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International Atomic
Energy Agency
Nuclear Data Services
DOCUMENTATION SERIES OF
THE IAEA NUCLEAR DATA SECTION
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IAEA-NDS-80
Rev.
1
PROGRAM X4TOC4
(Version
2001-3)
Translation
of experimental data from the EXFOR format
to
a computation format
by
Dermott
E. Cullen and Andrej Trkov
Abstract: Experimental nuclear
reaction data are world-wide compiled in EXFOR format (see document IAEA-NDS-1).
The computer program X4TOC4 described in the present document translates
data from the rather flexible EXFOR format to the more rigid computation
format which is suitable for
input to further computer processing of the data including graphical plotting
(see document IAEA-NDS-79).
The program is available upon request cost free from the IAEA Nuclear
Data Section.
March
2001
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Nuclear Data Section
International Atomic Energy
Agency
P.O. Box 100
A-1400 Vienna
Austria
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e-mail:
services@iaeand.iaea.org
fax:
(43-1) 26007
cable:
INATOM VIENNA
telex:
1-12645
telephone:
(43-1) 2600-21710
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Online: TELNET or FTP: iaeand.iaea.org
username: IAEANDS for interactive
Nuclear Data Information System
usernames: ANONYMOUS for FTP file
transfer;
FENDL2 for FTP file transfer of FENDL-2.0;
RIPL for FTP file transfer of RIPL;
NDSONL for FTP
access to files sent to NDIS "open" area.
Web: IAEA NDS3
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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.
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.
Neither the originator of the data libraries nor the
IAEA assume any liability for their correctness or for any damages resulting
from their use.
96/11
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: Dermott E. Cullen and
Andrej Trkov, Program X4TOC4,
report IAEA-NDS-80, Rev. 1, March, 2001
PROGRAM X4TOC4
(Version
2001-3)
Translation
of experimental data from the EXFOR format
to
a computation format
Introduction
Enclosed is the documentation for program X4TOC4.
The program is designed to translate experimental
data from the EXFOR format (which allows variable units and column
order for data) to a computation format (which uses a fixed set of units and
column order for data).
The
enclosed documentation includes,
1)
A listing of the comment cards from the beginning of the program.
2)
A listing of the three translation dictionaries used by the program
3)
A listing of an example
output report.
4)
A listing of example EXFOR
data.
5)
A listing of the
corresponding data in the computation format.
6)
Plots of the data, obtained using program PLOTC4 (see document
IAEA-NDS-79).
The
enclosed documentation is up to date as of March 2001. The program
documentation on the comment cards at the beginning of the program and the
translation dictionaries are continuously updated. Before using this program
the user is advised to consult the comment cards at the beginning of the
program and the translation dictionaries for the latest documentation.
Version
2001-3
The comments can be extracted using system search
routines by copying to x4toc4.man all records beginning with C-.
For example:
Unix:
grep
C-M x4toc4.f
>x4toc4.man
VMS
search
x4toc4.f C-M /out=x4toc4.man
Dos
find
C-M x4toc4.for
>x4toc4.man
Program
X4TOC4
Comment
cards
USERS' GUIDE FOR PROGRAM X4TOC4
===============================
PURPOSE
-------
This program is designed to translate experimental data from the
EXFOR format to a computation format.
WHAT COMPUTERS WILL THE PROGRAM RUN ON
--------------------------------------
The program has been implemented on a variety of computers from
Cray and IBM mainframe to Sun workstations to a PC. The
program is small enough to run on virtually any computer.
EXFOR FORMAT
------------
The EXFOR format is designed to allow experimentally measured data
to be coded in a computer readable format in a very flexible form.
In particular the data can be entered in essentially any set of
units (e.g., eV vs. barns or KeV vs. milli-barns) and in any table
format; essentially the table may be entered exactly as published
by an author (e.g., energy followed by columns of cross sections
in any order).
The EXFOR format is table oriented in the sense that data from a
given measurement are collected together and can be presented in
a single, or as a series of tables.
The advantage of the EXFOR format is that since data can be coded
essentially as published by an author problems of unit conversion
and re-formatting tables prior to coding are avoided and the
author can easily check the coded data. The result is a greatly
improved reliability of the coded data.
The disadvantage of the EXFOR format is that since physically
comparable data from different measurements (e.g. Fe-56 total
cross sections) may be given in a variety of different units and
formats it is very difficult to use in applications. In addition
the table oriented EXFOR system makes it difficult to collect
together physically comparable data from different measurements.
COMPUTATION FORMAT
------------------
The computation format used by this program is designed to present
experimental data in a fixed set of units and column order. By
starting from data in the EXFOR format and translating data to
the computation format it is possible to combine the advantages
of the improved reliability of the data coded in the EXFOR format
with the advantages of a fixed unit and column order format for
use in subsequent applications.
In addition the computation format is point oriented (as opposed
the table oriented EXFOR format). Each line of the computation
format represents a single data point. This makes it possible to
sort data in the computation format into any desired order for use
in application, e.g., sort 26-Fe-26 (n,2n) data from a number of
measurements together into energy order to simplify comparisons.
EXFOR VS. COMPUTATION FORMAT
----------------------------
The computation format is not intended as a substitute for the
EXFOR format, rather the two are complementary. The EXFOR format
contains much more information than can be included in computation
formats and this information should be consulted and used during
evaluation. The computation format is only intended to simplify
use of the data during evaluation, or other applications.
RELATIONSHIP TO ENDF
--------------------
It is assumed that one of the major uses of this program will be
to prepare data for subsequent use in evaluation and/or to compare
available evaluated and experimental data. As such the computation
format has been designed to allow data to be reduced to a form in
which data are classified in a manner similar to ENDF data.
In particular the EXFOR classification of data by the EXFOR
keyword reaction (or ISO-QUANT, etc.) is replaced by classifying
the data by (1) projectile, (2) target - ZA, (3) type of data
(ENDF MF number), (4) reaction (ENDF MT number). In addition the
standard units used by the translation program were selected to
be the same as the units used by ENDF (e.g., eV, barns, etc.).
The result of putting data into the computation format is that it
is easy to decide if the data is comparable to evaluated data
(e.g. same ZA, MF, MT) and once it is decided that data is
comparable, evaluation and/or comparison is simplified because the
data is in the same units as ENDF (e.g., eV vs. barns).
EXTENSIONS OF ENDF CONVENTIONS
------------------------------
For all types of data which are physically comparable to data,
which can be included in the ENDF data, this program uses
the ENDF definitions of (1) type of data (ENDF MF number),
(2) reaction (ENDF MT number). For example all cross sections
are represented by MF=3, angular distributions by MF=4, energy
distributions by MF=5 and double differential distributions
by MF=6. Similarly for simple reactions such as total, elastic
etc., the data are translated into corresponding MT=1,2, etc.,
respectively.
Since many types of data which appear in EXFOR do not have a one
to one correspondence to data which appears in ENDF the ENDF
classification of type of data (MF) and reaction (MT) have been
extended to allow additional types of data and reactions to be
translated (e.g., define MF numbers for ratios, define MT numbers
for (n,np)+(n,na) reactions).
The ENDF MF is a 2 digit number and the MT is a 3 digit number.
In the computation format MF has been extended to 3 digits and the
MT has been expanded to 4 digits. These extensions allow the user
the flexibility to translate virtually any EXFOR data to a fixed
set of units and column order for subsequent use in applications.
Some extensions of MF and MT have already been established (for,
details see the input dictionaries described below) and if at all
possible these conventions should be followed by the user. The
user has the flexibility of establishing any conventions that may
be required to meet his or her needs, but in this case it is the
responsibility of the user to properly interpret and use the
translated data.
DIRECT COMPARISON TO ENDF DATA
------------------------------
Although the ENDF classification system of MF and MT is used for
translation, generally very little of the EXFOR data is directly
comparable to ENDF data. Generally cross sections (MF=3) are
directly comparable. However, it must be realized that angular
(MF=4) and energy (MF=5) and double differential (MF=6) data are
given in ENDF in a normalized (i.e., normalized to unity when
integrated) form, whereas data in EXFOR are generally given in an
un-normalized form (e.g.,angular distributions in barns/steradian).
After this program has been used to translate EXFOR data to the
computation format the user may make additional data directly
comparable to the corresponding ENDF data by either,
(1) Normalizing the data in the computation format, or,
(2) Converting ENDF data to un-normalized form.
This involves selecting an integrated cross section as a standard
to use for the comparison (e.g., for a 14.2 MeV elastic angular
distribution use the 14.2 MeV ENDF elastic cross section).
Since the selection of a standard to use for comparison in highly
application dependent it has been decided that it is better to use
this program to translate data exactly as given in EXFOR (except
for conversion to a standard set of units) and to allow the user
to subsequently select a standard for re-normalization.
CONTROL OF TRANSLATION
----------------------
The user has complete control over what data is translated, where
given types of data appear in the computation format and the units
of the data in the computation format.
This is accomplished by using three dictionaries which control
the translation. All three of these dictionaries are distributed
with this program. Each dictionary is a simple card image file
which may be modified by the user at any time to meet specific
needs. The three dictionaries are:
(1) EXFOR REACTION - PROJECTILE, MF, MT EQUIVALENCE
This dictionary tells the program for each EXFOR reaction
what projectile, MF and MT to output in the computation format
(e.g.,(n,tot) = neutron, MF =3 (cross section),MT =1 (total)).
If a reaction read from the EXFOR format is not found in this
dictionary, or the assigned MF or MT is not positive the EXFOR
data will simply be skipped and not translated. Using this
dictionary the user has control over which data is
translated
and what MF and MT are assigned to each EXFOR reaction.
(2) EXFOR COLUMN TITLE - COMPUTATION FORMAT OUTPUT FIELD
Once the EXFOR reaction has been translated and assigned an
equivalent MF and MT this dictionary tells the program where
to place each EXFOR column in the computation format. The
assigned MF number can be used to output an EXFOR column
with the same title into different columns of the computation
format based on different MF numbers. For example, for cross
sections (MF=3) the user may use EN-MIN and EN-MAX to define
an average incident energy to be output in the first field
of the computation format and an equivalent energy uncertainty
in the second field of the computation format. Alternatively,
for resonance integrals (MF=213) the user may decide to output
EN-MIN and EN-MAX in the first two fields of the computation
format to define the energy range of the resonance integral.
There are 8 output fields in the computation format and for
any given MF number the user may output any EXFOR column
into any of these fields. Any EXFOR title which is not
assigned to an output field 1 to 8 will be ignored and not
output. This allows the user to selectively translate portions
of EXFOR data tables to meet any given need. For example, by
simply modifying this dictionary the user has control over
whether an EXFOR column DATA-ERR3 is translated or ignored,
and if translated the user has control over which of the 8
computation format data fields DATA-ERR3 will appear in.
(3) EXFOR COLUMN UNITS - COMPUTATION FORMAT UNITS
This dictionary tells the program how to convert each EXFOR
unit into standard units. As distributed this dictionary will
convert all EXFOR units to ENDF compatible units. However,
the user has the option to change this
dictionary at any time
to obtain any output units to meet his or her needs. For
example if the user would like output in MeV vs. milli-barns
instead of eV vs. barns it is merely necessary to modify this
dictionary.
OPERATIONS ON DATA
------------------
In addition to the information described above each of the three
dictionaries allows the user to select from a menu of operations
which may be performed on the data (for a complete and up-to-date
list of available operations see the dictionaries). For example,
the reaction dictionary allows the user to specify that legendre
coefficients may be re-normalized, the title dictionary allows the
user to specify that EN-MIN and EN-MAX are to be converted to an
average energy and associated energy uncertainty and the units
dictionary allows the user to specify that angles should be
converted to cosines.
These operations are completely under the control of the user and
by simply modifying the dictionaries the user can control whether
or not each operation is performed (e.g., if you want to output
angles instead of cosines modify the units dictionary by removing
the option to convert from angle to cosine from the EXFOR units
ASEC, AMIN and ADEG).
COMPUTATION FORMAT UNITS
------------------------
As distributed the Units dictionary will convert all EXFOR units
to ENDF units:
eV =
energy
barns =
cross section
steradians = solid angle
seconds = time
kelvin =
temperature
If the user would like to obtain any other output units it is
merely necessary to modify the units dictionary (see units
dictionary for details).
A LEARNING PROGRAM
------------------
As distributed the three translation dictionaries do not contain
definitions of how to translate all EXFOR reactions, titles and
units. At the present time this program has only been used to
translate a small portion of the data included in the EXFOR system
and the dictionaries only contain sufficient information to
translate the EXFOR data which has been encountered to date.
It is difficult and dangerous to try to define translation rules
for all types of EXFOR data without examining actual EXFOR data.
therefore only when a new reaction, title or unit is encountered
during translation will the actual EXFOR data be examined, a
decision made as to how to best translate the data and the
dictionaries updated.
Generally once a given type of EXFOR data has been encountered and
the dictionaries updated to define how to translate the data the
same rules can be used to translate all similar data. Therefore
over a period of time user experience will be accumulated in the
translation dictionaries and the program will learn to properly
translate more and more types of EXFOR data.
UNDEFINED EXFOR REACTIONS, TITLES AND UNITS
-------------------------------------------
In order to assist the user to define new types of EXFOR data as
they are encountered during translation the output report from
this program will indicate the number of EXFOR reactions, titles
and units which have been encountered during translation which are
not defined in the translation dictionaries. In additional all
undefined reactions, titles and units will be written to output
Unit 4 (NEWX4).
