR
EACH INCIDENT COSINE THE INTERPOLATION LAW
Sixpak

BETWEEN SECONDARY ENERGIES MUST BE LINEAR.
Sixpak

Sixpak

THESE 2
PRESENTATIONS ARE THE ONLY ONES PRESENTED IN ENDF/B-VI     Sixpak

AS OF JANUARY
1992 - SO THIS PROGRAM CAN TRANSLATED ALL LAW=7      Sixpak

DATA FOR
ENDF/B-VI.
Sixpak

Sixpak

LABORATORY VS.
CENTER-OF-MASS SYSTEM
Sixpak

==================================================================
Sixpak

IN MANY CASES
PEOPLE ASSUME THAT FOR HEAVY (HIGH ATOMIC WEIGHT)    Sixpak

MATERIALS THE
CENTER-OF-MASS AND LAB SYSTEMS ARE ALMOST IDENTICAL, Sixpak

SINCE IN THIS
CASE THE CENTER-OF-MASS ENERGY WILL BE MUCH SMALLER  Sixpak

THAN THE
INCIDENT ENERGY. FOR A PROCESS SUCH AS ELASTIC SCATTERING Sixpak

WHERE FOR HEAVY
MATERIALS THE SECONDARY ENERGY, EP, WILL ALWAYS    Sixpak

BE A LARGE FRACTION OF THE
INCIDENT ENERGY, THIS ASSUMPTION IS     Sixpak

VALID. HOWEVER,
FOR THE TYPICAL REACTIONS INCLUDED IN MF=6 THIS    Sixpak

IS NOT ALWAYS
TRUE - IN MANY OF THESE CASES THE SECONDARY ENERGY   Sixpak

CAN EXTEND ALL
THE WAY DOWN TO ZERO, AND IN PARTICULAR IT CAN      Sixpak

BE SMALL
COMPARED TO THE CENTER-OF-MASS ENERGY - WHICH MAKES THE   Sixpak

TRANSFORMATION
FROM CENTER-OF-MASS TO LAB IMPORTANT. THEREFORE     Sixpak

GENERALLY TO
TREAT MF=6 DATA WE MUST CONSIDER THIS TRANSFORMATION. Sixpak

Sixpak

THE FOLLOWING
DISCUSSING ONLY APPLIES TO SPECTRA THAT MAY BE
Sixpak

OUTPUT IN MF=5 =
ONLY DATA FOR NEUTRONS INCIDENT AND EMITTED -     Sixpak

IN PARTICULAR
THE FOLLOWING DEFINITIONS ARE NOT GENERAL - THEY     Sixpak

ARE ONLY VALID
FOR INCIDENT AND EMITTED NEUTRONS.
Sixpak

Sixpak

DOUBLE
DIFFERENTIAL DATA IN MF=6 MAY BE GIVEN IN EITHER THE LAB    Sixpak

OR C.M. SYSTEM.
SIMILARLY ANGULAR DISTRIBUTIONS IN MF=4 MAY BE     Sixpak

GIVEN IN EITHER
THE LAB OR C.M. SYSTEM. IN CONTRAST ENERGY
Sixpak

SPECTRA IN MF=5
CAN ONLY BE GIVEN IN THE LABORATORY SYSTEM.
Sixpak

Sixpak

THE ANGULAR
DISTRIBUTIONS OUTPUT BY THIS CODE IN MF=4 ARE IN THE   Sixpak

SAME SYSTEM IN
WHICH THEY ARE GIVEN IN MF=6 - EITHER LAB OR
Sixpak

CENTER-OF-MASS
SYSTEM.
Sixpak

Sixpak

THE ENERGY
SPECTRA OUTPUT BY THIS CODE IN MF=5 MUST BE IN THE LAB  Sixpak

SYSTEM - THIS IS
THE ONLY ALLOWED FORM FOR MF=5 DATA.
Sixpak

Sixpak

FOR MF=6 SPECTRA GIVEN
IN THE LAB SYSTEM THIS MERELY REQUIRES      Sixpak

COPYING THE
GIVEN SPECTRA TO MF=5 OUTPUT.
Sixpak

Sixpak

FOR MF=6 SPECTRA
GIVEN IN THE CENTER-OF-MASS SYSTEM ONLY FIRST     Sixpak

ORDER
CORRECTIONS IN THE SPECTRA AND USED AND THEY ARE THEN
Sixpak

OUTPUT IN MF=5
AS IN THE LAB SYSTEM - THE FIRST ORDER CORRECTIONS  Sixpak

ARE DESCRIBED BELOW.
Sixpak

Sixpak

DEFINING,
Sixpak

MM      = CENTER OF MASS
MOTION
Sixpak

CM      = OUTGOING
(EMITTED) PARTICLE IN CENTER OF MASS
Sixpak

LAB     = OUTGOING (EMITTED)
PARTICLE IN LAB
Sixpak

THETA   = CM SCATTERING ANGLE RELATIVE TO
INCIDENT DIRECTION
Sixpak

COS(CM) = COSINE
OF THE CM SCATTERING ANGLE
Sixpak

Sixpak

FOR NEUTRONS
INCIDENT WITH AN ENERGY, E, AND THEREFORE A SPEED,    Sixpak

Sixpak

VN(E) =
2*SQRT(E)/MASS(IN)
Sixpak

Sixpak

THE
CENTER-OF-MASS SPEED IS GIVEN BY,
Sixpak

Sixpak

V(MM) = VN(E)/(1
+ A)
Sixpak

Sixpak

AND THE CENTER
OF MASS ENERGY BY,
Sixpak

Sixpak

E(MM) =
1/2*MASS(IN)*V(MM)**2
Sixpak

= 1/2*MASS(IN)*VN(E)**2/(1 + A)**2
Sixpak

= E/(1 + A)**2
Sixpak

Sixpak

FOR
DISTRIBUTIONS GIVEN IN MF=6 IN THE CM, THE SPEED, V(CM),
Sixpak

SHOULD BE
VECTORIALLY ADDED TO THAT OF OUTGOING PARTICLES TO
Sixpak

DEFINE THE OUTGOING
PARTICLES LAB VELOCITY, AND IN TURN IT'S
Sixpak

ENERGY,
Sixpak

Sixpak

V(LAB)*COS(LAB)
= V(MM) + V(CM)*COS(CM)
Sixpak

V(LAB)*SIN(LAB)
=
V(CM)*SIN(CM)
Sixpak

Sixpak

V(LAB)**2 =
V(MM)**2 + V(CM)**2 + 2*COS(CM)*V(MM)*V(CM)
Sixpak

Sixpak

EP(LAB)   = 0.5*MASS(OUT)*V(LAB)**2
Sixpak

Sixpak

= E(MM) + EP(CM) + 2*COS(CM)*SQRT(E(MM)*EP(CM))
Sixpak

Sixpak

WE CAN ALSO
DEFINE THE REVERSE TRANSFORMATION USING,
Sixpak

Sixpak

V(CM)*COS(CM) =
V(LAB)*COS(LAB) - V(MM)
Sixpak

V(CM)*SIN(CM) =
V(LAB)*SIN(LAB)
Sixpak

Sixpak

V(CM)**2 =
V(MM)**2 + V(LAB)**2 - 2*COS(LAB)*V(MM)*V(LAB)
Sixpak

Sixpak

EP(CM)   = 0.5*MASS(OUT)*V(CM)**2
Sixpak

Sixpak

= E(MM) + EP(LAB) - 2*COS(LAB)*SQRT(E(MM)*EP(LAB))       Sixpak

Sixpak

WE CAN DEFINE
COS(LAB) FROM THE RELATIONSHIP,
Sixpak

Sixpak

V(LAB)*COS(LAB)
= V(MM) + V(CM)*COS(CM)
Sixpak

Sixpak

COS(LAB)
=[V(MM) + V(CM)*COS(CM)]/V(LAB)
Sixpak

Sixpak

[V(MM) + V(CM)*COS(CM)]
Sixpak

COS(LAB)
=---------------------------------------------     Sixpak

SQRT[V(MM)**2+V(CM)**2+2*COS(CM)*V(MM)*V(CM)]     Sixpak

Sixpak

OR COS(CM) FROM
THE RELATIONSHIP,
Sixpak

Sixpak

V(CM)*COS(CM)  =
V(LAB)*COS(LAB) - V(MM)
Sixpak

Sixpak

COS(CM)
=[V(LAB)*COS(LAB) - V(MM)]/V(CM)
Sixpak

Sixpak

[V(LAB)*COS(LAB) - V(MM)]
Sixpak

COS(CM)
=------------------------------------------------  Sixpak

SQRT[V(LAB)**2+V(CM)**2-2*COS(LAB)*V(LAB)*V(MM)]  Sixpak

Sixpak

THE JACOBIAN CAN
BE DEFINED FROM,
Sixpak

Sixpak

V(LAB)*COS(LAB)
= V(MM) + V(CM)*COS(CM)
Sixpak

Sixpak

J =
D[COS(CM)]/D[COS(LAB)] = V(LAB)/V(CM)
Sixpak

= SQRT[EP(LAB)/EP(CM)]
Sixpak

Sixpak

WITH THESE
DEFINITIONS OF EP(LAB) AND COS(LAB) IN TERMS OF E(MM),  Sixpak

EP(CM) AND
COS(CM) IT IS POSSIBLE TO PERFORM A POINT-BY-POINT      Sixpak

TRANSFORMATION
OF DISTRIBUTIONS FROM THE CM TO LAB SYSTEM USING    Sixpak

THESE
DEFINITIONS - OR IF WE WISHED WE COULD PERFORM THE REVERSE   Sixpak

TRANSFORMATION
USING THE ABOVE RELATIONSHIPS AND THE IDENTITY,     Sixpak

Sixpak

F(E,EP(LAB),COS(LAB))*D(COS(LAB))=F(E,EP(CM),COS(CM))*D(COS(CM))   Sixpak

Sixpak

THIS IS NOT WHAT
