INTERNATIONAL ATOMIC ENERGY AGENCY

NUCLEAR DATA SERVICESDOCUMENTATION SERIES OF THE IAEA NUCLEAR DATA SECTION

IAEA-NDS-206
June 2008

EXFOR Formats Description for Users(EXFOR Basics)

edited by
Otto Schwerer
IAEA Nuclear Data Section
Vienna, Austria

on behalf of the
Nuclear Reaction Data Centres Network
June 2008

Abstract: EXFOR is the exchange format for the transmission of experimental nuclear
reaction data between national and international nuclear data centres for the benefit ofnuclear data users in all countries. This report contains a general introduction to EXFOR, adetailed description of the exchange format, a brief description of the computational
format C4, and tables of the dictionaries of most important abbreviations used in EXFOR.

Nuclear Data Section
International Atomic Energy Agency
P.O. Box 100
A-1400 Vienna
Austriae-mail: services@iaeand.iaea.org
fax: (43-1)26007
telephone: (43-1)2600-21710
web: http://www-nds.iaea.org

Citation guideline:
When quoting EXFOR data in a publication this should be done in the following way:
"A.B. Author et al.: Data file EXFOR-12345.002 dated 1980-04-05, compare J. Nucl. Phys.
12,345, (1979). EXFOR data retrieved from the IAEA Nuclear Data Section, Vienna."

EXFOR Basics

PREFACE
EXFOR is the database for experimental nuclear reaction data maintained by theinternational Network of Nuclear Reaction Data Centres (NRDC) co-ordinated by the
IAEA Nuclear Data Section. This manual describes the main principles of thedatabase and the most important features of the EXFOR exchange format of interest
to database users. A description of the computational format C4 and brief examples ofother output formats are also included.
This manual is not intended as a complete guide to the EXFOR system. NRDC staff
and other experts involved in database input (compilation) and/or related softwaredevelopment should consult the following relevant manuals:

Name

Report code

TopicsEXFOR Exchange
Formats Manual

IAEA-NDS-207

LEXFOR

IAEA-NDS-208

EXFOR/CINDA
Dictionary Manual

IAEA-NDS-213

Description of
EXFOR exchange
formats
Quantity
definitions andcompilation
guidelines
Description of
dictionary formats

NRDC Protocol

NRDC Protocol

NRDC Network
document

INDC(NDS)-401

Procedures for
EXFOR exchange
between NRDC
centres
Scope of activities
and cooperation of
NRDC centres

Intendedreadership
Compilers,
softwaredevelopers
CompilersCompilers,
softwaredevelopers
Compilers, centre
heads

Centre heads

How to use this manual
Chapter I (A Quick Guide to EXFOR) explains the basic ideas of EXFOR; it can also
be used as a stand-alone introduction which may be sufficient as a guide for theoccasional user.
Chapter II gives a detailed overview of the exchange format, containing all details
which may be important for users, but excluding technical details which are ofsignificance only for data centre staff and external EXFOR compilers.

i

EXFOR Basics

Chapter III describes the computational format C4 in some detail and also shows
several examples of other user output formats.
The appendix lists the most important codes (abbreviations) from the EXFOR
dictionaries which users may need to interpret EXFOR retrievals.

Acknowledgements
This manual is partly based on earlier work by former NRDC staff. In particular thecontributions of V. McLane (National Nuclear Data Center, Brookhaven National
Laboratory, USA) and H.D. Lemmel (IAEA Nuclear Data Section, Vienna, Austria)
to earlier versions of this manual and other documents related to EXFOR are
gratefully acknowledged.

O.S., June 2008

ii

EXFOR Basics

Table of Contents

I. A Quick Guide to EXFOR..........................................................................................3
What is EXFOR? .......................................................................................................3
Principles of EXFOR .................................................................................................4
Data types included in EXFOR..................................................................................5
Quantities ...............................................................................................................5
Projectiles...............................................................................................................6
Basic structure of the EXFOR format........................................................................6
Data definition .......................................................................................................7
EXFOR examples ......................................................................................................9
History of EXFOR ...................................................................................................18
The Network of Nuclear Reaction Data Centres .....................................................19
EXFOR Retrieval Websites .....................................................................................20
Citation Guidelines ..................................................................................................20
II. Overview of the EXFOR Exchange Format ...........................................................21
General Structure of the Exchange Format..............................................................21
Permitted character set.........................................................................................22
Identification of Files, Entries, and Subentries....................................................23
EXFOR Records ..................................................................................................24
System Identifiers ................................................................................................24
BIB, COMMON and DATA Sections .....................................................................26
BIB Section..........................................................................................................26
COMMON and DATA Sections..........................................................................27
Pointers ................................................................................................................29
Nuclide and reaction specification...........................................................................30
Coding of nuclides and compounds .....................................................................30
Reaction Specification .........................................................................................30
Information Identifier Keywords .............................................................................35
Covariance Data File Format ...................................................................................44
III. User Output Formats..............................................................................................47
Computational Format C4........................................................................................48
Examples of other output formats............................................................................54
Appendix: Tables of Dictionaries ................................................................................611