Based on comparison to the reaction, title and units dictionaries
if an EXFOR reaction, title or units is encountered during
translation that is not defined in the dictionaries it will be
written to Unit 4 (NEWX4). This information is written in a form
that can be easily edited and added to a translation dictionary.
After updating the dictionaries if this program is then run a
second time using the same EXFOR data all of the EXFOR data can
be translated.
COMPUTATION FORMAT
------------------
The computation format uses a classification system and units
which are compatible with ENDF. Data is classified by (1) ZA
of projectile, (2) ZA of target, (3) metastable state of target,
(4) MF - type of data, (5) MT - reaction, (6) metastable state
of residual nucleus. To identify the source of the data the first
author and year and the EXFOR accession and sub-accession number
are included in the format. In addition, fields are assigned to
define the status of the EXFOR data (e.g., S = superceded),
whether data is in the laboratory or center-of-mass frame of
reference and the physical significance of the last 2 output
fields (LVL = level energy, HL = half-life). Finally the format
includes 8 fields in which the output data are contained (e.g.,
incident energy, data, cosine, uncertainties, etc.)
Columns Description
------- -----------
1- 5
Projectile ZA (e.g. neutron =1, proton =1001)
(defined by reaction dictionary).
6- 11 Target ZA (e.g.
26-Fe-56 = 26056)
(defined by EXFOR reaction).
12 Target metastable
state (e.g. 26-FE-56m = M)
(defined by EXFOR reaction).
13- 15 MF (ENDF
conventions, plus additions)
(defined by reaction dictionary).
16- 19 MT (ENDF
conventions, plus additions)
(defined by reaction dictionary).
20 Product metastable
state (e.g. 26-FE-56M = M)
(defined by EXFOR reaction).
21 EXFOR status
(defined by EXFOR keyword status).
22 Center-of-mass flag
(C=center-of-mass, blank=lab)
(defined by EXFOR title dictionary).
23- 94 8 data
fields (each in E9.3 format defined below)
(defined by MF and title dictionary).
95- 97 Identification
of data fields 7 and 8
(e.g., LVL=level, HL=half-life, etc.).
For a complete list of codes see title dictionary
(defined by MF and title dictionary).
98-122 Reference
(first author and year)
(defined by EXFOR keywords title and reference).
123-127 EXFOR
accession number
(defined by EXFOR format).
128-130 EXFOR
sub-accession number
(defined by EXFOR format).
131 Multi-dimension
table flag
(defined by EXFOR keyword reaction or common fields).
PRECISION OF THE 8 DATA FIELDS
------------------------------
If written in normal format E9.2 format the output from this
this program would give data to only 2 or 3 digits of accuracy,
depending on the computer used (e.g., 0.23E+02 or 2.34E+01), which
is not sufficient for many applications (e.g., energy of cross
section points in the resonance region).
In order to avoid this problem this program will output data in
a special compatible format to allow up to 7 digits of accuracy
(i.e. more than the full word accuracy of IBM computers).
Numbers between 0.01 and less than 10 million will be output in F
(rather than E format). For example, the energy 12.3456 KeV will
be output as 123456.0. Numbers less than 0.01 or greater than
10 million will be output in E format, but without as E and an
exponent of 1 or 2 digits. For example 14.123 MeV will be output
as "1.4123+7".
These output conventions have been used for many years with ENDF
related programs and have been proven to be FORTRAN compatible for
use on virtually any computer. For example, any fortran program
which is written to read this data using an E9.2 format will read
the data properly whether the data is actually in E or F format.
Generally maintaining high precision in the data is most important
for the independent variable, particularly incident energy. Since
we do not expect very narrow resonance structure below 0.01 eV or
above 10 MeV generally these output conventions will maintain the
accuracy of the EXFOR data to meet requirements.
DEFINITION OF 8 COMPUTATION FORMAT DATA FIELDS
----------------------------------------------
The user may use the title dictionary to output any EXFOR column
into any computation format data field. As distributed the
title
dictionary contains a number of conventions which if at all
possible should be followed by the users. The general definitions
of the 8 computation format data fields are:
Data field Definition
---------- ----------
1
Projectile incident energy
2
Projectile incident energy uncertainty
3
Data, e.g., cross section, angular distribution, etc.
4
Data uncertainty
5
Cosine or legendre order
6
Cosine uncertainty
7
Identified by columns 95-97 (e.g.,level E, half-life)
8
Identified by columns 95-97 (e.g.,level E, uncertainty)
The physical significance of each field is defined by the assigned
MF number. For example, for MF =3 (cross sections), columns 1 and
2 contain the incident projectile energy and its uncertainty in
eV, respectively and columns 3 - 4 contain the cross section and
its uncertainty in barns, respectively and columns 7 and 8 may
contain a level energy and its uncertainty in eV or a half-life
and its uncertainty in seconds.
SPECIAL CONVENTIONS
The above conventions are appropriate for most types of data
in the ENDF system. In order to allow this program to plot
additional types of data the following special conventions have
been adopted,
Cross section ratios - Field
5 = MT of denominator.
(MF = 203)
Field 6 = ZA of denominator.
Resonance integrals -
Field 1 = lower energy limit.
(MF = 213)
Field 2 = upper energy limit.
Spectrum averages
- Field 1 = lower energy limit.
(MF = 223)
Field 2 = upper energy limit.
Fission yield data -
Field 5 = ZA of fission fragment.
(MF = 801)
Field 6 = mass of fission fragment.
Production
- Field 6 = ZA of product.
(MT = 9000-9999)
See, remarks below on metastable state flags.
REQUIRED DATA FIELDS
--------------------
For various types of data the program will check if all required
fields are defined and non-blank. If they are not warning messages
will be printed. If the data field (Field 3) is not defined or
blank the data point will not be output. If the data field is not
defined this usually indicates an error in the EXFOR data. Blank
data fields are quite common in multi-dimensional tables and a
warning may or may not indicate an error (check the EXFOR data to
see if it is correct).
The program considers that the following fields are required:
MF (Data type)
Data field (X = Required)
--------------------- -------------------------
1
2 3
4 5 6
7 8
--------------------- -------------------------
3 (Cross sections)
X X
4 (Angular dist.)
X X
X
5 (Energy dist.)
X X
X
6 (Double diff.) X
X X
X
154 (Legendre coeff.) X X
X
203 (Ratios)
X X
X X
801 (Yield data).
X X
X X
(See the above definition of the 8 data fields).
MULTI-DIMENSIONAL TABLES
------------------------
The program can translate multi-dimensional EXFOR tables for:
(1) Multiple reactions following the EXFOR keyword reaction
(ISO-QUANT, etc.) with each reaction identified by a character
in column 11.
(2) Single reactions with multiple common fields each identified
by a character in the eleventh column of each field.
(3) The old ISO-QUANT, etc. convention of reactions separated by
commas, e.g., ((90-TH-232,NG)/(29-CU-0,NG)),(29-CU-0,NG)).
TRANSLATION OF EXFOR REACTIONS
------------------------------
Not all EXFOR reactions (ISO-QUANT, etc.) can be translated by
this program. In order to translate each reaction the program will
first break each reaction into a series of simple reactions and
remove and save the target and residual ZA, E.G.:
((26-FE-56(N,G)26-FE-57-M1,,SIG)/(26-FE-56(N,G)26-FE-57-G,,SIG))
is broken down to define
ZA-target = 26056 , ZA-residual = 260571, reaction = (N,G),SIG
Note residual metastable state flags. See explanation below.
The program will then define an equivalent MF, MT for each
reaction.
The program will next translate the following types of
reactions:
(1) Simple reactions
(N,G),SIG
(2) Equivalent reactions
((N,G),SIG)=...anything else....
After decoding the first simple reaction the program assumes
that the first simple reaction is truly equivalent to the
remainder of the reaction and defines ZA, MF and MT based on
the first simple reaction.
(3) Simple ratios
((N,G)M1/G,,SIG/RAT) or ((N,G)M1,SIG)/((N,G)G,SIG)
(4) Complex reactions - all with the same equivalent ZA
((N,EL),WID,,G)*((N,G),WID)/((N,TOT),WID)
(5) Other reactions
(((N,G),SIG)/((N,G),SIG),(N,G),SIG))
If the reaction is not one of the above types the program will
try to use the entire EXFOR reaction, including target and
residual ZA and see if it is defined in reaction equivalent
dictionary. If an MF, MT is defined for the entire reaction
the program will use the target and residual ZA from the first
simple reaction to translate the data. This last form may be
used to insure that almost all EXFOR reaction can
be
translated, regardless of how complicated it is (for examples
see reaction dictionary) however the user should carefully
check the output to insure that the data has been translated
as intended.
The only reactions that have so far been found that cannot be
correctly translated are ratios of production cross sections,
e.g., (29-CU-0(P,X)26-FE-56)/(28-NI-0(P,X)26-FE-58)
because ratio data requires fields 5 and 6 for the denominator
MT and ZA and ratio data requires field 5 for the product ZA.
When this case is encountered the program will print an error
message and output the denominator MT and ZA in fields 5 and 6.
In this case the output will identify the numerator as ZA=29000,
MT=9001 and the denominator as ZA=28000, MT=9001. One solution
is to modify the output of this program by defining two reactions,
e.g., MT = 8001 = (p,x) 26-Fe-56 and MT = 8002 = (p,x) 26-Fe-58,
modify the numerator MT to 8001 and denominator MT to 8002 and
then properly interpreting the data using these definition in all
applications (for examples, see program PLOTC4 input directions
for proton induced reactions).
OUTPUT REPORT
-------------
This program will write a report on Unit 6 (OUTP) to allow the
user to monitor the translation of the EXFOR data. It is extremely
important that the user read this report and not simply assume
that all of the data has been properly translated.
After identifying each EXFOR accession, sub-accession number,
ZA, MF, MT and reaction the program can print two types of
messages:
WARNING =
Something unusual has occurred. The user should
carefully check to insure that the output data has
been properly translated.
OPERATION = One of the
defined reaction, title or unit operations
has been performed on the data. The user should
carefully
check to insure that the proper operation
has been performed.
If the user does not agree with how the data has been translated
the three dictionaries may to be modified and the program re-run.
For example, if the program prints a warning that the title
dictionary tells it to output E-ERR1, E-ERR2, E-ERR3 all in the
same computation format field, followed by an operation that says
the program will only output E-ERR1 and ignore the other 2 EXFOR
fields, if the user would rather output E-ERR2 and ignore E-ERR1
and E-ERR3 it is merely necessary to modify the title dictionary
to ignore E-ERR1 and E-ERR3 and select E-ERR2 and then re-run the
program.
METASTABLE STATE
----------------
The computation format allows the metastable state of the target
and residual nucleus to be identified. For ratio data metastable
state of both numerator and denominator of the ratio may be
defined.
The metastable state of the target is identified in column 12 and
the metastable state of the residual nuclues in column 20. For
ratio data the metastable state of the denominator target and
residual nucleus are identified by output the denominator ZA and
MT in the form ZA.M and MT.M (e.g., 26056.9 and 102.1). Columns
12 and 20 could contain characters such as M, but to maintain the
eight output fields in strictly numerical form the denominator
ZA.M and MT.M will be output in numerical form. The possible
characters that may appear in columns 12 or 20 and their numerical
equivalents used with ratio denominator ZA and MT include:
Definition Column
12 or 20 Equivalent
---------- ---------------
----------
ground
G
0
m1
1
1
m2
2
2
m3
3
3
m4
4
4
m5
5 5
unknown
?
6
m
M
7
more than 1
+
8
all or total
T
9
all or total
blank
9
By convention if an EXFOR reaction does not specify a metastable
state the state is defined in the computation format to be..ALL..
(i.e., blank in column 12 or 20, 9 in ratio ZA or MT).
For example, for a ratio if the ZA.m and MT.m are output as
26056.9 and 102.1, respectively the ratio denominator target is
26-Fe-56 (all) and the reaction is capture (MT=102) leaving the
residual nucleus in the m1 state.
NOTE: Since most data will not contain a metastable state flag
the above convention to output the ZA and MT of the denominator
of ratios allows the user to read and use the denominator ZA and
MT as integers (effectively ignoring any metastable state flag) or
if necessary to determine the metastable state.
EXFOR STATUS
------------
Column 21 of each computation format record may contain blank
(status not specified) or one to the following characters:
Column 21 Definition
--------- ----------
U
Un-normalized (indicated by unit translation dictionary)
This condition has priority over the EXFOR status and
is used to indicate that the data is not in standard
output units).
A
Approved by author
C
Correlated
D
Dependent
O
Outdated
P
Preliminary
R
Re-normalized
S
Superceded
If data has any other EXFOR status (e.g., translated from SCISRS)
it will be ignored and the status field will be output as blank.
INPUT
FILES
-----------
Unit Description
---- -----------
10 EXFOR data (to be
translated) (BCD - 80 characters/record)
12 EXFOR reaction
dictionary (BCD
- 80 characters/record)
14 EXFOR title
dictionary
(BCD - 80 characters/record)
15 EXFOR units
dictionary
(BCD - 80 characters/record)
OUTPUT FILES
------------
Unit Description
---- -----------
4 List of all
undefined EXFOR reactions, titles and units
found during the translation (if any).(BCD -
80 characters)
6 Output report
(BCD - 132 characters)
11 Computation
format experimental data (BCD -
131 characters)
SCRATCH FILES
-------------
NONE
INPUT PARAMETERS
----------------
None
REPORTING ERRORS
----------------
In order to improve this code and make future versions more
compatible for use on as many different types of computers as
possible please report all compiler diagnostics and/or operating
problems to the author at the above address.