WILL BE DONE HERE, SINCE WE WILL ONLY BE
Sixpak

INTERESTED IN
THE ZEROTH ORDER MOMENTS OF THESE DISTRIBUTIONS,     Sixpak

BUT WE WILL BE
INTERESTED IN DEFINING THOSE MOMENTS IN THE
Sixpak

LAB SYSTEM IN
TERMS OF MF=6 SPECTRA GIVEN IN THE CM SYSTEM USING,  Sixpak

Sixpak

F(E,EP(LAB),COS(LAB)) = F(E,EP(CM),COS(CM))*J
Sixpak

Sixpak

THE LIMITS OF
EP(LAB) ARE DEFINED BY SETTING COS(CM) = +1 OR -1,   Sixpak

Sixpak

EP(LAB)   = (SQRT(EP(CM)) +
SQRT(E(MM)))**2  FOR COS(CM) = +1      Sixpak

= (SQRT(EP(CM)) - SQRT(E(MM)))**2
FOR COS(CM) = -1      Sixpak

Sixpak

IN THIS FORM WE
CAN SEE THAT AS LONG AS THE SECONDARY ENERGY IN    Sixpak

THE
CENTER-OF-MASS SYSTEM, EP(CM), IS MUCH LARGER THAN THE
Sixpak

ENERGY OF THE
CENTER-OF-MASS, E(MM), THE CENTER-OF-MASS AND LAB    Sixpak

ENERGIES WILL BE
ALMOST EQUAL - SIMILARLY FOR THE COSINE, IN
Sixpak

THIS CASE
COS(LAB) AND COS(CM) WILL BE ALMOST EQUAL - HOWEVER,     Sixpak

FOR THE MF=6
DATA WE CANNOT ASSUME THAT THIS IS TRUE.
Sixpak

Sixpak

TO FIRST ORDER
THE ANGULAR DEPENDENCE CAN BE IGNORED,
Sixpak

Sixpak

EP(LAB)   = E(MM) + EP(CM)
Sixpak

Sixpak

ALL THIS SAYS IS
THAT TO FIRST ORDER THE EFFECT OF TRANSFORMING    Sixpak

FROM THE CM TO
LAB SYSTEM IS TO INCREASE THE ENERGY OF THE
Sixpak

EMITTED PARTICLE
IN THE CENTER-OF-MASS SYSTEM BY THE ENERGY OF     Sixpak

THE
CENTER-OF-MASS TO DEFINE THE LAB ENERGY.
Sixpak

Sixpak

NOT ONLY THE
ENERGY, BUT ALSO THE SPECTRA MUST BE TRANSFORMED.     Sixpak

STARTING FROM
THE DOUBLE DIFFERENTIAL DATA IN THE LAB SYSTEM,      Sixpak

F(E,EP,COS(LAB)), WE CAN DEFINE THE LAB SCALAR SPECTRUM AS,
Sixpak

Sixpak

G0(E,EP) =
INTEGRAL F(E,EP,COS(LAB))*D(COS(LAB))                   Sixpak

Sixpak

THIS IS THE
NORMAL CALCULATION DEFINED ABOVE AND USED FOR DATA     Sixpak

GIVEN IN THE LAB
SYSTEM.
Sixpak

Sixpak

STARTING FROM
DATA IN THE CENTER OF MASS SYSTEM F(E,EP,COS(CM)),   Sixpak

WE CAN USE THE
RELATIONSHIP,
Sixpak

Sixpak

F(E,EP,COS(LAB))*D(COS(LAB)) = F(E,EP,COS(CM))*J*D(COS(LAB))
Sixpak

Sixpak

J         =
SQRT(EP(LAB)/EP(CM)) - THE JACOBIAN
Sixpak

Sixpak

= E(MM)/EP(CM) + 1 + 2*COS(CM)*SQRT(E(MM)/EP(CM))
Sixpak

Sixpak

AS IN THE CASE
OF THE ENERGY, IN THIS FORM WE CAN SEE THAT AS      Sixpak

LONG AS THE
SECONDARY ENERGY IN THE CENTER-OF-MASS SYSTEM,
Sixpak

EP(CM), IS LARGE
COMPARED TO THE CENTER-OF-MASS ENERGY, E(MM),     Sixpak

THE JACOBIAN IS
ESSENTIALLY UNITY AND THE CENTER-OF-MASS AND LAB   Sixpak

SPECTRA WILL BE
VERY SIMILAR - AGAIN, GENERALLY WE CANNOT
Sixpak

ASSUME THAT THIS
IS TRUE FOR THE MF=6 SPECTRA.
Sixpak

Sixpak

THEREFORE WE CAN
ALSO DEFINE THE LAB SCALAR SPECTRUM IN TERMS OF   Sixpak

THE CM SPECTRUM
IN THE FORM,
Sixpak

Sixpak

G0(E,EP) =
INTEGRAL F(E,EP,COS(CM))*J*D(COS(LAB))
Sixpak

Sixpak

CONSISTENT WITH
THE ABOVE ASSUMPTION THAT THE ANGULAR DEPENDENCE   Sixpak

OF EP(LAB) CAN
BE IGNORED THE JACOBIAN WILL NOT BE USED IN
Sixpak

PERFORMING THESE
INTEGRALS - IN WHICH CASE THE INTEGRAL REDUCES    Sixpak

TO EXACTLY THE
SAME FORM AS IF THE DATA WERE IN THE LAB SYSTEM.    Sixpak

Sixpak

IT SHOULD BE
NOTED THAT SINCE IN THIS CASE THE MF=4 ANGULAR
Sixpak

DISTRIBUTIONS
ARE GIVEN IN THE CM SYSTEM AND WHEN USED IN ANY      Sixpak

APPLICATION THEY
WILL BE TRANSFORMED TO THE LAB SYSTEM - WHEN      Sixpak

THIS IS DONE THE
JACOBIAN WILL BE APPLIED.
Sixpak

Sixpak

IN THIS CODE
WHERE WE ARE MOSTLY CONCERNED WITH CONSERVING THE     Sixpak

NUMBER OF
EMITTED PARTICLES AND AVERAGE ENERGIES THE NEUTRON
Sixpak

SPECTRA OUTPUT
IN MF=5 WILL NOT BE COMPLETELY CONVERTED TO THE     Sixpak

LAB SYSTEM -
ONLY FIRST ORDER CORRECTIONS WILL BE INCLUDED BY      Sixpak

INCREASING THE
EMITTED PARTICLE ENERGY BY THE CENTER OF MASS
Sixpak

ENERGY, I.E.,
FOR A CENTER OF MASS SPECTRUM TABULATED AT CENTER    Sixpak

OF MASS ENERGIES
EP(CM) THESE WILL ALL BE UNIFORMLY INCREASED      Sixpak

BY E(MM) TO
ACCOUNT FOR THE CENTER OF MASS MOTION - THE SPECTRA    Sixpak

WILL NOT BE
MODIFIED BY THE JACOBIAN FACTOR SQRT(EP(LAB)/EP(CM))   Sixpak

SINCE THIS WOULD
REQUIRE A DETAILED TRANSFORMATION IN ENERGY AND   Sixpak

COS(THETA) SPACE
- WHICH IS JUDGED NOT TO BE WORTH PERFORMING      Sixpak

WITHIN THE
LIMITS OF WHERE THE OUTPUT FROM THIS CODE IS INTENDED   Sixpak

TO BE USED.
Sixpak

Sixpak

SINCE THE
ANGULAR DISTRIBUTION IS ALWAYS OUTPUT IN THE SAME
Sixpak

SYSTEM AS WHICH
IT IS GIVEN IN MF=6, NO TRANSFORMATION IS
Sixpak

REQUIRED FOR THE
MF=4 OUTPUT.
Sixpak

Sixpak

WHEN USED IN LOW
ENERGY APPLICATIONS (E.G., FISSION REACTORS) THE  Sixpak

HIGH ENERGY
SPECTRA PRESENTED IN MF=6 WILL BE MOSTLY IMPORTANT     Sixpak

SIMPLY IN
CONSERVING PARTICLES, (E.G., AS IN (N,2N)) AND ENERGY    Sixpak

AND THE DETAILS
OF THE CORRELATION AND GROSS ENERGY SPECTRA WILL   Sixpak

NOTE PLAY THAT
IMPORTANT A ROLE. IN THIS CASE THE SPECTRA OUTPUT   Sixpak

BY THIS PROGRAM
IN MF=5 SHOULD BE ADEQUATE.
Sixpak

Sixpak

PLOTTAB
FORMATTED OUTPUT
Sixpak

==================================================================
Sixpak

THIS PROGRAM
CONTAINS ROUTINES TO PRODUCE OUTPUT THAT CAN BE USED  Sixpak

AS INPUT TO THE
PLOTTAB CODE TO OBTAIN GRAPHIC RESULTS.
Sixpak

Sixpak

THESE ROUTINES
ARE DESIGNED ONLY FOR USE BY THE AUTHOR TO CHECK    Sixpak

THIS CODE. USERS
ARE ASKED NOT TO ACTIVATE OR TRY TO USE THESE     Sixpak

ROUTINES. UNLESS
YOU COMPLETELY UNDERSTAND THIS CODE THE RESULTS   Sixpak

CAN BE
UNRELIABLE IF YOU ACTIVATE THESE ROUTINES.
Sixpak

Sixpak

INPUT FILES
Sixpak

==================================================================
Sixpak

UNIT  DESCRIPTION
Sixpak

----  -----------
Sixpak