Please remember if you simply report "I'VE GOT A PROBLEM" and
do
not adequately describe exactly how you were using the program
it will be impossible for the author to help you. When a problem
arises please write to the author, describe the problem in as much
detail as possible, identify the version of the program that you
are using (e.g. Version 2001-3) and send the following information
in computer-readable form (e-mail, floppy disc, etc.) to the author:
(1) A copy of the program you are using
(2) A copy of compiler diagnostics (if any)
(3) A copy of the JCL deck you used to execute the program
(4) A copy of the 3 translation dictionaries you are using
(5) A copy of the EXFOR format data you using
(6) A copy of the computation format data you produce
(7) A copy of the output report from the program.
Without all of this information it is impossible to exactly
simulate the problem that you ran and to determine the source
of your problem.
*****
COMPUTER DEPENDENT CODING ******
COMPUTER
DEPENDENT CODING
-------------------------
*
This program is designed to be used with a Fortran-77 or
Fortran-90 compiler.
*
The only compiler dependent format statements involve,
(1) CHARACTER*1 and CHARACTER*4
(2) Testing for errors and end of file during reads.
*
It is assumed that characters are stored in successive storage
locations and that characters may be treated as continuous strings
of characters in either CHARACTER*4 or CHARACTER*1 format.
*
For example, if one subroutine contains,
CHARACTER*4 BCD
DIMENSION BCD(10)
the array BCD is assumed to be an array of 40 characters in
successive byte locations.
It is assumed that this array can be passed as an argument to
another subroutine and used as CHARACTER*1, e.g.,
CALL DUMMY(BCD)
SUBROUTINE DUMMY(BCD)
CHARACTER*1 BCD
DIMENSION BCD(40)
*
This convention will work on all 32 bit per word computers (e.g.,
IBM or IBM compatible computers).
*
For longer word length computers (e.g., CDC or CRAY) it is
suggested that before implementing and using this program the
user first verify that character strings can be treated as
described above, e.g., write a simple program to read a character
string of 40 characters in CHARACTER*4 format, pass it to a
subroutine which uses the character string in CHARACTER*1 format
and print the character string in the subroutine. If the character
string is printed as a continuous string you will be able to use
this program. If the character string is not printed as a
continuous string it is not recommended that you use this rogram.
*
This program using the Fortran-77 convention for testing for
reading errors and end of file during reads, e.g.,
READ(10,1000,END=100,ERR=200) A,B,C,D
Reaction
Dictionary
EXFOR REACTION - MF/MT EQUIVALENCE TABLE
1
========================================
1
COMMENT CARDS ARE DEFINED BY A 1 IN COLUMN 80
1
REACTION DEFINITIONS MUST HAVE A BLANK COLUMN 80
1
WARNING...FAILURE TO FOLLOW THIS CONVENTION WILL
RESULT IN ERRORS
1
1
FORMAT
1
======
1
COLUMNS DEFINITION
1
======= ==========
1
1- 48
EXFOR REACTION (WARNING...DO NOT GO BEYOND COLUMN 48).
1
49- 53
PROJECTILE ZA (E.G. NEUTRON = 1, PROTON = 1001)
1
54- 56
MF NUMBER (USE ENDF/B CONVENTION FOR MF =1 TO 99, MF=100 TO 999
1
TO TRANSLATE DATA NOT EQUIVALENT TO ENDF/B)
1
57- 60
MT NUMBER (USE ENDF/B CONVENTION FOR MT =1 TO 999, MT=1000 TO 9999
1
TO TRANSLATE DATA NOT EQUIVALENT TO ENDF/B)
1
61- 63
OPERATION NUMBER (SEE, LIST BELOW FOR DEFINITIONS).
1
1
FOR COMPLICATED REACTIONS OF OVER 48 CHARACTERS IT IS
ONLY NECESSARY TO
1
LIST THE FIRST 48 CHARACTERS, AS OPPOSED TO THE ENTIRE
REACTION, AS LONG
1
AS THE FIRST 48 CHARACTERS UNIQUELY DEFINE THE
REACTION, E.G., SEE
1
REACTION DEFINITIONS UNDER YIELD DATA.
1
1
TRANSLATION CONVENTIONS
1
=======================
1
NOTE, THE PROGRAM TO CONVERT DATA FROM THE EXFOR TO
COMPUTATION FORMAT
1
HAS BEEN DESIGNED TO ALLOW THE USER TO CONVERT
VIRTUALLY ANY EXFOR DATA
1
TO THE COMPUTATION FORMAT. THE USER SHOULD USE THE
ENDF/B DEFINITION OF
1
MF AND MT IF POSSIBLE. IN ADDITION THE SPECIAL
EXTENSIONS OF MF AND MT
1
DEFINED BELOW SHOULD BE FOLLOWED, IF POSSIBLE. IF THE
USER TRANSLATES
1
OTHER DATA YOU SHOULD BE AWARE THAT THE TRANSLATION
PROGRAM MAY BE USED
1
TO CONVERT EXFOR DATA TO STANDARD UNITS AND COLUMN
ORDER, BUT THE USER
1
MUST WRITE PROGRAMS TO SUBSEQUENTLY OPERATE ON THE
TRANSLATED DATA.
1
1
THE AUTHOR OF THE TRANSLATION CODE ACCEPTS NO
RESPONSIBILITY TO PROVIDE
1
SPECIAL PROGRAMS TO TREAT SPECIAL TYPES OF DATA
TRANSLATED BY THE USER
1
THE USER.
1
1
DEFINED MF NUMBERS
1
==================
1
FOR CONVENIENCE IN LISTING AND/OR PLOTTING DATA THE
FOLLOWING MF NUMBERS
1
HAVE BEEN DEFINED,
1
1
DATA TYPE
MF
SPECIAL CONVENTIONS
1
=========
==== ===================
1
SAME AS ENDF/B
3- 6 (PARTICLE/ISOTOPE
MT=9000
1
PRODUCT
DEFINED BY
1
FIELD 6 =ZA)
1
LEGENDRE COEFFICIENTS
154
1
RATIOS
203 (DENOMINATOR DEFINED BY
1
FIELD 5 =MT.MF
1
FIELD 6 =ZA.MI
1
MF - FINAL METASTABLE STATE
1
MI - INITIAL METASTABLE STATE
1
RESONANCE INTEGRALS
213
1
SPECTRUM AVERAGES
223
1
TRIPLE DIFFERENTIAL
306
1
NUCLEAR AND RESONANCE PARAMETERS
400-499
1
FISSION YIELD DATA
800-899 (FISSION PRODUCT DEFINED BY
1
FIELD
5 =ELEMENT
1
FIELD 6 =MASS)
1
LEVEL DENSITY PARAMETER
900
1
1
DEFINED MT NUMBERS
1
==================
1
FOR CONVENIENCE IN LISTING AND/OR PLOTTING DATA THE
FOLLOWING MT NUMBERS
1
HAVE BEEN DEFINED,
1
1
REACTION
MT 1
========
====
1
SAME AS ENDF/B
1- 999
1
(N,N+P)
1001 * MT EXTENSIONS
1
(N,N+P)+(N,P)
1002 MT =1000 +
ASSIGNED MT
1
(N,N+P)+(N,D)
1003 NUMBER
1
(N,N+A)+(N,A)
1004
1
(N,3-LI-7)PAR,SIG
1200
1
(N,P)DI
2103 * DIRECT MT = MT + 2000
1
(N,P)CN
3103 * COMPOUND MT = MT + 3000
1
(P,N)
8001 * LIGHT PARTICLE INDUCED
1
(D,N)
8002 NEUTRON PRODUCTION MT =
1
(T,N)
8003 8000 + ASSIGNED MT
1
(A,N)
8004
1
(N,X)
9000 PARTICLE/ISOTOPE PRODUCTION
1
(P,X)
9001 (PRODUCT DEFINED BY
1
(D,X)
9002
FIELD 6 =ZA)
1
(T,X)
9003
1
(HE-3,X)
9004
1
(A,X)
9005
1
1
DEFINITION OF 8 COMPUTATION FORMAT DATA FIELDS
1
==============================================
1
IN ORDER TO ESTABLISH STANDARDS IF AT ALL POSSIBLE THE
USER SHOULD
1
FOLLOW THE BELOW CONVENTIONS,
1
1
DATA FIELD
DEFINITION
1
==========
==========
1
1
PROJECTILE INCIDENT ENERGY
1
2
PROJECTILE INCIDENT ENERGY UNCERTAINTY
1
3
DATA (E.G., CROSS SECTION, ANGLE OR ENERGY DISTRIBUTION)
1
4
DATA UNCERTAINTY
1
5
COSINE OR LEGENDRE ORDER
1
6
COSINE UNCERTAINTY
1
7
SECONDARY ENERGY
1
8
SECONDARY ENERGY UNCERTAINTY
1
1
SPECIAL CONVENTIONS
1
===================
1
CROSS SECTION RATIOS
- FIELDS 5 WILL CONTAIN MT AND FIELD 6 WILL
1
CONTAIN ZA OF THE DENOMINATOR OF THE RATIO 1
RESONANCE INTEGRALS
- FIELDS 1 AND 2 WILL CONTAIN LOWER AND UPPER 1
ENERGY LIMITS
1
SPECTRUM AVERAGES
- FIELDS 1 AND 2 WILL CONTAIN LOWER AND UPPER 1
ENERGY LIMITS
1
FISSION YIELD DATA
- FIELD 5 WILL CONTAIN THE ELEMENT ZA AND FIELD
1
FIELD 6 WILL CONTAIN THE MASS
1
PRODUCTION
- FIELD 6 WILL CONTAIN THE ZA OF THE PARTICLE OR
1
ISOTOPE PRODUCED
1
1
DEFINED OPERATIONS
1
==================
1
TO PERFORM ANY OF THE FOLLOWING OPERATIONS ON THE
EXFOR DATA ENTER ONE
1
OF THE FOLLOWING NUMBERS IN COLUMN 63 (E.G., FOR
SPECTRUM AVERAGED DATA
1
IF NO ENERGY IS GIVEN TO CREATE AN ENERGY = 0.0253 EV
INSERT A 1 IN
1
COLUMN 63 OPPOSITE (N,G),SIG,,MXW)).
1
1
ALL OPERATIONS ON DATA (COLUMN 3) WILL ALSO BE
PERFORMED ON THE DATA
1
ERROR (COLUMN 4).
1
1
(1) IF NO EN DEFINE EN = 0.0253 EV (THERMAL SPECTRUM
AVERAGE).
1
(2) IF NO EN DEFINE EN =2.0 MEV (FISSION SPECTRUM
AVERAGE).
1
(3) DATA = DATA/2.0 (CONVERT (N,EL),,WID,,2G TO (N,EL),,WID,,G)).
1
(4) DATA = DATA/(2*L+1) (LEGENDRE COEFFICIENTS).
1
(5) DATA = DATA/F(0) (F(0) = ZEROTH ORDER LEGENDRE
COEFFICIENT)
1
(6) DATA = DATA/(F(0)*(2*L+1)) (F(0) = ZEROTH ORDER
LEGENDRE COEFFICIENT)
1
1
NOTE, THESE CONVENTIONS ARE CODED INTO THE TRANSLATION
PROGRAM.
1
THE USER SHOULD NOT ADD ANY OPERATIONS TO THIS LIST
UNLESS THEY ARE
1
ALSO INCLUDED IN THE TRANSLATION PROGRA.
1
1
REACTION
PROJECTILE MF MT OPERATION 1
======================================================================
1
1
CROSS SECTIONS
1
1
(N,TOT),SIG
1
3 1
0
TOT
1 3
1 0
(N,EL),SIG
1 3
2 0
NF
1 3
18 0
NG
1
3 102 0
(N,P),SIG
1 3 103
0
(N,P),SIG,,A
1 3 103 0
(N,D),SIG
1 3 104
0
NT
1
3 105 0
NA
1 3 107
0
(N,A),SIG
1 3 107
0
(N,2A),SIG
1 3 108
0
(N,2A)PAR,SIG
1
31108 0
(N,T+2A),SIG
1 3 113 0
(N,T+2A)PAR,SIG
1 31113 0
(N,N+P),SIG
1 31001
0
((N,P),SIG)+((N,N+P),SIG)
1
31002 0
((N,N+P),SIG)+((N,D),SIG)
1 31003
0
(N,3-LI-7)PAR,SIG
1 31200 0
(N,P)DI,SIG
1 32103
0
(D,N)PAR,TTY,G,,EXP
1002
0 0
0
(D,N)PAR,SIG,G,,EXP
1002 38002
0
1
ANGULAR DISTRIBUTIONS
1
1
(N,EL),DA
1 4
2 0
(N,INL),DA
1 4
4 0
(N,INL)PAR,DA
1
4 51
0
(N,INL)PAR,DA,G,A
1 4 51
0
(N,P),DA
1 4 103
0
(N,P)PAR,DA
1 41103
0
(N,N+P),DA,P
1
41001 0
((N,P),DA)+((N,N+P),DA,P)
1 41002
0
(N,P)DI,DA
1 42103
0
1
DOUBLE DIFFERENTIAL DATA
1
1
(N,2N),DA/DE
1 6 16
0
(N,N+A),DA/DE,A,REL
1 6
22 0
(N,N+P),DA/DE,P
1 6 28
0
(N,P),DA/DE
1 6 103
0
(N,A),DA/DE,,REL
1 6 107 0
((N,P),DA/DE)+((N,N+P),DA/DE,P)
1 61002
0
((N,A),DA/DE,,REL)+((N,N+A),DA/DE,A,REL)
1 61004
0
1
PARTICLE/ISOTOPE PRODUCTION
1
1
THE PRODUCED PARTICLE OR ISOTOPE WILL BE DEFINED BY
OUTPUTTING ZA IN
1
FIELD 6.