2  INPUT LINES (BCD - 80
CHARACTERS/RECORD)                     Sixpak

10  ORIGINAL ENDF/B DATA (BCD
- 80 CHARACTERS/RECORD)
Sixpak

Sixpak

OUTPUT
FILES
Sixpak

==================================================================
Sixpak

UNIT  DESCRIPTION
Sixpak

----  -----------
Sixpak

3  OUTPUT REPORT (BCD - 120
CHARACTERS/RECORD)
Sixpak

11  ENDF/B DATA MF=4 (BCD -
80 CHARACTERS/RECORD)
Sixpak

12  ENDF/B DATA MF=5 (BCD -
80 CHARACTERS/RECORD)
Sixpak

14  ENDF/B DATA MF=15 (BCD - 80
CHARACTERS/RECORD)
Sixpak

17  ENDF/B DATA MF=12 (BCD -
80 CHARACTERS/RECORD)
Sixpak

18  ENDF/B DATA MF=14 (BCD -
80 CHARACTERS/RECORD)
Sixpak

15  PLOTTAB INPUT PARAMETERS
(BCD - 80 CHARACTERS/RECORD)
Sixpak

16  PLOTTAB FORMATTED OUTPUT
(BCD - 80 CHARACTERS/RECORD)
Sixpak

Sixpak

SCRATCH
FILES                                                      Sixpak

==================================================================
Sixpak

NONE
Sixpak

Sixpak

OPTIONAL
STANDARD FILE NAMES (SEE SUBROUTINE FILIO1 AND FILIO2)    Sixpak

==================================================================
Sixpak

UNIT  FILE NAME
Sixpak

----  ----------
Sixpak

2   SIXPAK.INP
Sixpak

3   SIXPAK.LST
Sixpak

10   ENDFB.IN
Sixpak

11   ENDFB.MF4
Sixpak

12   ENDFB.MF5
Sixpak

14   ENDFB.M15
Sixpak

17   ENDFB.M12
Sixpak

18   ENDFB.M14
Sixpak

15   PLOTTAB.INP
Sixpak

16   PLOTTAB.CUR
Sixpak

Sixpak

Sixpak

INPUT
PARAMETERS
Sixpak

==================================================================
Sixpak

LINE  COLS.  DESCRIPTION
Sixpak

----  -----  -----------
Sixpak

1   1-60  ENDF/B INPUT DATA FILENAME
Sixpak

(STANDARD OPTION = ENDFB.IN)
Sixpak

2-N   1-6   MINIMUM MAT FOR REQUESTED
RANGE
Sixpak

9-11  MINIMUM MT FOR
REQUESTED RANGE
Sixpak

12-17  MAXIMUM MAT FOR
REQUESTED RANGE
Sixpak

20-22  MAXIMUM MT FOR
REQUESTED RANGE
Sixpak

Sixpak

LEAVE THE
DEFINITION OF THE FILENAME BLANK - THE PROGRAM WILL      Sixpak

THEN USE THE
STANDARD FILENAME (ENDFB.IN).
Sixpak

Sixpak

UP TO 100 MAT/MT
RANGES MAY BE SPECIFIED. THE LIST OF RANGES IS    Sixpak

TERMINATED BY A
BLANK LINE. IF THE FIRST INPUT LINE IS COMPLETELY  Sixpak

BLANK ALL DATA
WILL BE PROCESSED.
Sixpak

Sixpak

EXAMPLE INPUT
NO. 1
Sixpak

-------------------
Sixpak

PROCESS ALL MF=6
DATA ON AN ENDF/B TAPE. USE THE STANDARD INPUT    Sixpak

DATA FILENAME
ENDFB.IN IN THIS CASE THE USER CAN EITHER EXPLICITLY Sixpak

SPECIFY THE
FILENAME AND MAT/MT RANGE BY THE FOLLOWING
2 INPUT    Sixpak

LINES,
Sixpak

Sixpak

ENDFB.IN
Sixpak

1    1  9999  999
Sixpak

(BLANK
LINE, TERMINATES REQUEST LIST)
Sixpak

Sixpak

OR BY INPUTTING
2 BLANK LINE = PROCESS EVERYTHING.
Sixpak

Sixpak

EXAMPLE INPUT
NO. 2
Sixpak

-------------------
Sixpak

PROCESS BE-9,
MAT=425, MT=16. READ THE DATA FROM ENDFB6\BE9.
Sixpak

IN THIS CASE THE
FOLLOWING 3 INPUT LINES ARE REQUIRED,
Sixpak

Sixpak

ENDFBB6\BE9
Sixpak

425   16   425   16
Sixpak

(BLANK LINE, TERMINATES REQUEST LIST)
Sixpak

Sixpak

EXAMPLE INPUT
NO. 3
Sixpak

-------------------
Sixpak

PROCESS ALL
MT=16 (N,2N) DATA. THIS CAN BE DONE BY SPECIFYING THE  Sixpak

MAXIMUM MAT RANGE
= 1 TO 9999, AND MT=16 FOR THE MINIMUM AND
Sixpak

MAXIMUM MT
RANGE. READ THE DATA FROM ENDFB6\K300. IN THIS CASE     Sixpak

CASE THE
FOLLOWING 3 INPUT LINES ARE REQUIRED,
Sixpak

Sixpak

ENDFB6\K300
Sixpak

1   16  9999   16
Sixpak

(BLANK LINE, TERMINATES REQUEST LIST)
Sixpak

Sixpak

=======================================================================
Sixpak

=======================================================================
Virgin

Virgin

PROGRAM
VIRGIN
Virgin

VERSION 76-1 (NOVEMBER
1976)
Virgin

VERSION 84-1
(JUNE 1984)   *DOUBLE PRECISION
ENERGY
Virgin

VERSION 86-1
(JANUARY 1986)*FORTRAN-77/H VERSION
Virgin

VERSION 88-1
(JULY 1988)   *OPTION...INTERNALLY DEFINE ALL
I/O     Virgin

FILE NAMES (SEE, SUBROUTINE FILEIO     Virgin

FOR DETAILS).
Virgin

*IMPROVED BASED ON USER COMMENTS.
Virgin

VERSION 89-1
(JANUARY 1989)*PSYCHOANALYZED BY PROGRAM FREUD TO     Virgin

INSURE PROGRAM WILL NOT DO ANYTHING    Virgin

CRAZY.
Virgin

*UPDATED TO USE NEW PROGRAM CONVERT     Virgin

KEYWORDS.
Virgin

*ADDED LIVERMORE
CIVIC COMPILER
Virgin

CONVENTIONS.
Virgin

VERSION 92-1
(JANUARY 1992)*COMPLETE RE-WRITE
Virgin

*OUTPUT IN PLOTTAB FORMAT
Virgin

*UP TO 2000 THICKNESSES
Virgin

*INCREASED INCORE PAGE SIZE TO 6000     Virgin

CROSS SECTION POINTS
Virgin

*ADDED PHOTON CALCULATIONS
Virgin

*ADDED BLACKBODY SPECTRUM
Virgin

*ADDED MULTIPLE LAYERS
Virgin

*ADDED
SPATIALLY DEPENDENT DENSITY
Virgin

*ADDED FORTRAN SAVE OPTION
Virgin

*COMPLETELY CONSISTENT I/O ROUTINES -   Virgin

TO
MINIMIZE COMPUTER DEPENDENCE.       Virgin

VERSION 92-2
(MAY 1992)    *CORRECTED
TO HANDLE MULTIGROUP CROSS
Virgin

SECTIONS AS INPUT IN ENDF/B FORMAT.    Virgin

VERSION 96-1
(JANUARY 1996) *COMPLETE RE-WRITE
Virgin

*IMPROVED COMPUTER INDEPENDENCE
Virgin

*ALL DOUBLE PRECISION
Virgin

*ON SCREEN OUTPUT
Virgin

*UNIFORM TREATMENT OF ENDF/B I/O
Virgin

*IMPROVED OUTPUT PRECISION
Virgin

*DEFINED SCRATCH FILE NAMES
Virgin

VERSION 99-1
(MARCH 1999)   *CORRECTED
CHARACTER TO FLOATING       Virgin

POINT READ FOR MORE DIGITS
Virgin

*UPDATED TEST FOR ENDF/B FORMAT
Virgin

VERSION BASED ON RECENT FORMAT CHANGE Virgin

*GENERAL IMPROVEMENTS BASED ON
Virgin

USER FEEDBACK
Virgin

VERS. 2000-1
(FEBRUARY 2000)*GENERAL IMPROVEMENTS BASED ON
Virgin

USER FEEDBACK
Virgin

VERS. 2002-1
(MAY 2002)
*OPTIONAL INPUT PARAMETERS
Virgin

VERS. 2004-1
(MARCH 2004)   *ADDED INCLUDE
FOR COMMON
Virgin

*UP TO 2000 THICKNESSES
Virgin

*INCREASED INCORE PAGE SIZE TO 60,000  Virgin

VERS. 2007-1
(JAN.  2007)   *CHECKED AGAINST ALL
ENDF/B-VII.
Virgin

*INCREASED INCORE PAGE SIZE TO
Virgin

240,000 FROM 60,000.
Virgin

Virgin

OWNED,
MAINTAINED AND DISTRIBUTED BY
Virgin

------------------------------------
Virgin

THE NUCLEAR DATA
SECTION
Virgin

INTERNATIONAL
ATOMIC ENERGY AGENCY
Virgin

P.O. BOX 100
Virgin

A-1400, VIENNA, AUSTRIA                                            Virgin

EUROPE
Virgin

Virgin

ORIGINALLY
WRITTEN BY
Virgin

------------------------------------
Virgin

DERMOTT E.
CULLEN
Virgin

UNIVERSITY OF CALIFORNIA
Virgin

LAWRENCE
LIVERMORE
NATIONAL LABORATORY
Virgin

L-159
Virgin

P.O. BOX 808
Virgin

LIVERMORE, CA
94550
Virgin

U.S.A.
Virgin

TELEPHONE  925-423-7359
Virgin

E. MAIL    [email-masked]
Virgin

WEBSITE
HTTP://WWW.LLNL.GOV/CULLEN1
Virgin

Virgin

PURPOSE
Virgin

-------
Virgin

THIS PROGRAM IS
DESIGNED TO CALCULATE UNCOLLIDED (I.E. VIRGIN)     Virgin

FLUX AND REACTIONS
DUE TO TRANSMISSION OF A MONODIRECTIONAL
Virgin

BEAM OF NEUTRONS
THROUGH ANY THICKNESS OF MATERIAL. IN ORDER
Virgin

TO SIMULATE AN
EXPERIMENTAL MEASUREMENT THE RESULTS ARE GIVEN      Virgin

AS INTEGRALS
OVER ENERGY TALLY GROUPS (AS OPPOSED TO POINTWISE     Virgin

IN ENERGY). BY
TAKING THE RATIO OF REACTIONS TO FLUX IN EACH
Virgin

GROUP AN
EQUIVALENT SPATIALLY DEPENDENT GROUP AVERAGED CROSS
Virgin

SECTION IS
CALCULATED BY THE PROGRAM.
Virgin

Virgin

EVALUATED
DATA
Virgin

--------------
Virgin

THE EVALUATED
DATA MUST BE IN THE ENDF/B FORMAT. HOWEVER IT
Virgin

MUST BE
LINEAR-LINEAR INTERPOLABLE IN ENERGY-CROSS SECTION
Virgin

BETWEEN
TABULATED POINTS. SINCE ONLY CROSS SECTIONS (FILE 3 OR 23) Virgin

ARE USED, THIS
PROGRAM WILL WORK ON ANY VERSION OF ENDF/B
Virgin

(I.E. ENDF/B-I,
II, III, IV, V OR VI).
Virgin

Virgin

RELATED COMPUTER
CODES
Virgin

----------------------
Virgin

IN ORDER TO
CONVERT ENDF/B DATA TO THE FORM REQUIRED BY THIS CODE  Virgin

THE FOLLOWING
COMPUTER CODES MAY BE USED,
Virgin

Virgin

LINEAR  - CONVERT FROM GENERAL ENDF/B
INTERPOLATION TO LINEAR-
Virgin

LINEAR
INTERPOLATION.
Virgin

RECENT  - ADD THE RESONANCE CONTRIBUTION TO
TABULATED BACKGROUND   Virgin

CROSS SECTIONS TO OBTAIN LINEAR-LINEAR INTERPOLABLE      Virgin

RESULTS.
Virgin

SIGMA1  - DOPPLER BROADEN CROSS SECTION TO
OBTAIN LINEAR-LINEAR
Virgin

INTERPOLABLE RESULTS.
Virgin

MIXER   - MIX INDIVIDUAL MATERIALS
TOGETHER TO DEFINE COMPOSITE
Virgin

MIXTURES, E.G., COMBINE MATERIALS TO DEFINE STAINLESS    Virgin

STELL.
Virgin

Virgin

IN ORDER TO PLOT
THE OUTPUT RESULTS OF THIS CODE USE PROGRAM
Virgin

PLOTTAB.
Virgin

Virgin

COPIES OF ANY OR
ALL OF THESE CODES MAY BE OBTAINED FROM D.E.      Virgin

CULLEN AT THE
ABOVE ADDRESS.
Virgin

Virgin

OUTPUT
FORMAT
Virgin

-------------
Virgin

FOR ALL VERSIONS
OF THIS PROGRAM PRIOR TO VERSION 92-1 OUTPUT WAS  Virgin

IN TABULAR
FORM.
Virgin

Virgin

FOR VERSION 92-1
AND LATER VERSIONS OF THIS CODE ALL OUTPUT IS IN  Virgin

THE PROGRAM
PLOTTAB FORMAT TO ALLOW RESULTS TO BE EASILY PLOTTED.  Virgin

FOR A COPY OF
PROGRAM PLOTTAB CONTACT D.E. CULLEN AT THE ABOVE     Virgin

ADDRESS.
Virgin

Virgin

TALLY
GROUPS
Virgin

------------
Virgin

THE TALLY GROUP
STRUCTURE MAY BE ANY SET OF MONONTONICALLY
Virgin

INCREASING
ENERGY BOUNDARIES. THERE MAY BE UP TO 2000 TALLY
Virgin

GROUPS. BY USING
THE INPUT PARAMETERS THE USER MAY SPECIFY ANY     Virgin

ARBITRARY TALLY
GROUP STRUCTURE OR SELECT ONE OF THE FOLLOWING     Virgin

BUILT-IN GROUP
STRUCTURES.
Virgin

Virgin

(1) TART 175
GROUPS (INPUT  0)
Virgin

(2) ORNL  50 GROUPS (INPUT -1)
Virgin

(3) ORNL 126
GROUPS (INPUT -2)
Virgin

(4) ORNL 171
GROUPS (INPUT -3)
Virgin

(5) SAND-II 620
GROUPS...UP TO 18 MEV (INPUT -4)
Virgin

(6) SAND-II 640
GROUPS...UP TO 20 MEV (INPUT -5)
Virgin

(7) WIMS 69
GROUPS (INPUT -6)
Virgin

(8) GAM-I 68
GROUPS (INPUT -7)
Virgin

(9) GAM-II 99
GROUPS (INPUT -8)
Virgin

(10) MUFT 54 GROUPS
(INPUT -9)
Virgin

(11) ABBN 28 GROUPS
(INPUT -10)
Virgin

Virgin

INCIDENT
SPECTRUM
Virgin

-----------------
Virgin

THE INCIDENT
SPECTRUM MAY BE ANY TABULATED FUNCTION THAT IS
Virgin

GIVEN BY A SET
OF POINTS THAT IS MONOTONICALLY INCREASING IN
Virgin

ENERGY AND
LINEAR-LINEAR INTERPOLABLE IN ENERGY-SPECTRUM
Virgin

BETWEEN
TABULATED POINTS. THERE IS NO LIMIT TO THE NUMBER OF
Virgin

POINTS USED TO
DESCRIBE THE SPECTRUM. THERE ARE FIVE BUILT-IN      Virgin

OPTIONS FOR THE
SPECTRUM.
Virgin

Virgin

(1)
CONSTANT...ENERGY INDEPENDENT (INPUT 0)
Virgin

(2) 1/E (INPUT
1)
Virgin

(3) BLACKBODY -
PHOTON SPECTRUM
Virgin

(4) BLACKBODY -
ENERGY SPECTRUM (E TIMES THE PHOTON SPECTRUM)      Virgin

(5) TRANSMITTED
SPECTRUM FROM PREVIOUS CASE
Virgin

Virgin

NORMALIZATION OF
SPECTRUM
Virgin

-------------------------                                          Virgin

ANY INCIDENT
SPECTRUM, EITHER READ AS INPUT OR ONE OF THE
Virgin

BUILT-IN
SPECTRA, WILL BE NORMALIZED TO UNITY WHEN INTEGRATED      Virgin

OVER THEIR
ENTIRE ENERGY RANGE.
Virgin

Virgin

TRANSMITTED
SPECTRA WILL NOT BE RE-NORMALIZED, SINCE IT ALREADY    Virgin

INCLUDES THE
NORMALIZATION OF THE INCIDENT SPECTRUM.               Virgin

Virgin

NOTE, INCIDENT
SPECTRA IS NORMALIZED TO UNITY OVER THEIR ENTIRE    Virgin

ENERGY RANGE -
NOT OVER THE ENERGY RANGE OF THE GROUPS. IF THE     Virgin

ENERGY RANGE OF
THE GROUPS IS LESS THAN THAT OF THE SPECTRUM
Virgin

ONLY THAT
PORTION OF THE SPECTRUM WILL BE USED AND THIS WILL
Virgin

NOT BE
RE-NORMALIZED TO UNITY.
Virgin

Virgin

COMPOSITION OF A
LAYER
Virgin

----------------------
Virgin

YOU MAY RUN
PROBLEMS INVOLVING