1
1
(N,X),SIG
1 39000
0
(N,X)CN,SIG
1 39000
0
(P,X),SIG
1 39001
0
(D,X),SIG
1
39002 0
(T,X),SIG
1 39003
0
(HE-3,X),SIG
1 39004 0
(A,X),SIG
1 39005
0
(N,X),DA
1
49000 0
(N,X)PAR,DA
1 49000
0
1
LEGENDRE COEFFICIENTS
1
OPERATION FLAGS ARE SET TO REDUCE ALL LEGENDRE
COEFFICIENTS TO THE FORM,
1
D(SIGMA)/D(MU)=1.0 +SUM(L=1 TO N) (2*L+1)*F(L)*P(L,MU)
1
(I.E., ENDF/B CONVENTION - COEFFICENTS NORMALIZED TO
F(0) WITH 2*L+1)
1
1
(N,EL),DA,,LEG/RSL
1154 2 0
(N,EL),DA,,LEG/RS
1154 2 4
(N,EL),DA,,LEG/RSD
1154
2 4
(N,EL),DA,,LEG/2L2
1154 2 5
(N,EL),DA,,LEG/L4P
1154 2 5
(N,EL),DA,,LEG
1154 2
6
(N,EL),DA,,LEG/1K2
1154
2 6
(N,EL),DA,,LEG/RS0
1154 2 6
(D,N),DA,,LEG/1K2
10021548002 6
(A,N)PAR,DA,,LEG/RS0,EVAL
20041548004 6
1
RATIOS
1
1
SIMPLE CROSS SECTION (MF=3) RATIOS, E.G.
(90-TH-232,MF)/(94-PU-238,NF)
1
WILL BE AUTOMATICALLY TRANSLATED AND NEED NOT BE
INCLUDED IN THE BELOW
1
LIST. WHEN SIMPLE RATIOS ARE TRANSLATED THE
DENOMINATOR WILL BE DEFINED
1
BY OUTPUTTING MT IN FIELD 5 AND ZA IN FIELD 6. THE
FOLLOWING LIST SHOULD 1
ONLY BE USED TO DEFINE COMPLEX RATIOS.
1
1
(N,P),SIG/RAT
1203 103 0
1
RESONANCE INTEGRALS
1
1
(N,G),RI
1213
102 0
(N,G),RI,,RAW
1213 102 0
1
SPECTRUM AVERAGES
1
1
(N,G),SIG,,MXW
1223 102 1
(N,G),SIG,,FIS
1223 102 2
1
TRIPLE DIFFERENTIAL DATA
1
1
(N,2N+P),DA/DE/DE,N/N/P
1306 103 0
1
NUCLEAR AND RESONANCE PARAMETERS
1
1
(0,0),TEM 04016001
0
(N,0),L
14026002 0
(N,0),J
14026003 0
(N,0),D
14026004 0
(N,TOT),WID
14026010 0
(N,EL),WID
14026021 0
(N,EL),WID,,G
14026022 0
(N,EL),WID/RED
14026023 0
(N,EL),WID/RED,,G
14026024 0
(N,EL),WID/RED,,2G
14026024 3
(N,G),WID
14026031 0
(N,G),WID,,G
14026032 0
(N,G),WID,,2G
14026032 3
((N,EL),WID,,G)*((N,G),WID)/((N,TOT),WID)
14026051 0
(N,EL),STF
14036001 0
(N,G),ARE
14046001 0
(N,G),WID,,AV
14056001 0
1
YIELD DATA (USUALLY FISSION)
1
1
(N,F)ELEM/MASS,CUM,FY,,SPA
1801 18
0
(N,F)ELEM/MASS,CUM,FY
1801 18 0
(N,F)ELEM/MASS,IND,FY,,MXW
1801 18
0
(N,F)MASS,CHN,FY,,MXW
1801
18 0
((N,F)ELEM/MASS,IND,FY,,MXW)/((N,F)MASS,CHN,FY,,
1802 18
0
(N,F),DA,FF,COS/RSD
1 41016
0
(G,F),DA,FF,REL,EXP
0 41019
0
(N,F),DA,FF,LEG/RSD
11541016 4
1
LEVEL DENSITY PARAMETER
1
1
LDP
19001800 0
Titles
Dictionary
EXFOR COLUMN TITLE TO COMPUTATION FORMAT OUTPUT COLUMN
TABLE
1
============================================================
1
COMMENT CARDS ARE DEFINED BY A 1 IN COLUMN 80
1
REACTION DEFINITIONS MUST HAVE A BLANK COLUMN 80
1
WARNING...FAILURE TO FOLLOW THIS CONVENTION WILL
RESULT IN ERRORS
1
1
FORMAT
1
======
1
COLUMNS DEFINITION
1
======= ==========
1
1- 10
EXFOR TITLE
1
11- 15
LOWEST MF NUMBER
1
16- 20
HIGHEST MF NUMBER
1
21- 25
COMPUTATION FORMAT OUTPUT FIELD (1 TO 8)
1
26- 30
OPERATION NUMBER (SEE, LIST BELOW FOR DEFINITIONS)
1
33- 35
DEFINITION OF FIELDS 7 AND 8...SEE BELOW LIST
1
(DEFINITION MUST BE RIGHT ADJUSTED TO END IN COLUMN 35).
1
ONLY ONE OF THE FOLLOWING SHOULD BE USED,
1
LVL=LEVEL
HL=HALF-LIFE E2=SECONDARY
ENERGY
1
DLV=LEVEL RANGE EXC=EXCITATION
DE2=SECONDARY ENERGY RANGE
1
MIN=E-MIN
MAX=E-MAX
1
1
REACTION DEFINED MF
1
===================
1
NOTE, THE REACTION DEFINED MF NUMBER CAN BE USED TO
OPERATE ON AND
1
OUTPUT THE SAME TITLE IN DIFFERENT WAYS FOR DIFFERENT
TYPES OF DATA
1
(E.G., SEE EN-MIN AND EN-MAX BELOW).
1
1
DEFINED OPERATIONS
1
==================
1
TO PERFORM ANY OF THE FOLLOWING OPERATIONS ON AN EXFOR
TITLE ENTER ONE
1
OF THE FOLLOWING NUMBERS IN COLUMN 30 (E.G., TO SET
THE CENTER-OF-MASS
1
SYSTEM FLAG THE EXFOR TITLE DATA-CM HAS A 6 IN COLUMN
30).
1
1
(1) MULTIPLE FIELDS...ALWAYS CHOOSE THIS FIELD.
1
(2) MULTIPLE FIELDS...CHOOSE THE FIRST FIELD.
1
(3) MULTIPLE FIELDS...NEVER CHOOSE THIS FIELD.
1
(4) MULTIPLE FIELDS...CHOOSE THE LARGEST FIELD, E.G.
ERRORS.
1
(5) MULTIPLE FIELDS...COMBINE FIELDS QUADRATICALLY,
E.G. ERRORS,
1
(EN-ERR = SQRT(EN-ERR1**2 + EN-ERR2**2)).
1
(6) SET CENTER-OF-MASS SYSTEM FLAG IN OUTPUT
1
(7) MULTIPLE FIELDS...COMBINE FIELDS TO DEFINE
AVERAGE, BUT NOT ERROR,
1
(EN-MIN AND EN-MAX TO DEFINE EN). 1
(8) MULTIPLE FIELDS...COMBINE FIELDS TO DEFINE AVERAGE
AND ERROR,
1
(EN-MIN AND EN-MAX TO DEFINE EN AND EN-ERR). 1
(9) -MIN/-MAX MUST APPEAR TOGETHER, E.G. EN-MIN/EN-MAX
- RESONANCE INTEGRAL, 1
(IF MISSING DEFINE -MIN= 0 OR -MAX= 15 MEV).
1
(10) MULTIPLE FIELDS..CHOOSE LARGEST AND SMALLEST IN 2
SUCCESSIVE FIELDS,
1
(MULTIPLE E-LVL).
1
1
MF MF OUTPUT
1
LOW HIGH FIELD OPERATION
1
1
INITIAL ENERGY
1
1
EN
1 999 1
1
EN-RES
1
999 1
1
EN-DUMMY
1 999 1
0
EN-MIN
121 399
1 9
EN-MAX
121 399
2 9
EN-MIN
1 999 1
8
EN-MAX
1 999 1
8
EN-RSL
1 999 2
4
EN-ERR
1 999 2
4
EN-RES-ERR
1 999
2 4
EN-NRM
1 999 0
0
1
DATA
1
1
DATA
1 199 3
1
DATA
200 209
3 0
DATA
210 999
3 1
DATA-APRX
1 999 3
0
DATA-CM
1 999 3
6
DATA-MIN
1 999 3
8
DATA-MAX
1 999 3
8
DATA-ERR
1 999 4
4
DATA-ERR1
1 999 4
4
DATA-ERR2
1 999 4
4
+DATA-ERR
1 999 4
4
-DATA-ERR
1 999 4
4
ERR-T
1 999 4
1
ERR-S
1 999 4
3
RATIO
200 209
3 1
RATIO-APRX 200
209 3
0
RATIO-ERR 200
209 4
0
RATIO
802 802
3 0
RATIO-APRX 802
802 3
0
RATIO-ERR 802
802 4
0
RATIO
1 999 0
0
RATIO-APRX
1 999 0
0
RATIO-ERR
1 999 0
0
1
ANGULAR VARIABLES
1
1
COS
4 999 5
0
COS-CM
4 999 5
6
ANG
4 999 5
0
ANG-CM
4 999 5
6
ANG-RSL
4 999 6
4
1
SECONDARY ENERGY
1
1
E
1 999 7 10
E2
E-CM
1 999 7 10
E2
E-LVL
1 999 7 10
LVL
E-EXC
1 999 7 10
EXC
E-EXC1
1 999 7 10
EXC
E-EXC2
1 999 7 10
EXC
E-EXC3
1 999 7 10
EXC
E1
1 999 7
0 DE2
E2
1 999 8
0
E-MIN
1 999 7
0 DE2
E-MAX
1 999 8
0 DE2
E1-MAX
1 999
7 0 DE2
E1-MIN
1 999 8
0 DE2
E-CM-MIN
1 999 7
0 DE2
E-CM-MAX
1 999 8
0 DE2
E-LVL-MIN
1 999 7
0 DE2
E-LVL-MAX
1 999 8
0 DE2
1
YIELD (USUALLY FISSION). OUTPUT ELEMENT IN FIELD 5,
MASS IN FIELD 6.
1
1
ELEMENT
3 3 5
1
ELEMENT
4 4 0
0
ELEMENT
801 802
5 1
ELEMENT
804 804
0 0
MASS
3 4 6
1
MASS
801 804
6 1
1
MISCELLANEOUS (USED)
1
1
MOMENTUM L
1 999 5
0
NUMBER
1 999 5
0
NUMBER-CM
1 999 5
6
HL1
1 999 7
0 HL
HL1-ERR
1 999 8
0
1
MISCELLANEOUS (IGNORED)
1
1
MONIT1
1 999 0
0
MONIT2
1 999 0
0
MONIT3
1 999 0
0
MONIT-ERR
1 999 0
0
ASSUM
1 999 0
0
ASSUM1
1 999 0
0
ASSUM2
1 999 0
0
MISC
1 999 0
0
MISC1
1 999
0 0
MISC2
1 999 0
0
MISC3
1 999 0
0
MISC4
1 999 0
0
MISC-ERR
1 999 0
0
MISC1-ERR
1 999 0
0
MONIT
1 999 0
0
MONIT1-ERR
1 999 0
0
MONIT2-ERR
1 999 0
0
ISOMER
1 999 0
0
DECAY-FLAG
1 999 0
0
FLAG
1 999 0
0
N-OUT
1 999 0
0
Units
Dictionary
EXFOR UNITS TO STANDARD UNIT CONVERSION TABLE
1
=============================================
1
COMMENT CARDS ARE DEFINED BY A 1 IN COLUMN 80
1
REACTION DEFINITIONS MUST HAVE A BLANK COLUMN 80
1
WARNING...FAILURE TO FOLLOW THIS CONVENTION WILL
RESULT IN ERRORS
1
1
FORMAT
1
======
1
COLUMNS DEFINITION
1
======= ==========
1
1- 11
EXFOR UNITS
1
12- 22
STANDARD UNITS
1
23- 33
MULTIPLIER
1
34- 44
ADDER
1
45- 55
OPERATION NUMBER (SEE, LIST BELOW FOR DEFINITIONS).
1
1
NOTE, EXFOR UNITS WILL BE CONVERTED TO STANDARD UNITS
BY MULTIPLYING
1
BY THE MULTIPLIER, ADDING THE ADDER AND THEN
PERFORMING AN OPERATION
1
(IF ANY OPERATION), E.G., TO CONVERT DEG-C TO DEG-K
MULTIPLY BY 1.0 AND
1
ADD 273.16, E.G., TO CONVERT ADEG TO COSINE MULTIPLY
BY 1.0 AND PERFORM
1
OPERATION 2 (ANGLE TO COSINE CONVERSION).
1
1
STANDARD UNITS
1
==============
1
THE USER MAY SPECIFY ANY SET OF DESIRED STANDARD
OUTPUT UNITS. THE
1
FOLLOWING TABLE HAS CONVERSION FACTORS FOR EXFOR UNITS
TO THE STANDARD
1
UNITS,
1
1
EV
- ENERGY
1
BARNS
- CROSS SECTION
1
STERADIANS -
SOLID ANGLE
1
SECONDS
- TIME
1
KELVIN
- TEMPERATURE
1
1
DEFINED OPERATIONS
1
==================
1
TO PERFORM ANY OF THE FOLLOWING OPERATIONS ON AN EXFOR
UNIT ENTER ONE
1
OF THE FOLLOWING NUMBERS IN COLUMN 55 (E.G., TO
PERFORM PER-CENT TO
1
ABSOLUTE CONVERSION THE EXFOR UNIT PER-CENT HAS A 1 IN
COLUMN 55).
1
1
(1) CONVERT PER-CENT TO ABSOLUTE
1
(2) CONVERT ANGLE TO COSINE (ANGLE OR ANGULAR ERROR).
1
(3) CONVERT RESOLUTION (E.G. NSEC/M TO ENERGY ERROR EV).
1
WARNING...THIS
CONVERSION ASSUMES MASS =1 PROJECTILES, E.G. N OR P. 1
(4) CONVERT ANGSTROM TO EV.
1
(5) CONVERT LENGTH TO BARNS (E.G., FERMI TO BARNS).
1
(6) BARNS*SQRT(E) TO BARNS (E.G., SOME RESONANCE
PARAMETERS).
1
(7) PRINT WARNING FOLLOWED BY UNITS (E.G.,
WARNING...UNITS=ABR-UNITS).
1
(8) PRINT WARNING FOLLOWED BY UNITS (E.G.,
WARNING...UNITS=ABR-UNITS),
1
AND
CHANGE STATUS TO UNNORMALIZED (U).
1
1
EXFOR
STANDARD
1
UNITS
UNITS
MULTIPLIER ADDER
OPERATION
1
1
ENERGY
1
1
MICRO-EV EV
1.00000- 6 0.0
0
MILLI-EV EV
1.00000- 3 0.0
0
EV
EV
1.0 0.0
0
KEV
EV
1.00000+ 3 0.0
0
MEV
EV
1.00000+ 6 0.0
0
GEV
EV
1.00000+ 9 0.0
0
TEV
EV
1.00000+12 0.0
0
1/MICRO-EV 1/EV
1.00000+ 6 0.0
0
1/MILLI-EV 1/EV
1.00000+ 3 0.0
0
1/EV
1/EV
1.0
0.0
0
1/KEV
1/EV
1.00000- 3 0.0
0
1/MEV
1/EV
1.00000- 6 0.0
0
1/GEV
1/EV
1.00000- 9 0.0
0
1/TEV
1/EV
1.00000-12 0.0
0
1
RESOLUTION
1
1
NSEC/M
EV
1.0 0.0
3
MICROSEC/M EV
1.00000+ 3 0.0
3
MSEC/M
EV
1.00000+ 6 0.0
3
ANGSTROM EV
1.0 0.0
4
1
CROSS SECTIONS
1
1
MICRO-B
B
1.00000- 6 0.0
0
MB
B
1.00000- 3 0.0
0
B
B
1.0 0.0
0
KB
B
1.00000+ 6 0.0
0
MB*RT-EV B
1.00000- 3 0.0
6
B*RT-EV
B
1.0 0.0
6
MB*MILLIEV B*EV
1.00000- 6 0.0
0
MB*EV
B*EV
1.00000- 3 0.0
0
B*MILLI-EV B*EV
1.00000- 3 0.0
0
B*EV
B*EV
1.0
0.0
0
MB*EV-SQ B*EV-SQ
1.00000- 3 0.0
0
B*EV-SQ
B*EV-SQ 1.0
0.0
0
B*EV*RT-EV B*EV*RT-EV
1.0
0.0
0
1
LENGTH
1
1
FERMI
B
1.00000- 1 0.0
5
MM
B
1.00000+11 0.0
5
CM
B
1.00000+12 0.0
5
M
B
1.00000+14 0.0
5
1
ANGLES
1
1
ASEC
NO-DIM 2.77777-
4 0.0
2
AMIN
NO-DIM 1.66666-
2 0.0
2
ADEG
NO-DIM 1.0
0.0
2
1
ANGULAR DISTRIBUTIONS
1
1
MU-B/SR
B/SR
1.00000- 6 0.0
0
MB/SR
B/SR
1.00000- 3 0.0
0
B/SR
B/SR
1.0
0.0 0
1/SR
1/SR
1.0
0.0
0
1
ENERGY DISTRIBUTIONS
1
1
MU-B/MEV B/EV
1.0
0.0
0
MB/EV
B/EV
1.00000- 3 0.0
0
MB/KEV
B/EV
1.00000- 6 0.0
0
MB/MEV
B/EV
1.00000- 9 0.0
0
B/MILLI-EV B/EV
1.00000+ 3 0.0
0
B/EV
B/EV
1.0
0.0
0
B/KEV
B/EV
1.00000- 3 0.0
0
B/MEV
B/EV
1.00000- 6 0.0
0
1
DOUBLE DIFFERENTIAL DISTRIBUTIONS
1
1
MUB/SR/MEV B/SR/EV
1.00000-12 0.0
0
MB/SR/EV B/SR/EV
1.00000- 3 0.0
0
MB/SR/KEV B/SR/EV
1.00000- 6 0.0
0
MB/SR/MEV B/SR/EV
1.00000- 9 0.0
0
MB/SR/GEV B/SR/EV
1.00000-12 0.0
0
B/SR/MI-EV B/SR/EV
1.00000+ 3 0.0
0
B/SR/EV
B/SR/EV 1.0
0.0
0
B/SR/KEV B/SR/EV
1.00000- 3 0.0
0
B/SR/MEV B/SR/EV
1.00000- 6 0.0
0
B/SR/GEV B/SR/EV
1.00000- 9 0.0
0
1
TRIPLE DIFFERENTIAL DISTRIBUTIONS
1
1
MB/SR/MEV2 B/SR/EV2
1.00000-15 0.0
0
1
TEMPERATURE
1
1
DEG-K
DEG-K
1.0
0.0
0
DEG-C
DEG-K
1.0
273.16
0
DEG-F
DEG-K
0.555556 255.382 0
1
TIME
1
1
PSEC
SEC
1.00000-12 0.0
0
NSEC
SEC
1.00000- 9 0.0
0
MICROSEC SEC
1.00000- 6 0.0
0
MSEC
SEC
1.00000- 3 0.0
0
SEC
SEC
1.0
0.0
0
MIN
SEC
6.00000+ 1 0.0
0
HR
SEC
3.60000+ 2 0.0
0
D
SEC
8.64000+ 3 0.0
0
Y
SEC
3.15576+ 6 0.0
0
YR
SEC
3.15576+ 6 0.0
0
1/PSEC
1/SEC
1.00000+12 0.0
0
1/NSEC
1/SEC
1.00000+ 9 0.0
0
1/MICROSEC 1/SEC
1.00000+ 6 0.0
0
1/MSEC
1/SEC
1.00000+ 3 0.0
0
1/SEC
1/SEC
1.0 0.0
0
1/MIN
1/SEC
1.66666- 2 0.0
0
1/HR
1/SEC
2.77777- 3 0.0
0
1/D
1/SEC
1.15741- 4 0.0
0
1/Y
1/SEC
3.16881- 7 0.0
0
1/YR
1/SEC
3.16881- 7 0.0
0
1
MISCELLANEOUS
1
1
PER-CENT (VARIOUS)
1.0
0.0
1
NO-DIM
NO-DIM 1.0
0.0
0
GAM/100N GAM/100N
1.00000- 2 0.0
7
GAM/PART GAM/PART
1.0
0.0 7
PC/FIS
PC/FIS 1.00000-
2 0.0
7
ARB-UNITS ARB-UNITS
1.0
0.0
8
SEE TEXT SEE
TEXT 1.0 0.0
7
MUCI/MUA MUCI/MUA
1.0
0.0
7
MUCI/MUAHR MUCI/MUAHR
1.0
0.0
7
Example
Output Report
TRANSLATE
DATA FROM EXFOR TO COMPUTATION FORMAT (X4TOC4 VERSION 86-1)
======================================================================
READING
TRANSLATION TABLES
======================================================================
REACTIONS------------
100 ( 400 ALLOWED)
TITLES---------------
90 ( 400 ALLOWED)
UNITS----------------
93 ( 400 ALLOWED)
======================================================================
AN SAN PROJECT TARGET RESIDUAL MF
MT REACTION
======================================================================
10529
3 1
14028 14028
3 4
(N,INL),SIG
11274
11 1
14028 13028
3 103
(N,P),SIG
OPERATION...CONVERTED PER-CENT TO ABSOLUTE
11464
4 1
14028 13028
3 103
(N,P),SIG
20498
2 1
14028 14028
4 2
(N,EL),DA
OPERATION...CENTER-OF-MASS SYSTEM FLAG SET
OPERATION...CONVERTED ANGULAR ERROR TO COSINE ERROR
21984
119 1
14028 14028
4 2 (N,EL),DA
OPERATION...CENTER-OF-MASS SYSTEM FLAG SET
OPERATION...CENTER-OF-MASS SYSTEM FLAG SET
OPERATION...CONVERTED ANGLES TO COSINES
31097
3 1
14028 13028
3 103
(N,P),SIG
======================================================================
TRANSLATION
SUMMARY
======================================================================
SUBENTRIES
TRANSLATED--------
6
SUBENTRIES
SKIPPED-----------
0 (NO OUTPUT)
POINTS
READ------------------ 318
POINTS
TRANSLATED------------ 318
DATA
FIELDS NOT DEFINED------
0 (NO OUTPUT)
DATA
FIELDS BLANK------------
0 (NO OUTPUT)
UNDEFINED
REACTIONS----------
0
UNDEFINED
TITLES-------------
0
UNDEFINED
UNITS--------------
0
======================================================================
Example
EXFOR format data
REQUEST
1001 20010326
3 095246
0 0
0
ENTRY
10529 830901
10529000 1
SUBENT
10529001 830901
10529001 1
BIB
13 21
10529001 2
INSTITUTE
(1USAORL)
10529001 3
REFERENCE
(C,71KNOX,1,191,7103)
10529001 4
AUTHOR
(F.G.PEREY,W.E.KINNEY,R.L.MACKLIN)
10529001 5
TITLE
HIGH RESOLUTION INELASTIC CROSS SECTION MEASUREMENTS
10529001 6
FOR NA,SI,AND FE.
10529001 7
FACILITY
(LINAC) OAK RIDGE ELECTRON LINEAR ACCELERATOR
10529001 8
N-SOURCE
(PHOTO) PHOTONEUTRONS
10529001 9
METHOD
(TOF) TIME-OF-FLIGHT
10529001 10
DETECTOR
(SCIN) CARBON-FLUORIDE LIQUID SCINTILLATOR
10529001 11
CORRECTION
DATA CORRECTED FOR BACKGROUND COUNTS.
10529001 12
MONITOR
(3-LI-7(N,INL)3-LI-7,PAR,SIG)
10529001 13
KNOWN LITHIUM-7 CROSS SECTION AT
10529001 14
THE 478 KEV LEVEL IN BNL-325,1964,2ND ED.,USED TO
10529001 15
DETERMINE NEUTRON FLUX SHAPE.
10529001 16
ERR-ANALYS
CROSS SECTION NORMALIZED TO PREVIOUS ABSOLUTE 10529001
17
MEASUREMENT. ESTIMATED UNCERTAINTY IS APPROX.
10529001 18
15. PER-CENT
10529001 19
STATUS
(APRVD) APPROVED BY AUTHOR 751017
10529001 20
DATA TAKEN FROM PRIVATE COMM., PEREY, 75/8.