Virgin

1) A LAYER OF
UNIFORM DENSITY - DENSITY FOR ATTENUATION IS THAT    Virgin

OF THE TOTAL. DENSITY FOR REACTIONS IS THAT OF THE REACTION.    Virgin

2) A LAYER OF
UNIFORM DENSITY - DENSITY IS THE SUM OF THE TOTAL    Virgin

AND REACTION DENSITIES - THE SUM OF THE CROSS SECTIONS IS       Virgin

USED FOR ATTENUATION AND REACTIONS.
Virgin

3) A LAYER OF
VARYING DENSITY BASED ON A UNIFORM TOTAL DENSITY     Virgin

PLUS A VARIATION BETWEEN 0 AND A MAXIMUM BASED ON THE
Virgin

REACTION DENSITY - 0 AT 0 THICKNESS AND MAXIMUM AT MAXIMUM      Virgin

THICKNESS. IN THIS CASE THE AVERAGE REACTION DENSITY IS EQUAL   Virgin

TO THE INPUT REACTION DENSITY. THE VARIATION IN REACTION
Virgin

DENSITY CAN BE LINEAR, SQUARE OR CUBIC.
Virgin

4) A LAYER OF
VARYING DENSITY BASED ON A TOTAL DENSITY WHICH
Virgin

VARYING FROM MAXIMUM AT 0 THICKNESS TO 0 AT MAXIMUM THICKNESS   Virgin

PLUS A REACTION DENSITY WHICH VARIES FROM 0 AT 0 THICKNESS      Virgin

TO MAXIMUM AT MAXIMUM THICKNESS. IN THIS CASE THE AVERAGE
Virgin

DENSITY OF THE TOTAL AND REACTION WILL BOTH BE EQUAL TO THE     Virgin

INPUT TOTAL AND REACTION DENSITIES. THE VARIATION IN TOTAL      Virgin

AND REACTION DENSITY CAN BE LINEAR, SQUARE OR CUBIC.            Virgin

Virgin

IN THE FIRST
CASE THE TWO REQUESTED CROSS SECTIONS ARE CONSIDERED  Virgin

TO BE
INDEPENDENT - THE TOTAL CROSS SECTION IS USED TO CALCULATE   Virgin

ATTENUATION AND
THE REACTION CROSS SECTION IS USED TO CALCULATE    Virgin

REACTIONS, E.G.,
TRANSMISSION THROUGH NATURAL URANIUM (THE TOTAL   Virgin

CROSS SECTION
SHOULD BE THAT OF NATURAL URANIUM) AND REACTIONS     Virgin

IN A U-235 DETECTOR (THE REACTION CROSS
SECTION SHOULD BE THAT OF
Virgin

U-235).
Virgin

Virgin

IN THE OTHER
THREE CASES THE TWO REQUESTED CROSS SECTIONS ARE      Virgin

TREATED AS TWO
CONSTITUENTS OF A MIXTURE OF TWO MATERIALS AND      Virgin

THE TWO CROSS
SECTIONS ARE USED BOTH TO DEFINE A TOTAL CROSS
Virgin

SECTION FOR
ATTENUATION AND A REACTION CROSS SECTION TO DEFINE     Virgin

REACTIONS. IN
THESE CASES THE MIXTURE WILL VARY CONTINUOUSLY,      Virgin

E.G., IN CASE 4)
HALF WAY THROUGH THE LAYER THE COMPOSITION WILL   Virgin

BE 1/2 THE
MATERIAL DEFINED BY THE TOTAL AND 1/2 THE MATERIAL      Virgin

BASED ON THE
REACTION. IN THESE CASES RATHER THAN THINKING OF      Virgin

THE TWO CROSS
SECTIONS AS A TOTAL AND REACTION CROSS SECTION,      Virgin

IT IS BETTER TO
THINK OF THEM AS THE TOTAL CROSS SECTIONS FOR      Virgin

MATERIALS A AND
B AND THE CALCULATED REACTIONS WILL BE BASED
Virgin

ON THESE TWO
TOTAL CROSS SECTIONS.
Virgin

Virgin

MULTIPLE
LAYERS
Virgin

---------------
Virgin

THIS CODE MAY BE
USED TO RUN EITHER A NUMBER OF INDEPENDENT
Virgin

PROBLEMS, EACH
INVOLVING TRANSMISSION THROUGH A SINGLE LAYER OF    Virgin

MATERIAL, OR
TRANSMISSION THROUGH A NUMBER OF LAYERS ONE AFTER     Virgin

THE OTHER.
Virgin

Virgin

IN THE CASE OF
MULTIPLE LAYERS, ONE LAYER AFTER ANOTHER, THE
Virgin

TRANSMITTED
ENERGY DEPENDENT SPECTRUM IS USED AS THE INCIDENT      Virgin

SPECTRUM FOR THE NEXT
LAYER. THERE IS NO LIMIT TO THE NUMBER
Virgin

OF LAYERS WHICH
MAY BE USED - EACH LAYER IS TREATED AS A
Virgin

COMPLETELY
INDEPENDENT PROBLEM WITH A DEFINED INCIDENT SOURCE,     Virgin

AND AS SUCH THE
CYCLE OF TRANSMISSION THROUGH EACH LAYER AND
Virgin

USING THE
TRANSMITTED SPECTRUM AS THE INCIDENT SPECTRUM FOR THE    Virgin

NEXT LAYER MAY
BE REPEATED ANY NUMBER OF TIMES.
Virgin

Virgin

REMEMBER - THE
INCIDENT SPECTRUM IS ASSUMED TO BE LINEARLY
Virgin

INTERPOLABLE IN
ENERGY AND SPECTRUM BETWEEN THE ENERGIES AT
Virgin

WHICH IT IS
TABULATED. THE TRANSMITTED SPECTRUM WILL BE TABULATED  Virgin

AT THE UNION OF
ALL ENERGIES OF THE INCIDENT SPECTRUM AND CROSS    Virgin

SECTIONS (TOTAL
AND REACTION). IN ORDER TO INSURE THE ACCURACY     Virgin

OF THE RESULT
WHEN PERFORMING MULTIPLE LAYER CALCULATION BE SURE   Virgin

TO SPECIFY THE
INCIDENT SPECTRUM ON THE FIRST LAYER TO SUFFICIENT  Virgin

DETAIL (ENOUGH
ENERGY POINTS CLOSELY SPACED TOGETHER) IN ORDER TO  Virgin

ALLOW THE
TRANSMITTED SPECTRUM TO BE ACCURATELY REPRESENTED BY     Virgin

LINEAR
INTERPOLATION BETWEEN SUCCESSIVE ENERGY POINTS - THERE IS   Virgin

NO LIMIT TO THE
NUMBER OF POINTS ALLOWED IN THE INCIDENT SPECTRUM, Virgin

SO IF YOU ARE IN
DOUBT, SIMPLY USE MORE ENERGY POINTS TO SPECIFY   Virgin

THE INCIDENT
SPECTRUM.
Virgin

Virgin

RESULT OUTPUT
UNITS
Virgin

-------------------
Virgin

FLUX      = EXACTLY AS
CALCULATED
Virgin

REACTIONS = 1/CM
OR 1/GRAM
Virgin

AVERAGE   = 1/CM - MACROSCOPIC UNITS
Virgin

CROSS
Virgin

SECTION
Virgin

Virgin

THICKNESS AND
DENSITY
Virgin

---------------------
Virgin

THE UNCOLLIDED
CALCULATION ONLY DEPENDS ON THE PRODUCT OF
Virgin

THICKNESS AND
DENSITY (I.E. GRAMS PER CM SQUARED). THIS FACT
Virgin

MAY BE USED TO
SIMPLIFY INPUT BY ALLOWING THE THICKNESS AND
Virgin

DENSITY TO BE
GIVEN EITHER AS CM AND GRAMS/CC RESPECTIVELY
Virgin

OR ELSE TO GIVE
THICKNESS IN GRAMS/(CM*CM) AND INPUT A
Virgin

DENSITY OF 1.0 -
OR IN ANY OTHER CONVENIENT UNITS AS LONG AS
Virgin

THE PRODUCT OF
THICKNESS AND DENSITY IS IN THE CORRECT GRAMS
Virgin

PER CENTIMETER
SQUARED.
Virgin

Virgin

GRAMS/(CM*CM)
ARE RELATED TO ATOMS/BARN THROUGH THE RELATIONSHIP   Virgin

Virgin

GRAMS/(CM*CM)=(ATOMS/BARN)*(GRAMS/MOLE)*(MOLE/ATOM)
Virgin

Virgin

OR...
Virgin

Virgin

GRAMS/(CM*CM)=(ATOMS/BARN)*(ATOMIC WEIGHT)/0.602
Virgin

Virgin

CROSS SECTIONS
AT A SPACE POINT AND OPTICAL THICKNESS
Virgin

-----------------------------------------------------
Virgin

THIS PROGRAM