10529001 21
HISTORY
(750804C)
10529001
22
(830901A) CONVERTED TO REACTION FORMALISM
10529001 23
ENDBIB
21
10529001 24
NOCOMMON
0 0
10529001 25
ENDSUBENT
24
1052900199999
SUBENT
10529003 830901
10529003 1
BIB
1 1
10529003 2
REACTION
(14-SI-28(N,INL)14-SI-28,,SIG)
10529003 3
ENDBIB
1
10529003 4
NOCOMMON
0 0
10529003 5
DATA
3 258
10529003 6
EN
DATA DATA-ERR
10529003 7
KEV
MB MB
10529003 8
1772.2
-9.6 10.5
10529003
9
1781.1
1.4 10.9
10529003 10
1785.0
-2.8 10.8
10529003 11
1788.9
-2.2 10.9
10529003
12
1792.9
-4.1 10.9
10529003 13
1796.8
-6.6 10.9
10529003 14
1800.7
11.7 11.5
10529003 15
1804.6
22.0 11.8
10529003 16
1808.5
14.0 11.6
10529003 17
1812.5
7.8 11.5
10529003 18
1816.4
31.7 12.3
10529003 19
1820.3
24.9 12.1
10529003 20
1824.2
37.6 12.6
10529003 21
1828.1
31.5 12.5
10529003 22
1832.0
60.5 13.3
10529003 23
1836.0
74.8 13.8
10529003 24
1839.9
102.1 14.6
10529003
25
1843.8
148.4 15.8
10529003 26
1847.7
219.3 17.5
10529003 27
1851.6
384.8 20.8
10529003
28
1855.5
455.7 22.2
10529003 29
1859.5
436.9 22.0
10529003 30
1863.4
397.3 21.5
10529003 31
1867.3
287.9 19.5
10529003 32
1871.2
218.8 18.2
10529003 33
1875.1
190.6 17.8
10529003 34
1879.0
168.7 17.4
10529003 35
1883.0
149.1 17.0
10529003 36
1886.9
151.1 17.2
10529003 37
1890.8
99.1 16.0
10529003 38
1894.7
103.5 16.2
10529003 39
1898.6
78.3 15.7
10529003 40
1902.5
92.7 16.2
10529003
41
1906.5
155.6 17.9
10529003 42
1910.4
203.3 19.2
10529003 43
1914.3
259.5 20.6
10529003
44
1918.2
329.8 22.2
10529003 45
1922.1
366.6 23.1
10529003 46
1926.0
331.4 22.5
10529003 47
1930.0
309.7 22.2
10529003 48
1933.9
279.3 21.6
10529003 49
1937.8
242.0 20.9
10529003 50
1941.7
200.3 20.0
10529003 51
1945.6
200.5 20.1
10529003 52
1949.5
158.8 19.2
10529003 53
1953.5
210.0 20.6
10529003 54
1957.4
203.7 20.5
10529003 55
1961.3
193.3 20.4
10529003 56
1965.2
183.1 20.2
10529003
57
1969.1
188.7 20.5
10529003 58
1973.0
192.6 20.7
10529003 59
1974.0
175.1 16.5
10529003
60
1979.9
142.0 15.8
10529003 61
1985.7
123.4 15.5
10529003 62
1991.6
105.6 15.1
10529003 63
1997.5
91.7 14.8
10529003 64
2003.4
117.0 15.4
10529003 65
2009.2
96.1 14.9
10529003 66
2015.1
106.8 15.2
10529003 67
2021.0
77.8 14.5
10529003 68
2026.8
83.5 14.7
10529003 69
2032.7
96.3 15.0
10529003 70
2038.6
137.5 16.0
10529003 71
2044.5
138.4 16.0
10529003 72
2050.3
173.9 16.8
10529003
73
2056.2
247.5 18.3
10529003 74
2062.1
341.0 20.1
10529003 75
2067.9
329.8 19.9
10529003
76
2073.8
293.1 19.2
10529003 77
2079.7
317.0 19.6
10529003 78
2085.5
403.3 21.1
10529003 79
2091.4
408.0 21.2
10529003 80
2097.3
377.9 20.7
10529003 81
2103.1
232.9 18.0
10529003 82
2109.0
168.7 16.8
10529003 83
2114.9
215.8 17.7
10529003 84
2120.7
348.2 20.1
10529003 85
2126.6
266.8 18.6
10529003 86
2132.5
158.8 16.5
10529003 87
2138.3
104.2 15.3
10529003 88
2144.2
103.3 15.2
10529003
89
2150.1
110.9 15.4
10529003 90
2155.9
116.9 15.5
10529003 91
2161.8
124.0 15.6
10529003
92
2167.7
151.2 16.2
10529003 93
2173.5
167.2 16.5
10529003 94
2179.4
207.8 17.3
10529003 95
2185.3
234.9 17.8
10529003 96
2191.1
193.4 17.1
10529003 97
2197.0
216.6 17.5
10529003 98
2202.9
212.8 17.4
10529003 99
2208.7
214.5 17.5
10529003 100
2214.6
257.0 18.3
10529003 101
2220.5
357.8 20.1
10529003 102
2226.3
517.3 22.6
10529003 103
2232.2
518.0 22.7
10529003 104
2238.1
415.6 21.2
10529003
105
2243.9
243.2 18.3
10529003 106
2249.8
193.2 17.5
10529003 107
2255.6
204.3 17.7
10529003
108
2261.5
280.2 19.2
10529003 109
2267.4
354.8 20.5
10529003 110
2273.2
551.6 23.6
10529003 111
2279.1
708.0 25.7
10529003 112
2285.0
768.6 26.5
10529003 113
2290.8
604.1 24.2
10529003 114
2296.7
436.2 21.7
10529003 115
2302.5
294.0 19.4
10529003 116
2308.4
251.5 18.6
10529003 117
2314.3
226.1 18.1
10529003 118
2320.1
224.4 18.1
10529003 119
2326.0
206.2 17.8
10529003 120
2331.8
226.0 18.2
10529003
121
2337.7
213.0 18.0
10529003 122
2343.6
279.5 19.2
10529003 123
2349.4
309.2 19.8
10529003
124
2355.3
337.4 20.3
10529003 125
2361.1
395.2 21.3
10529003 126
2367.0
443.3 22.1
10529003 127
2372.9
492.7 22.9
10529003 128
2378.7
499.8 23.0
10529003 129
2384.6
390.1 21.4
10529003 130
2390.4
331.6 20.5
10529003 131
2396.3
295.5 19.9
10529003 132
2402.2
305.6 20.1
10529003 133
2408.0
315.0 20.3
10529003 134
2413.9
330.4 20.7
10529003 135
2419.7
336.4 20.8
10529003 136
2425.6
338.5 20.9
10529003
137
2431.5
386.5 21.8
10529003 138
2437.3
438.5 22.7
10529003 139
2443.2
497.0 23.6
10529003
140
2449.0
544.2 24.4
10529003 141
2454.9
523.3 24.1
10529003 142
2460.7
481.9 23.6
10529003 143
2463.7
408.5 19.4
10529003 144
2471.5
340.3 18.5
10529003 145
2479.3
369.6 19.1
10529003 146
2487.1
471.1 20.6
10529003 147
2494.9
489.1 20.9
10529003 148
2502.7
497.1 21.2
10529003 149
2510.5
410.9 20.1
10529003 150
2518.3
272.9 18.1
10529003 151
2526.1
238.2 17.7
10529003 152
2533.9
207.3 17.3
10529003
153
2541.7
239.1 18.0
10529003 154
2549.5
260.6 18.5
10529003 155
2557.4
268.7 18.8
10529003
156
2565.2
279.3 19.1
10529003 157
2573.0
282.5 19.3
10529003 158
2580.8
253.1 18.9
10529003 159
2588.6
252.0 19.0
10529003 160
2596.4
266.4 19.4
10529003 161
2604.2
279.9 19.8
10529003 162
2612.0
228.1 19.1
10529003 163
2619.8
166.5 18.1
10529003 164
2627.6
210.1 19.1
10529003 165
2635.4
171.0 18.6
10529003 166
2643.2
214.9 19.6
10529003 167
2651.0
216.4 19.8
10529003 168
2658.8
286.2 21.2
10529003
169
2666.6
262.8 21.1
10529003 170
2674.4
218.1 20.5
10529003 171
2682.2
278.2 21.9
10529003
172
2690.0
264.6 21.9
10529003 173
2697.8
331.5 23.4
10529003 174
2705.6
283.4 22.8
10529003 175
2713.4
283.0 23.1
10529003 176
2721.2
254.2 22.9
10529003 177
2729.0
280.5 23.6
10529003 178
2736.8
326.5 24.7
10529003 179
2744.6
272.1 24.1
10529003 180
2752.4
283.2 24.6
10529003 181
2760.2
266.7 24.7
10529003 182
2768.0
298.8 25.7
10529003 183
2775.8
335.8 26.8
10529003 184
2783.6
376.3 27.9
10529003
185
2791.4
352.2 28.0
10529003 186
2799.2
367.6 28.7
10529003 187
2807.0
343.4 28.7
10529003
188
2814.8
392.0 29.8
10529003 189
2822.6
409.4 30.4
10529003 190
2830.4
523.7 32.7
10529003 191
2838.2
639.4 34.9
10529003 192
2846.0
843.9 38.3
10529003 193
2853.7
824.3 38.3
10529003 194
2861.5
951.8 40.4
10529003 195
2869.3
896.2 39.8
10529003 196
2877.1
752.0 37.9
10529003 197
2884.9
538.1 34.6
10529003 198
2892.7
359.1 31.5
10529003 199
2900.5
335.9 31.3
10529003 200
2908.3
242.0 29.5
10529003
201
2916.1
331.7 31.3
10529003 202
2923.9
308.4 31.0
10529003 203
2931.7
411.8 33.0
10529003
204
2939.5
494.9 34.6
10529003 205
2947.3
381.7 32.6
10529003 206
2952.1
274.2 27.3
10529003 207
2961.9
220.0 26.3
10529003 208
2971.6
199.1 25.9
10529003 209
2981.3
189.2 25.7
10529003 210
2991.1
254.2 26.9
10529003 211
3000.8
283.4 27.3
10529003 212
3010.6
324.9 27.8
10529003 213
3020.3
350.4 28.0
10529003 214
3030.0
286.5 26.6
10529003 215
3039.8
349.7 27.4
10529003 216
3049.5
433.6 28.7
10529003
217
3059.2
548.4 30.4
10529003 218
3069.0
545.6 30.3
10529003 219
3078.7
416.4 28.2
10529003
220
3088.4
367.3 27.4
10529003 221
3098.2
539.1 30.1
10529003 222
3107.9
751.5 33.1
10529003 223
3117.6
762.3 33.3
10529003 224
3127.4
683.9 32.3
10529003 225
3137.1
634.8 31.6
10529003 226
3146.8
675.1 32.3
10529003 227
3156.5
581.9 31.1
10529003 228
3166.3
433.8 29.1
10529003 229
3176.0
483.9 30.0
10529003 230
3185.7
394.3 28.8
10529003 231
3195.5
442.8 29.8
10529003 232
3205.2
417.0 29.8
10529003
233
3214.9
486.3 31.1
10529003 234
3224.6
685.3 34.3
10529003 235
3234.4
882.0 37.2
10529003
236
3244.1
866.3 37.4
10529003 237
3253.8
771.2 36.4
10529003 238
3263.5
615.9 34.5
10529003 239
3273.3
567.2 34.1
10529003 240
3283.0
627.9 35.2
10529003 241
3292.7
640.4 35.6
10529003 242
3302.4
602.6 35.3
10529003 243
3312.2
543.4 34.7
10529003 244
3321.9
486.5 34.1
10529003 245
3331.6
521.6 34.9
10529003 246
3341.3
557.0 35.7
10529003 247
3351.1
569.6 36.0
10529003 248
3360.8
577.1 36.3
10529003
249
3370.5
542.5 36.0
10529003 250
3380.2
558.8 36.5
10529003 251
3389.9
472.5 35.3
10529003
252
3399.7
495.8 35.8
10529003 253
3409.4
449.8 35.3
10529003 254
3419.1
526.8 36.7
10529003 255
3428.8
561.8 37.4
10529003 256
3438.5
473.5 36.1
10529003 257
3448.2
363.8 34.3
10529003 258
3458.0
284.3 32.9
10529003 259
3467.7
303.4 33.2
10529003 260
3477.4
281.3 32.9
10529003 261
3487.1
234.1 32.1
10529003 262
3496.8
219.3 31.9
10529003 263
3506.5
260.2 32.9
10529003 264
3516.3
407.6 35.7
10529003
265
3526.0
433.7 36.3
10529003 266
ENDDATA
260
10529003 267
ENDSUBENT
266
1052900399999
ENDENTRY
2
1052999999999
ENTRY
11274 860318
11274000 1
SUBENT
11274001 860318
11274001 1
BIB
10 15
11274001 2
INSTITUTE
(1CANCRC)
11274001 3
REFERENCE
(J,CJP,31,267,53)
11274001 4
AUTHOR
(E.B.PAUL,R.L.CLARKE)
11274001 5
TITLE
CROSS SECTION MEASUREMENTS OF REACTIONS INDUCED BY
11274001 6
NEUTRONS OF THE 14.5 MEV ENERGY.
11274001 7
INC-SOURCE
(D-T) 11274001
8
MONITOR
NEUTRON FLUX MONITORED BY A LONG BORON COUNTER.
11274001 9
BETA COUNTERS CALIBRATED WITH STANDARD SOURCES.
11274001 10
METHOD
(ACTIV).
11274001 11
HALF-LIFE
HALF LIVES TAKEN FROM N.B.C. CIRCULAR 499(1952)
11274001 12
STATUS
(SCSRS)
11274001 13
HISTORY
(761001T) TRANSLATED FROM SCISRS
11274001
14
(810428A) CONVERTED TO REACTION FORMALISM
11274001 15
(820108U) BIB CORRECTIONS
11274001 16
(860318A) BIB CORRECTION.