ALLOWS LAYERS OF EITHER UNIFORM DENSITY OR
Virgin

CONTINUOUSLY
VARYING DENSITY. THE DENSITY CAN BE ONE OF THE
Virgin

FOLLOWING
FORMS,
Virgin

1) C
= UNIFORM DENSITY
Virgin

2)
C*2*(X/T)
= LINEAR VARIATION FROM 0 TO C
Virgin

3)
C*(2-2*(X/T))       = LINEAR
VARIATION FROM C TO 0
Virgin

4) C*3*(X/T)**2        =
SQUARE VARIATION FROM 0 TO C
Virgin

5)
C*(3-3*(X/T)**2)/2  = SQUARE
VARIATION FROM C TO 0
Virgin

6)
C*4*(X/T)**3        =
CUBIC VARIATION FROM 0 TO C
Virgin

7)
C*(4-4*(X/T)**3)/3  = CUBIC
VARIATION FROM C TO 0
Virgin

Virgin

IN ORDER TO
CALCULATE REACTIONS AT A POINT THE MICROSCOPIC
Virgin

REACTION CROSS
SECTION NEED MERELY BE SCALED BY THESE DENSITIES.   Virgin

Virgin

IN ORDER TO
CALCULATE TRANSMISSION WE MUST DEFINE THE OPTICAL      Virgin

PATH LENGTH
WHICH MAY BE DEFINED BY INTEGRATING EACH OF THE
Virgin

ABOVE DENSITY
FORMS TO FIND,
Virgin

1) C*X
Virgin

2)
C*X*(X/T)
Virgin

3)
C*X*(2-(X/T))
Virgin

4)
C*X*(X/T)**2
Virgin

5)
C*X*(3-(X/T)**2)/2
Virgin

6)
C*X*(X/T)**3
Virgin

7)
C*X*(4-(X/T)**3))/3
Virgin

Virgin

IN ORDER TO
CALCULATE TRANSMISSION TO A POINT THE MICROSCOPIC      Virgin

TOTAL CROSS
SECTION NEED MERELY BE SCALED BY THESE DENSITIES
Virgin

TO DEFINE THE
OPTICAL PATH LENGTH.
Virgin

Virgin

THE VARIATION OF
THE DENSITY THROUGH THE LAYER MAY BE DEFINED      Virgin

BY SETTING X = 0
OR X = T TO FIND,
Virgin

X = 0      X = T
Virgin

-----
-----
Virgin

1) C
C
Virgin

2) 0
2*C                                                  Virgin

3) 2*C
0
Virgin

4) 0
3*C
Virgin

5) 3*C/2      0
Virgin

6) 0
4*C
Virgin

7) 4*C/3      0
Virgin

Virgin

THE OPTICAL PATH
THROUGH A LAYER OF THICKNESS T MAY BE DEFINED     Virgin

FROM THE ABOVE
EXPRESSIONS BY SETTING X=T TO FIND THAT IN ALL      Virgin

CASES THE ANSWER
WILL BY C*T. THE CONSTANTS IN THE ABOVE
Virgin

EXPRESSIONS HAVE
BEEN INTRODUCED IN ORDER TO FORCE THIS RESULT.    Virgin

WITH THESE
FACTORS THE OPTICAL PATH LENGTH THROUGH THE LAYER
Virgin

WILL EXACTLY
CORRESPOND TO AN AVERAGE DENSITY CORRESPONDING TO     Virgin

THAT INPUT FOR
THE TOTAL AND/OR REACTION, I.E., C CORRESPONDS      Virgin

TO THE INPUT
DENSITY.
Virgin

Virgin

NOTE - FOR THE
SAME OPTICAL PATH LENGTHS THROUGH THE LAYER THE     Virgin

TRANSMISSION
WILL BE EXACTLY THE SAME. HOWEVER, VARYING THE
Virgin

DENSITY WILL
ALLOW YOU TO MODIFY THE REACTION RATES AT SPECIFIC    Virgin

DEPTHS INTO THE
LAYER.
Virgin

Virgin

COMPUTATION OF
INTEGRALS
Virgin

------------------------
Virgin

STARTING FROM
TOTAL CROSS SECTIONS, REACTION CROSS SECTIONS AND    Virgin

A SOURCE
SPECTRUM ALL OF WHICH ARE GIVEN IN TABULAR FORM WITH      Virgin

LINEAR
INTERPOLATION BETWEEN TABULATED POINTS ALL REQUIRED
Virgin

INTEGRALS CAN BE
DEFINED BY ANALYTICAL EXPRESSIONS INVOLVING
Virgin

NOTHING MORE
COMPLICATED THAN EXPONENTIALS. THE INTEGRALS THAT     Virgin

MUST BE
EVALUATED ARE OF THE FORM...
Virgin

Virgin

FLUX
Virgin

----
Virgin

(INTEGRAL EK TO
EK+1) (S(E)* EXP(-XCT(E)*Z)*DE)
Virgin

Virgin

REACTIONS
Virgin

---------
Virgin

(INTEGRAL EK TO
EK+1) (S(E)*XCR(E)*EXP(-XCT(E)*Z)*DE)
Virgin

Virgin

WHERE..
Virgin

EK TO EK+1 =
LONGEST ENERGY INTERVAL OVER WHICH S(E), XCT(E) AND   Virgin

XCR(E) ARE ALL LINEARLY INTERPOLABLE.
Virgin

S(E)       = ENERGY
DEPENDENT WEIGHTING SPECTRUM
Virgin

XCR(E)     = REACTION CROSS
SECTION
Virgin

XCT(E)     = OPTICAL PATH LENGTH
(BASED ON TOTAL CROSS SECTION)
Virgin

Z
= MATERIAL THICKNESS
Virgin

Virgin

S(E), XCR(E) AND
XCT(E) ARE ALL ASSUMED TO BE GIVEN IN TABULAR     Virgin

FORM WITH LINEAR
INTERPOLATION USED BETWEEN TABULATED POINTS.      Virgin

IN OTHER WORDS
BETWEEN TABULATED POINTS EACH OF THESE THREE IS     Virgin

DEFINED BY A
FUNCTION OF THE FORM...
Virgin

Virgin

F(E)=((E -
EK)*FK+1 + (EK+1 - E)*FK)/(EK+1 - EK)
Virgin

Virgin

EACH OF THESE
THREE CAN BE CONVERTED TO NORMAL FORM BY THE
Virgin

CHANGE OF
VARIABLES....
Virgin

Virgin

X=(E - 0.5*(EK+1
+ EK))/(EK+1 - EK)                                Virgin

Virgin

IN WHICH CASE X
WILL VARY FROM -1 (AT EK) TO +1 (AT EK+1) AND      Virgin

EACH FUNCTION
REDUCES TO THE NORMAL FORM...
Virgin

Virgin

F(X)=0.5*(FK*(1
- X) + FK+1*(1 + X))
Virgin

=0.5*(FK+1 + FK) + 0.5*(FK+1 - FK)*X
Virgin

Virgin

BY DEFINING THE
AVERAGE VALUE AND 1/2 THE CHANGE ACROSS THE
Virgin

INTERVAL.
Virgin

Virgin

AVF=0.5*(FK+1 +
FK)
Virgin

DF= 0.5*(FK+1 -
FK)
Virgin

DE= 0.5*(EK+1 -
EK)
Virgin

Virgin

EACH OF THE
THREE FUNCTIONS REDUCES TO THE SIMPLE FORM...
Virgin

Virgin

F(X)=AVF+DF*X
Virgin

Virgin

AND THE TWO REQUIRED
INTEGRALS REDUCE TO...
Virgin

Virgin

FLUX
Virgin

----
Virgin

DE*EXP(-AVXCT*Z)
* (INTEGRAL -1 TO +1)
Virgin

((AVS+DS*X)*EXP(-DXCT*Z*X)*DX)
Virgin

Virgin

REACTION
Virgin

--------
Virgin

DE*EXP(-AVXCT*Z)
* (INTEGRAL -1 TO +1)                             Virgin

((AVS*AVXCR+(AVS*DXCR+AVXCR*DS)*X+DS*DXCR*X*X)*EXP(-DXCT*Z*X)*DX)  Virgin

Virgin

WHERE
Virgin

Virgin

AVXCT   = AVERAGE VALUE OF THE TOTAL CROSS
SECTION
Virgin

AVXCR   = AVERAGE VALUE OF THE REACTION
CROSS SECTION
Virgin

AVS     = AVERAGE VALUE OF THE
SOURCE
Virgin

DXCT    = 1/2 THE CHANGE IN THE
TOTAL CROSS SECTION
Virgin

DXCR    = 1/2 THE CHANGE IN THE
REACTION CROSS SECTION
Virgin

DS      = 1/2 THE CHANGE
IN THE SOURCE
Virgin

DE      = 1/2 THE CHANGE
IN THE ENERGY
Virgin

Virgin

NOTE THAT IN
THIS FORM THE ENERGY ONLY APPEARS IN FRONT OF THE     Virgin

INTEGRALS AND
THE INTEGRALS ARE EXPRESSED ONLY IN TERMS OF THE     Virgin

TABULATED VALUES
OF S(E), XCT(E) AND XCR(E). IN PARTICULAR NO      Virgin

DERIVATIVES ARE
USED, SO THAT THERE ARE NO NUMERICAL INSTABILITY   Virgin

PROBLEMS IN THE
VACINITY OF DISCONTINUITIES IN S(E), XCT(E) OR     Virgin

XCR(E). INDEED,
SINCE (EK+1 - EK) APPEARS IN FRONT OF THE INTEGRAL Virgin

POINTS OF
DISCONTINUITY AUTOMATICALLY MAKE ZERO CONTRIBUTION TO    Virgin

THE
INTEGRALS.
Virgin

Virgin

THE REQUIRED
INTEGRALS CAN BE EXPRESSED IN TERMS OF THE THREE      Virgin

INTEGRALS IN
NORMAL FORM....
Virgin

Virgin

F(A,N) =
(INTEGRAL -1 TO 1) (X**N*EXP(-A*X)*DX), N=0,1 AND 2.      Virgin

Virgin

THESE THREE
INTEGRALS CAN BE EVALUATED TO FIND...
Virgin

Virgin

N=0
Virgin

---
Virgin

F(A,0) =
(EXP(A)-EXP(-A))/A
Virgin

Virgin

N=1
Virgin

---
Virgin

F(A,1) =
((1-A)*EXP(A)-(1+A)*EXP(-A))/(A*A)
Virgin

Virgin

N=2
Virgin

---
Virgin

F(A,2) =
((2-2*A+A*A)*EXP(A)-(2+2*A+A*A)*EXP(-A))/(A*A*A)
Virgin

Virgin

HOWEVER THESE
EXPRESSIONS ARE NUMERICALLY UNSTABLE FOR SMALL
Virgin

VALUES OF A.
THEREFORE FOR SMALL A THE EXPONENTIAL IN THE
Virgin

INTEGRALS ARE
EXPANDED IN A POWER SERIES...
Virgin

Virgin

EXP(-AX)=1.0-(AX)+(AX)**2/2-(AX)**3/6+(AX)**4/24-........
Virgin

=(SUM K=0 TO INFINITY) (-AX)**K/(K FACTORIAL)
Virgin

Virgin

AND THE INTEGRAL
REDUCES TO THE FORM....
Virgin

Virgin

(SUM K=0 TO
INFINITY) ((-A)**K/(K FACTORIAL)) *
Virgin

(INTEGRAL -1 TO
1) (X**(N+K))*DX
Virgin

Virgin

WHICH CAN BE
ANALYTICALLY EVAULATED TO FIND....
Virgin

(K(N) = K
FACTORIAL)
Virgin

Virgin

N=0
Virgin

---
Virgin

F(A,0) =
2*(1+(A**2)/K(3)+(A**4)/K(5)+(A**6)/K(7)+....
Virgin

Virgin

N=1
Virgin

---
Virgin

F(A,1) =
-2*A*(2/K(3)+4*(A**2)/K(5)+6*(A**4)/K(7)+8*(A**6)/K(9)+.. Virgin

Virgin

N=2
Virgin

---
Virgin

F(A,2) =
2*(2/K(3)+3*4*(A**2)/K(5)+5*6*(A**4)/K(7)+
Virgin

7*8*(A**6)/K(9)+....
Virgin

Virgin

THESE EXPANSIONS
ARE USED WHEN THE ABSOLUTE VALUE OF A IS LESS     Virgin

THAN 0.1. BY
TRUNCATING THE ABOVE SERIES BEFORE A**8 THE ERROR     Virgin

RELATIVE TO THE
LEADING TERM OF THE SERIES WILL BE 10**(-10),      Virgin

YIELDING 10
DIGIT ACCURACY.                                        Virgin

Virgin

AFTER EVALUATING
THE ABOVE FUNCTIONS, EITHER DIRECTLY OR BY USING  Virgin

THE EXPANSION
THE TWO REQUIRED INTEGRALS CAN BE WRITTEN AS...      Virgin

Virgin

FLUX
Virgin

----
Virgin

DE*EXP(-AVXCT*Z)*(AVS*F(A,0) + DS*F(A,1))
Virgin

Virgin

REACTIONS
Virgin

---------
Virgin

DE*EXP(-AVXCT*Z)*
Virgin

(AVS*AVXCR*F(A,0) + (AVS*DXCR+AVXCR*DS)*F(A,1) + DS*DXCR*F(A,2))   Virgin

Virgin

INPUT FILES
Virgin

-----------
Virgin

FILENAME  UNIT  DESCRIPTION
Virgin

--------  ----  -----------
Virgin

INPUT       2   INPUT LINES
Virgin

ENDFIN     10   EVALUATED DATA IN ENDF/B
FORMAT
Virgin

Virgin

OUTPUT
FILES
Virgin

------------                                                       Virgin

FILENAME  UNIT  DESCRIPTION
Virgin

--------  ----  -----------
Virgin

OUTPUT      3   OUTPUT LISTING
Virgin

Virgin

SCRATCH
FILES
Virgin

-------------
Virgin

FILENAME  UNIT  DESCRIPTION
Virgin

--------  ----  -----------
Virgin

SCR1       12   REACTION, FLUX AND CROSS SECTION
RESULTS (BCD)
Virgin

(SORTED AT END OF RUN AND OUTPUT SEPARATELY)
Virgin

SCR2       13   TALLY GROUP ENERGY BOUNDARIES
(BINARY)
Virgin

SCR3       14   SOURCE SPECTRUM (BINARY)
Virgin

SCR4       15   TOTAL CROSS SECTION (BINARY)
Virgin

SCR5       16   REACTION CROSS SECTION (BINARY)
Virgin

Virgin

OPTIONAL
STANDARD FILE NAMES (SEE SUBROUTINE FILIO1 AND FILEIO2)   Virgin

----------------------------------------------------------------   Virgin

UNIT  FILE NAME   FORMAT
Virgin

----  ----------  ------
Virgin

2   VIRGIN.INP   BCD
Virgin

3   VIRGIN.LST   BCD
Virgin

10   ENDFB.IN     BCD
Virgin

11-15  (SCRATCH)   BINARY
Virgin

16   PLOTTAB.CUR PLOTTAB OUTPUT FORMAT
DATA
Virgin

Virgin

INPUT LINES
Virgin

-----------
Virgin

ANY NUMBER OF
CASES MAY BE RUN ONE AFTER THE OTHER. AFTER THE      Virgin

FIRST CASE HAS
BEEN RUN THE FOLLOWING CASES MAY USE THE SAME
Virgin

THICKNESSES,
GROUP STRUCTURE AND SPECTRUM AS THE PRECEDING CASE.   Virgin

IN ADDITION THE
TRANSMITTED SPECTRUM FROM ONE CASE MAY BE USED     Virgin

AS THE INCIDENT
SPECTRUM IN THE NEXT CASE, TO ALLOW MULTIPLE
Virgin

LAYERS OF
DIFFERENT MATERIALS.
Virgin

Virgin

LINE  COLS.  FORMAT  DESCRIPTION
Virgin

----  -----  ------  ----------
Virgin

1   1-60   ENDF/B INPUT DATA FILENAME
Virgin

(STANDARD OPTION = ENDFB.IN)
Virgin

Virgin

LEAVE THE
DEFINITION OF THE FILENAMES BLANK - THE PROGRAM WILL     Virgin

THEN USE
STANDARD FILENAMES.
Virgin

Virgin

2-3   1-72   18A4   TWO LINE TITLE DESCRIBING
PROBLEM
Virgin

4   1- 6    I6    ZA (1000*Z+A) OF TARGET FOR
TOTAL
Virgin

7-11    I5    MT OF TOTAL
Virgin

12-22   E11.4  DENSITY FOR TOTAL
Virgin

23-28    I6    ZA (1000*Z+A) OF TARGET FOR
REACTION
Virgin

29-33    I5    MT OF REACTION
Virgin

= 0 - NO REACTION CALCULATION (ONLY FLUX).    Virgin

=
GREATER THAN 0 - CALCULATE REACTIONS.       Virgin

34-44   E11.4  DENSITY FOR REACTION
Virgin

45-50    I6    NUMBER OF TARGET THICKNESSES
Virgin

= GREATER THAN 0 = READ FROM INPUT
Virgin

(1 TO 2000 ALLOWED)
Virgin

=  0 = SAME AS LAST CASE
Virgin

51-55    I5    NUMBER OF TALLY GROUPS
Virgin

(REMEMBER NUMBER OF GROUP BOUNDARIES
Virgin

IS ONE MORE THAN THE NUMBER OF GROUPS)
Virgin

UP TO 2000 GROUPS ARE ALLOWED
Virgin

BUILT-IN GROUP STRUCTURES.
Virgin

= GREATER THAN 0 = READ FROM INPUT
Virgin

=  0 SAME AS LAST CASE                        Virgin

= -1 TART 175 GROUPS
Virgin

= -2 ORNL  50 GROUPS
Virgin

= -3 ORNL 126 GROUPS
Virgin

= -4 ORNL 171 GROUPS
Virgin

= -5 SAND-II 620 GROUPS..UP TO 18 MEV.
Virgin

= -6 SAND-II 640 GROUPS..UP TO 20 MEV.        Virgin