11274001 17
ENDBIB
15
11274001 18
NOCOMMON
0 0
11274001 19
ENDSUBENT
18
1127400199999
SUBENT
11274011 810428
11274011 1
BIB
2 2
11274011 2
REACTION
(14-SI-28(N,P)13-AL-28,,SIG)
11274011 3
DECAY-DATA
(13-AL-28,2.4MIN,B)
11274011 4
ENDBIB
2
11274011 5
NOCOMMON
0 0
11274011 6
DATA
3 1
11274011
7
EN
DATA DATA-ERR
11274011 8
MEV
B PER-CENT
11274011 9
1.45
+01 2.20 -01
23.
11274011
10
ENDDATA
3
11274011 11
ENDSUBENT
10
1127401199999
ENDENTRY
2
1127499999999
ENTRY
11464 820813
11464000 1
SUBENT
11464001 820813
11464001 1
BIB
9 11
11464001 2
INSTITUTE
(1USANRD)
11464001 3
REFERENCE
(J,NP,10,226,5905)
11464001 4
(R,USNRDL-TR-269,5810) TABULATED DATA
11464001 5
AUTHOR
(B.D.KERN,W.E.THOMPSON,J.M.FERGUSON)
11464001 6
TITLE
CROSS SECTIONS FOR SOME (N,P) AND (N,ALPHA) REACTIONS. 11464001
7
N-SOURCE
(D-T) D(T,N) SOURCE
11464001 8
METHOD
(ACTIV)
11464001 9
MONITOR
(3-LI-6(N,T)2-HE-4,,SIG)
11464001 10
STATUS
(SCSRS)
11464001 11
HISTORY
(761016T) TRANSLATED FROM SCISRS
11464001
12
(820813A) CONVERTED TO REACTION FORMALISM
11464001 13
ENDBIB
11
11464001 14
NOCOMMON
0 0
11464001 15
ENDSUBENT
14
1146400199999
SUBENT
11464004 820813
11464004 1
BIB
1 1
11464004 2
REACTION
(14-SI-28(N,P)13-AL-28,,SIG)
11464004 3
ENDBIB
1
11464004 4
NOCOMMON
0 0
11464004 5
DATA
3 33
11464004 6
EN
DATA DATA-ERR
11464004 7
MEV
B B
11464004 8
1.233
+01 3.77 -01 4.52
-02 11464004 9
1.299
+01 3.577 -01 4.3
-02
11464004 10
1.30
+01 3.401 -01 4.08
-02
11464004 11
1.31
+01 4.480 -01 6.3
-02
11464004
12
1.338
+01 3.896 -01 4.3
-02
11464004 13
1.35
+01 3.816 -01 4.5
-02
11464004 14
1.359
+01 3.888 -01 4.67
-02
11464004 15
1.373
+01 3.485 -01 3.5
-02
11464004 16
1.373
+01 3.264 -01 3.3
-02
11464004 17
1.384
+01 4.150 -01 4.6
-02
11464004 18
1.401
+01 4.413 -01 5.3
-02
11464004 19
1.428
+01 3.505 -01 3.9
-02
11464004 20
1.428
+01 3.766 -01 4.7
-02
11464004 21
1.474
+01 3.403 -01 3.7
-02
11464004 22
1.499
+01 3.062 -01 4.00
-02
11464004 23
1.499
+01 3.446 -01 4.50
-02
11464004 24
1.499
+01 2.601 -01 3.1
-02 11464004 25
1.506
+01 3.010 -01 3.3
-02
11464004 26
1.544
+01 2.985 -01 3.3
-02
11464004 27
1.566
+01 3.160 -01 3.5
-02
11464004
28
1.599
+01 2.332 -01 2.8
-02
11464004 29
1.599
+01 2.606 -01 3.1
-02
11464004 30
1.621
+01 2.312 -01 2.5
-02
11464004 31
1.632
+01 2.926 -01 4.1
-02
11464004 32
1.668
+01 2.684 -01 3.2
-02
11464004 33
1.698
+01 2.111 -01 2.5
-02
11464004 34
1.698
+01 2.148 -01 2.6
-02
11464004 35
1.704
+01 2.542 -01 3.6
-02
11464004 36
1.712
+01 2.824 -01 3.6
-02
11464004 37
1.75
+01 2.330 -01 3.5
-02
11464004 38
1.75
+01 1.887 -01 2.6
-02
11464004 39
1.752
+01 2.098 -01 2.4
-02
11464004 40
1.824
+01 1.584 -01 2.5
-02 11464004 41
ENDDATA
35
11464004 42
ENDSUBENT
41
1146400499999
ENDENTRY
2
1146499999999
ENTRY
20498 840120
20498000 1
SUBENT
20498001 840120
20498001 1
BIB
16 42
20498001 2
INSTITUTE
(2ITYTUR)
20498001 3
REFERENCE
(J,NCL,8,249,7309)
20498001 4
(C,72BUD,,134,7208) ALSO C-12 AND O-16.
20498001 5
(J,NIM,87,291,7010) WITH DETAILS
ON EXPERIMENTAL
20498001 6
TECHNIQUES.
20498001 7
AUTHOR
(B.MINETTI, A.PASQARELLI, G.C.BONAZZOLA, T.BRESSANI,
20498001 8
E.CHIAVASSA)
20498001 9
TITLE
-ELASTIC AND INELASTIC BACKSCATTERING OF 14.2 MEV
20498001 10
NEUTRONS FROM SI-28.-
20498001 11
FACILITY
(CCW )
14 MEV ELECTRO-STATIC GENERATOR AT ISTITUTO 20498001
12
DI FISICA SPERIMENTALE DEL POLITECNICO, TURIN.
20498001 13
INC-SOURCE
(D-T ) DEUTERON-TRITIUM.
20498001 14
SAMPLE
NATURAL POWDERED SI (92.2 PERC. SI-28, 4.7 PERC. SI-2920498001
15
AND 3.1 PERC. SI-30).
20498001 16
SAMPLE WAS CONTAINED IN A PARALLELEPIPED, 70 * 70 * 4 20498001
17
CM3, COMPOSED OF AN ALUMINUM FRAME WITH 2 POLYETYLENE 20498001
18
WINDOWS STRENGTHENED BY A THIN ALUMINUM MESH.
20498001 19
METHOD
(TOF )
TIME OF FLIGHT, PATH = 220 CM. SEE
20498001 20
NUCL.INSTR.METH.,87(1970)291.
20498001 21
DETECTOR
(SCIN ) NE 213
LIQUID SCINTILLATOR, CONTAINED IN A 20498001 22
CYLINDRICAL BOX OF 9 CM DIAM. AND 10 CM LENGTH, WITH
20498001 23
A XP 1021 PHOTOMULTIPLIER.
20498001 24
ANALYSIS
- THE WHOLE ANGULAR DISTRIBUTION FOR ELASTIC SCATT.
20498001 25
WAS FIRST ANALYSED WITH A SPHERICAL OPTICAL
20498001 26
POTENTIAL.
20498001 27
- THE ANGULAR DISTRIBUTIONS BOTH FOR ELASTIC AND
20498001 28
INELASTIC SCATT. TO 1.77 MEV LEVEL WAS AFTERWARDS
20498001 29
ANALYSED WITH THE COUPLED-CHANNEL METHOD, IN THE
20498001 30
ADIABATIC APPROXIMATION.
20498001
31
MONITOR
ABSOLUTE MEASUREMENT. THE NEUTRON FLUX DISTRIBUTION
20498001 32
ON THE SCATTERER PLANE WAS MEASURED BY SCANNING ITS
20498001 33
SURFACE IN STEPS OF 5 CM WITH A PLASTIC SCINTILLATOR
20498001 34
WHOSE EFFICIENCY WAS MEASURED WITH 1 PERCENT ERROR
20498001 35
PART-DET
(N )
NEUTRONS.
20498001 36
STATUS
DATA FROM TABLE I OF LETT.NUOVO CIMENTO,8(1973)249.
20498001 37
HISTORY
(731031C)
20498001 38
(760315E)
20498001 39
CORRECTION
DOUBLE SCATTERING CORRECTIONS, 12 PERC. FOR ELASTIC
20498001 40
SCATTERING AND 17 PERC. FOR INELASTIC ONE, WERE
20498001 41
CALCULATED WITH MONTE-CARLO METHOD.
20498001 42
ERR-ANALYS
ERRORS ARE STATISTICAL.
20498001 43
ANGULAR RESOLUTION IS +-1.5 DEG. FWHM.
20498001 44
ENDBIB
42
20498001 45
COMMON
1 3
20498001 46
EN
20498001
47
MEV
20498001 48
1.4200E+01
20498001 49
ENDCOMMON
3
20498001 50
ENDSUBENT
49
2049800199999
SUBENT
20498002 840120
20498002 1
BIB
2 3
20498002 2
REACTION
(14-SI-28(N,EL)14-SI-28,,DA)
20498002 3
HISTORY
(731031C)
20498002 4
(760315E)
20498002 5
ENDBIB
3
20498002 6
NOCOMMON
0 0
20498002 7
DATA
4 8
20498002 8
COS-CM
ANG-RSL DATA
DATA-ERR
20498002 9
NO-DIM
ADEG MB/SR
MB/SR
20498002 10
-9.9945E-01
7.5000E-01 1.3000E+01 1.0000E+00
20498002 11
-9.9415E-01
7.5000E-01 1.1000E+01 9.0000E-01
20498002
12
-9.9189E-01
7.5000E-01 1.1000E+01 8.0000E-01
20498002 13
-9.6901E-01
7.5000E-01 1.1100E+01 9.0000E-01
20498002 14
-9.4551E-01
7.5000E-01 9.7000E+00 8.0000E-01
20498002 15
-9.0850E-01
7.5000E-01 8.4000E+00 8.0000E-01
20498002 16
-8.7964E-01
7.5000E-01 6.8000E+00 6.0000E-01
20498002 17
-8.3771E-01
7.5000E-01 6.7000E+00 6.0000E-01
20498002 18
ENDDATA
10
20498002 19
ENDSUBENT
18
2049800299999
ENDENTRY
2
2049899999999
ENTRY
21984 970922
21984000 1
SUBENT
21984001 970922
21984001 1
BIB
15 43
21984001 2
INSTITUTE
(2JPNTOH)
21984001 3
REFERENCE
(C,85SANTA,1,223,8505)
21984001 4
(W,CHIBA,851001) DATA RECEIVED ON TAPE.
21984001 5
AUTHOR
(M.BABA,M.ONO,N.YABUTA,T.KIKUTI,N.HIRAKAWA) 21984001
6
TITLE
-SCATTERING OF 14.1MEV NEUTRONS FROM B-10,B-11,C,N,O,F 21984001
7
AND SI-.
21984001 8
FACILITY
(DYNAM) DYNAMITRON
21984001 9
INC-SOURCE
(D-T ) THE T(D,N) REACTION USING
A SOLID TI-T TARGET 21984001
10
90 AND 0 DEGREES FOR 14.2 AND
18.2 MEV MEASUREMENT 21984001
11
RESPECTIVELY. A SMALL NE213 SCINTILLATOR MONITORED THE21984001
12
SOURCE NEUTRONS FOR FLUX
NORMALISATION.
21984001 13
SAMPLE
.THE SCATTERING SAMPLES WERE CYLINDERS OF 10-B(4)C (90 21984001
14
PERCENT 10-B), BORON, CARBON, SI(3)N(4), SIO(2), CF(2)21984001
15
AND SI, 2.5 OR 3.5 CM IN DIAMETER AND 4 CM LONG. THE
21984001 16
SAMPLES OTHER THAN CARBON AND CF(2) WERE INCASED IN
21984001 17
THIN-WALLED ALUMINUM CANS.
21984001 18
METHOD
(TOF ) TIME OF FLIGHT
TECHNIQUES.
21984001 19
DETECTOR
(SCIN ) A WELL SHIELDED NE213 LIQUID SCINTILLATOR OF
21984001 20
5 INCH DIAMETER AND 2 INCH THICK, INCORPORATING TWO
21984001 21
SEPARATE NEUTRON-GAMMA DISCRIMINATORS WITH 0.3 AND
21984001 22
2 MEV BAIS RESPECTIVELY. THE EFFICIENCY WAS DETERMINED21984001
23
TO +- 4 PERCENT BY COMBINING THE CALCULATION AND THE
21984001 24
MEASUREMENT OF FISSION SPECTRUM FROM CF-252 AND OF
21984001 25
N-P SCATTERING.
21984001 26
PART-DET
(N ) NEUTRONS
21984001 27
MONITOR
(1-H-1(N,EL)1-H-1,,SIG) NO VALUES GIVEN IN CONFERENCE
21984001 28
PAPER.
21984001 29
CORRECTION
.FOR SAMPLE-OUT BACKGROUND, SAMPLE-SIZE EFFECT ( MONTE-21984001
30
CARLO SIMULATION TAKING THE FINITE TARGET-SAMPLE
21984001 31
GEOMETRY INTO ACCOUNT), AND FOR BACKGROUND DUE TO
21984001 32
PARASITIC D-D NEUTRONS.
21984001 33
ERR-ANALYS
(DATA-ERR) STANDARD DEVIATION
21984001 34
STATUS
.DATA TAKEN FROM PRIVATE COMMUNICATION.