= -7 WIMS 69 GROUPS
Virgin

= -8 GAM-I 68 GROUPS
Virgin

= -9 GAM-II 99 GROUPS
Virgin

=-10
MUFT 54 GROUPS
Virgin

=-11 ABBN 28 GROUPS
Virgin

56-60    I5    NUMBER OF POINTS IN SOURCE SPECTRUM
Virgin

(MUST
BE AT LEAST TWO POINTS)
Virgin

= GREATER THAN 1 = READ FROM INPUT
Virgin

=  0 = SAME AS LAST CASE
Virgin

= -1 = CONSTANT
(ENERGY INDEPENDENT)
Virgin

= -2 = 1/E
Virgin

= -3 = BLACKBODY - PHOTON SPECTRUM
Virgin

= -4 = BLACKBODY - ENERGY SPECTRUM
Virgin

= -5 = TRANSMITTED SPECTRUM FROM LAST CASE    Virgin

NOTE, ALL SPECTRA, EXCEPT THE TRANSMITTED     Virgin

SPECTRUM FROM THE LAST CASE, WILL BE
Virgin

NORMALIZED SUCH THAT ITS INTEGRAL OVER
Virgin

ENERGY WILL BE UNITY.
Virgin

61-64  1X,3I1  SPATIALLY DEPENDENT OUTOUT                    Virgin

= 0 = NO
Virgin

= 1 = YES
Virgin

FOR THE 3 QUANTITIES
Virgin

COLUMN 67 FLUX
Virgin

68 REACTIONS
Virgin

69 AVERAGE CROSS SECTION
Virgin

65-65    I1    ENERGY DEPENDENT OUTOUT
Virgin

= 0 = NONE
Virgin

= 1 = INCIDENT SPECTRUM
Virgin

=
2 = TRANSMITTED SPECTRUM
Virgin

= 3 = INCIDENT REACTIONS
Virgin

= 4 = TRANSMIITED REACTIONS
Virgin

=
5 = TOTAL CROSS SECTION
Virgin

= 6 = REACTION CROSS SECTION
Virgin

5   1-11   E11.4  BLACKBODY TEMPERATURE IN EV
Virgin

12-22   E11.4  FLUX NORMALIZATION
Virgin

23-33   E11.4  REACTION NORMALIZATION
Virgin

CALCULATIONS WILL BE BASED ON THE SPECTRUM    Virgin

AND CROSS SECTIONS AS READ. AT OUTPUT THE     Virgin

RESULTS WILL BE MULTIPLIED BY THESE
Virgin

NORMALIZATION FACTORS.
Virgin

34-44    I11   DENSITY PROFILE                               Virgin

= 0 - UNIFORM - BASED ON TOTAL DENSITY
Virgin

= 1 - UNIFORM - TOTAL + REACTION DENSITY      Virgin

= 2 - TOTAL + LINEAR REACTION
Virgin

= 3 - LINEAR (TOTAL + REACTION)
Virgin

= 4 - TOTAL + SQUARE REACTION
Virgin

= 5 - SQUARE (TOTAL + REACTION)               Virgin

= 6 - TOTAL + CUBIC REACTION
Virgin

= 7 - CUBIC (TOTAL + REACTION)
Virgin

6-N   1-66  6E11.4  TARGET THICKNESSES IN CM
Virgin

IF SAME AS LAST CASE THIS SECTION IS NOT      Virgin

INCLUDED IN THE INPUT.
Virgin

VARY   1-66  6E11.4  TALLY GROUP ENERGY BOUNDARIES
Virgin

(NUMBER OF BOUNDARIES IS ONE MORE THAN
Virgin

THE NUMBER OF TALLY GROUPS)
Virgin

IF THE STANDARD OPTION (-11 TO 0) IS
Virgin

SELECTED
THIS SECTION IS NOT INCLUDED
Virgin

IN THE INPUT
Virgin

VARY   1-66  6E11.4  SOURCE SPECTRUM IN ENERGY (EV)-SOURCE
PAIRS   Virgin

(MUST BE AT
LEAST TWO POINTS)
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IF STANDARD OPTION (-5 TO 0) IS SELECTED THIS Virgin

SECTION IS NOT INCLUDED IN THE INPUT
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ANY NUMBER OF
CASES MAY BE RUN ONE AFTER ANOTHER.
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EXAMPLE INPUT
NO. 1
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-------------------
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CALCULATE THE
UNCOLLIDED FLUX AND CAPTURE (MT=102) THROUGH
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30 CM OF IRON
(DENSITY 7.87 G/CC). TALLY THE RESULTS USING
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THE TART 175
GROUP STRUCTURE. THE SOURCE WILL BE CONSTANT
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FROM 1 KEV TO 20
MEV. USE THE STANDARD ENDF/B INPUT DATA
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FILENAME.
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ENDFB.IN
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IRON 0 TO 30 CM
THICK.
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CONSTANT SOURCE
FROM 1 KEV TO 20 MEV.
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26000    1 7.87000+ 0 26000  102 7.87000+ 0     2    0    2 1100  Virgin

0.00000+ 0
1.00000+ 0 1.00000+ 0
0 0.00000+00
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0.00000+00
3.00000+01
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1.0000E+03
1.0000E+00 2.0000E+07 1.0000E+00
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EXAMPLE INPUT
NO. 2
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-------------------
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CALCULATE THE
UNCOLLIDED PHOTON FLUX THROUGH A MIXTURE OF SILICON  Virgin

AND IRON FOR 100
MEV PHOTONS INCIDENT. THE TRANSMISSION WILL BE    Virgin

CALCULATED FOR
21 THICKNESSES VARYING BETWEEN 0 AND 1 CM. THERE    Virgin

WILL BE ONLY 1
TALLY GROUP SPANNING A VERY NARROW ENERGY RANGE     Virgin

NEAR 100 MEV,
AND THE SOURCE SPECTRUM WILL BE CONSTANT OVER THE    Virgin

SAME ENERGY RANGE.
USE THE STANDARD ENDF/B INPUT DATA FILENAME     Virgin

BY LEAVING THE
FIRST INPUT LINE BLANK.
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(THIS IS A BLANK
LINE TO USE THE STANDARD INPUT FILENAME)
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100 MEV
PHOTONS
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SILICON + 5 %
IRON
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14000  521 2.30000+ 0 26000  521 1.15000- 1    21    1    2 1000  Virgin

0.00000+ 0
1.00000+ 0 1.00000+ 0
1 0.00000+00
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0.00000+00
5.00000-01 1.00000+00 1.50000+00 2.00000+00 2.50000+00 Virgin

3.00000+00
3.50000+00 4.00000+00 4.50000+00 5.00000+00 5.50000+00 Virgin

6.00000+00
6.50000+00 7.00000+00 7.50000+00 8.00000+00 8.50000+00 Virgin

9.00000+00
9.50000+00 1.00000+01
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9.99000+ 7
1.00100+ 8
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9.99000+ 7
1.00000+ 4 1.00100+ 8 1.00000+ 4
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