21984001 35
HISTORY
(860128C)
21984001 36
(860210E)
21984001 37
(880802A) SUBENTRIES 32-41 DELETED
21984001
38
(880810E)
21984001 39
(910103A) S.W. MAIN REFERENCE IMPROVED. 14 MEV DATA FOR21984001
40
C-12 AND O-16 DELETED.
21984001 41
(910103E)
21984001 42
(970922A) * * CORRECTED BY S.MAEV
21984001 43
PART OF SUPERSEDED DATA FOR C-12 AND O-16
21984001 44
HAVE
BEEN RESTORED * *
21984001 45
ENDBIB
43
21984001 46
NOCOMMON
0 0
21984001 47
ENDSUBENT
46
2198400199999
SUBENT
21984119 970922
21984119 1
BIB
3 5
21984119 2
REACTION
(14-SI-28(N,EL)14-SI-28,,DA)
21984119 3
STATUS
.DATA TAKEN FROM PRIVATE COMMUNICATION.
21984119 4
HISTORY
(860128C)
21984119 5
(860210E)
21984119
6
(970922U) CHECKED
21984119 7
ENDBIB
5
21984119 8
COMMON
1 3
21984119 9
EN
21984119 10
MEV
21984119 11
1.4200E+01
21984119 12
ENDCOMMON
3
21984119 13
DATA
3 10
21984119 14
ANG-CM
DATA-CM DATA-ERR
21984119 15
ADEG
B/SR B/SR
21984119 16
2.5900E+01
2.4720E-01 3.9800E-02
21984119 17
3.1000E+01
1.1800E-01 1.3500E-02
21984119 18
4.6400E+01
1.8700E-02 2.1000E-03 21984119 19
6.1800E+01
3.9300E-02 3.6000E-03
21984119 20
7.7000E+01
2.1000E-02 4.1000E-03
21984119 21
8.2000E+01
1.3100E-02 2.0000E-03
21984119
22
1.0700E+02
1.0500E-02 1.7000E-03
21984119 23
1.2180E+02
9.5700E-03 1.0300E-03
21984119 24
1.3640E+02
6.7700E-03 7.6000E-04
21984119 25
1.5100E+02
5.3100E-03 6.0000E-04
21984119 26
ENDDATA
12
21984119 27
ENDSUBENT
26
2198411999999
ENDENTRY
2
2198499999999
ENTRY
31097 851217
31097000 1
SUBENT
31097001 851217
31097001 1
BIB
5 5
31097001 2
INSTITUTE
(3ISLISL)
31097001 3
REFERENCE
(J,NIM,21,197,63)
31097001 4
AUTHOR
(M.BIRK,G.GOLDRING,P.HILLMAN)
31097001 5
TITLE
FAST NEUTRON SPECTROSCOPY WITH SOLID STATE DETECTORS.
31097001 6
HISTORY
(771115T) CONVERTED FROM EXFOR 70097
31097001 7
ENDBIB
5
31097001
8
NOCOMMON
0 0
31097001 9
ENDSUBENT
8
3109700199999
SUBENT
31097003 851217
31097003 1
BIB
3 3
31097003 2
REACTION
(14-SI-28(N,P)13-AL-28,,SIG)
31097003 3
DETECTOR
(SOLST) SOLID
STATE DETECTOR
31097003 4
STATUS
(SCSRS)
31097003 5
ENDBIB
3
31097003 6
NOCOMMON
0 0
31097003 7
DATA
2 8
31097003 8
EN
DATA
31097003 9
MEV
B
31097003 10
5.3500E+00
1.5000E-02
31097003 11
5.5500E+00
6.0000E-02
31097003 12
5.7000E+00
1.0900E-01
31097003 13
5.7500E+00
8.5000E-02
31097003
14
5.8500E+00
5.5000E-02
31097003 15
6.0000E+00
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31097003 16
6.1500E+00
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6.4000E+00
1.5000E-01
31097003 18
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31097003 19
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3109700399999
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3109799999999
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10529 3
1 14028 3
4 A 2791400.
0.352200 0.028000
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 2799200.
0.367600 0.028700
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 2807000.
0.343400 0.028700
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 2814800.
0.392000 0.029800
F.G.PEREY,ET.AL.
(71) 10529
3
1 14028 3
4 A 2822600.
0.409400 0.030400
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 2830400.
0.523700 0.032700
F.G.PEREY,ET.AL.
(71) 10529 3
1 14028 3
4 A 2838200.
0.639400 0.034900
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 2846000.
0.843900 0.038300 F.G.PEREY,ET.AL.
(71) 10529
3
1 14028 3
4 A 2853700.
0.824300 0.038300
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 2861500.
0.951800 0.040400
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 2869300.
0.896200 0.039800
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 2877100.
0.752000 0.037900
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 2884900.
0.538100 0.034600
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 2892700.
0.359100 0.031500
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 2900500.
0.335900 0.031300
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 2908300.
0.242000 0.029500
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 2916100.
0.331700 0.031300
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 2923900.
0.308400 0.031000
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 2931700.
0.411800 0.033000
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3 4 A 2939500.
0.494900 0.034600
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 2947300.
0.381700 0.032600
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 2952100.
0.274200 0.027300
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 2961900.
0.220000 0.026300
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 2971600.
0.199100 0.025900
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 2981300.
0.189200 0.025700
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 2991100.
0.254200 0.026900
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3000800.
0.283400 0.027300
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3010600.
0.324900 0.027800
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3020300.
0.350400 0.028000
F.G.PEREY,ET.AL.
(71) 10529
3
1 14028 3
4 A 3030000.
0.286500 0.026600
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3039800.
0.349700 0.027400
F.G.PEREY,ET.AL.
(71) 10529 3
1 14028 3
4 A 3049500.
0.433600 0.028700
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3059200.
0.548400 0.030400
F.G.PEREY,ET.AL.
(71) 10529
3
1 14028 3
4 A 3069000.
0.545600 0.030300
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3078700.
0.416400 0.028200
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3088400.
0.367300 0.027400
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3098200.
0.539100 0.030100
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3107900.
0.751500 0.033100
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3117600.
0.762300 0.033300
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3127400.
0.683900 0.032300
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3137100.
0.634800 0.031600
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3146800.
0.675100 0.032300
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3156500.
0.581900 0.031100
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3166300.
0.433800 0.029100
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3176000.
0.483900 0.030000
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3185700.
0.394300 0.028800
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3195500.
0.442800 0.029800
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3205200.
0.417000 0.029800
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3214900.
0.486300 0.031100
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3224600.
0.685300 0.034300
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3234400.
0.882000 0.037200
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3244100.
0.866300 0.037400
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3253800.
0.771200 0.036400
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3263500.
0.615900 0.034500
F.G.PEREY,ET.AL.
(71) 10529
3
1 14028 3
4 A 3273300.
0.567200 0.034100
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3283000.
0.627900 0.035200
F.G.PEREY,ET.AL.
(71) 10529
3
1 14028 3
4 A 3292700.
0.640400 0.035600
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3302400.
0.602600 0.035300
F.G.PEREY,ET.AL.
(71) 10529 3
1 14028 3
4 A 3312200.
0.543400 0.034700
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3321900.
0.486500 0.034100
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3331600.
0.521600 0.034900
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3341300.
0.557000 0.035700
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3351100.
0.569600 0.036000
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3360800.
0.577100 0.036300
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3370500.
0.542500 0.036000
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3380200.
0.558800 0.036500
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3389900.
0.472500 0.035300
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3399700.
0.495800 0.035800
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3409400.
0.449800 0.035300
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3419100.
0.526800 0.036700
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3428800.
0.561800 0.037400
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3438500.
0.473500 0.036100
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3448200.
0.363800 0.034300
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3458000.
0.284300 0.032900
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3467700.
0.303400 0.033200
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3477400.
0.281300 0.032900
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3487100.
0.234100 0.032100
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3496800.
0.219300 0.031900
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3506500.
0.260200 0.032900
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3516300.
0.407600 0.035700
F.G.PEREY,ET.AL. (71)
10529 3
1 14028 3
4 A 3526000.
0.433700 0.036300
F.G.PEREY,ET.AL.
(71) 10529
3
1 14028 3 103
5350000.
0.015000
M.BIRK,ET.AL. (63)
31097 3
1 14028 3 103
5550000.
0.060000
M.BIRK,ET.AL.
(63) 31097
3
1 14028 3 103
5700000.
0.109000
M.BIRK,ET.AL. (63)
31097 3
1 14028 3 103
5750000.
0.085000
M.BIRK,ET.AL.
(63) 31097
3
1 14028 3 103
5850000.
0.055000
M.BIRK,ET.AL. (63)
31097 3
1 14028 3 103
6000000.
0.120000 M.BIRK,ET.AL.
(63) 31097
3
1 14028 3 103
6150000.
0.120000
M.BIRK,ET.AL. (63)
31097 3
1 14028 3 103
6400000.
0.150000
M.BIRK,ET.AL. (63)
31097 3
1 14028 3 103
1.2330+7
0.377000 0.045200
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.2990+7
0.357700 0.043000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.3000+7
0.340100 0.040800
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103 1.3100+7
0.448000 0.063000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.3380+7
0.389600 0.043000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.3500+7
0.381600 0.045000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.3590+7
0.388800 0.046700
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.3730+7
0.348500 0.035000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.3730+7
0.326400 0.033000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.3840+7
0.415000 0.046000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.4010+7
0.441300 0.053000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.4280+7
0.350500 0.039000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.4280+7
0.376600 0.047000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.4740+7
0.340300 0.037000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.4990+7
0.306200 0.040000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.4990+7
0.344600 0.045000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.4990+7
0.260100 0.031000
B.D.KERN,ET.AL.
(59) 11464
4
1 14028 3 103
1.5060+7
0.301000 0.033000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.5440+7
0.298500 0.033000
B.D.KERN,ET.AL.
(59) 11464
4
1 14028 3 103
1.5660+7
0.316000 0.035000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.5990+7
0.233200 0.028000
B.D.KERN,ET.AL.
(59) 11464
4
1 14028 3 103
1.5990+7
0.260600 0.031000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.6210+7
0.231200 0.025000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.6320+7
0.292600 0.041000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.6680+7
0.268400 0.032000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.6980+7
0.211100 0.025000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.6980+7 0.214800 0.026000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.7040+7
0.254200 0.036000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.7120+7
0.282400 0.036000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.7500+7
0.233000 0.035000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103 1.7500+7
0.188700 0.026000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.7520+7
0.209800 0.024000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3
103 1.8240+7
0.158400 0.025000
B.D.KERN,ET.AL. (59)
11464 4
1 14028 3 103
1.4500+7
0.220000 0.050600
E.B.PAUL,ET.AL. (53)
11274 11
1 14028 4
2 C 1.4200+7
0.247200 0.039800 0.899558
M.BABA,ET.AL. (85)
21984119
1 14028 4
2 C 1.4200+7
0.118000 0.013500 0.857167
M.BABA,ET.AL. (85) 21984119
1 14028 4
2 C 1.4200+7
0.018700 2.1000-3 0.689619
M.BABA,ET.AL. (85)
21984119
1 14028 4
2 C 1.4200+7
0.039300 3.6000-3 0.472549
M.BABA,ET.AL. (85)
21984119
1 14028 4
2 C 1.4200+7
0.021000 4.1000-3 0.224949
M.BABA,ET.AL. (85)
21984119
1 14028 4
2 C 1.4200+7
0.013100 2.0000-3 0.139171
M.BABA,ET.AL. (85)
21984119
1 14028 4
2 C 1.4200+7
0.010500 1.7000-3-0.292374
M.BABA,ET.AL. (85)
21984119
1 14028 4
2 C 1.4200+7
9.5700-3 1.0300-3-0.526958
M.BABA,ET.AL.
(85) 21984119
1 14028 4
2 C 1.4200+7
6.7700-3 7.6000-4-0.724174
M.BABA,ET.AL. (85)
21984119
1 14028 4
2 C 1.4200+7
5.3100-3 6.0000-4-0.874622
M.BABA,ET.AL.
(85) 21984119
1 14028 4
2 C 1.4200+7
0.013000 1.0000-3-0.999450 4.3407-4
B.MINETTI,ET.AL. (73)
20498 2
1 14028 4
2 C 1.4200+7
0.011000 9.0000-4-0.994150 1.4138-3
B.MINETTI,ET.AL. (73)
20498 2
1 14028 4
2 C 1.4200+7
0.011000 8.0000-4-0.991890 1.6637-3
B.MINETTI,ET.AL. (73)
20498 2
1 14028 4
2 C 1.4200+7
0.011100 9.0000-4-0.969010 3.2334-3
B.MINETTI,ET.AL. (73)
20498 2
1 14028 4
2 C 1.4200+7
9.7000-3 8.0000-4-0.945510 4.2619-3
B.MINETTI,ET.AL. (73)
20498 2
1 14028 4
2 C 1.4200+7
8.4000-3 8.0000-4-0.908500 5.4699-3
B.MINETTI,ET.AL. (73)
20498 2
1 14028 4
2 C 1.4200+7
6.8000-3 6.0000-4-0.879640 6.2259-3
B.MINETTI,ET.AL. (73)
20498 2
1 14028 4
2 C 1.4200+7
6.7000-3 6.0000-4-0.837710 7.1484-3
B.MINETTI,ET.AL. (73)
20498 2
PLOTS of the Data using program
PLOTC4
(see
document IAEA-NDS-79)