EXFOR Basics

2

EXFOR Basics

I. A Quick Guide to EXFOR
What is EXFOR?
EXFOR is the library and format for the collection, storage, exchange and retrieval ofexperimental nuclear reaction data. The library is the product of a worldwide cooperation, namely the international Network of Nuclear Reaction Data Centres(NRDC) which is co-ordinated by the IAEA Nuclear Data Section (NDS).
At present (May 2008), the EXFOR database contains about 17,000 works witharound 129,000 data tables, representing• a "complete" compilation of low-energy experimental neutron-induced
reaction data,• a less complete compilation of charged-particle-induced reaction data,• a selected compilation of photon-induced, heavy-ion-induced,

and high

energy neutron-induced reaction data.
At present, compilation efforts concentrate on complete coverage of newly publisheddata as well as, depending on the available manpower, on filling gaps in oldmeasurements which are important for certain applications.
Selective retrievals from the database are available in various formats from the web
sites of the IAEA Nuclear Data Section and other cooperating NRDC centres. The
output formats include the original EXFOR (Exchange) format (described in detail in
Chapter II) as well as various other “user” formats which may differ at various data
centres (examples of several user output formats are given in Chapter III).
The basic unit of EXFOR is an entry, which corresponds to one experiment which isusually described in one or more bibliographic references (journal articles, laboratory
reports, conference proceedings etc.). An entry contains the numerical data and theirdefinition as measured by the authors, along with the related bibliographic
information and a brief description of the experimental method. An entry is typicallydivided in several subentries containing the various data tables resulting from theexperiment.
EXFOR is, unlike bibliographic systems, primarily work-oriented, not publicationoriented, and contains many data which have never been published in numerical form,
and it is regularly updated (e.g. when authors revise their data after publication).

3

EXFOR Basics

Principles of EXFOR

4•

EXFOR is not a bibliographic system but contains numerical nuclear data withcross-references to pertinent publications•

EXFOR contains many data that have never been published in numerical form.
It is therefore a publication medium supplementary to conventional, formal
publications.

•

EXFOR data are currently updated. When authors revise their data after
publication, the EXFOR files are kept up-to-date accordingly.

•

The numerical data in EXFOR are supplemented by explanatory text giving
essential information on meaning and quality of the data including summaries
on measurement techniques, corrections and error analysis, standard reference
values used, etc.

•

An EXFOR “entry” represents the results of a work performed at a given
laboratory at a given time; an EXFOR “entry” does not necessarily correspondto the information found in one particular publication. Very often, a “work” isreported in several – formal or informal – publications, typically in one ormore progress reports, a conference paper with preliminary results, a lab
report, and a final but often less detailed article in a refereed international
journal. The EXFOR compiler extracts the essential information from all thesesources and, in addition, contacts the author in order to obtain additional
information (e.g. details on the error analysis) and/or tabular data for results
published only in graphical form, and to verify that the data compiled are theauthor’s final results. This makes EXFOR entirely different from any
bibliographic system, which may or may not include all the relevantpublications, but will never tell the user whether they describe actually thesame work or not. (The only exception to this is CINDA, a bibliography also
maintained by the NRDC and closely related to EXFOR, where publications
describing the same experiment are listed together in one block).

•

EXFOR contains also numerical data which were digitized from results
published only in graphical form, and where the original tabulated data could
not be obtained from the authors.

•

An EXFOR “entry” is identified by an accession number and a date (meaning
the date of compilation or of the last revision of the entry). If an entry isrevised, nature and reason of the revision are documented within the entry.

•

Each EXFOR entry is divided into a number of subentries (data sets)containing the data tables from this particular work. A subentry is identified bya subaccession number, consisting of the accession number and a subentry
number.

•

EXFOR is designed for flexibility, to meet the diverse needs of the nuclear
reaction data centers and to allow the compilation of very diverse type ofquantities while making computerized processing of the data possible.

EXFOR Basics•

Compilations are done following as much as possible the author’s
representations of the quantities and the originally published data units, toavoid mistakes during data input and to facilitate comparison with the original
publication. Computerized processing and plotting of the data therefore do not
use the basic EXFOR exchange format but one of the available computational
formats which are offered as additional output options in the data centres’s
retrieval systems.

•

EXFOR may include also preliminary data (labelled as such) or (with consent
of the author) pre-publication data. Preliminary data will be routinely replacedby the final data once they become available, and any new bibliographic
references describing the results will be added.

•

EXFOR is a compilation of the author’s original published experimental data.
While the format allows the inclusion of data renormalized to up-to-datestandard values (with proper documentation), this task is normally left to data
evaluators who systematically review the experimental works.

•

EXFOR is not a collection of recommended values for each reaction but willusually contain results from different authors for the same reaction which may
or may not be in agreement. The task of recommending best evaluated crosssection data is the task of data evaluators. Their work is largely based on theexperimental data from EXFOR and their results are collected in various
evaluated data files such as ENDF/B, JEFF, JENDL, etc., most of them alsoavailable from the IAEA Nuclear Data Section. The retrieval software allows
to make comparison plots of evaluated data with experiments retrieved fromEXFOR.

Data types included in EXFOR
Quantities
All types of microscopic cross sections and related data, in particular:z Integral and partial cross sections (including excitation functions, spectrumaveraged data, ratios etc.)
z Differential cross sections of many types, including angular distributions andLegendre coefficients, secondary particle spectra, double-differential crosssections, polarization data, etc.
z Resonance parametersz Fission product yields, ν ( Nu-bar), fission quantities
z Product yields and thick target yields
z Reaction rates, resonance integrals

5

EXFOR Basics

Projectiles
z Regular compilation for projectile energies up to 1 GeV; selected data forhigher energies may be included alsoz Neutrons (Note that the neutron files include also some data with projectile‘0’, e.g. fission product yields from spontaneous fission)z Charged particles (regular compilation up to A=12)z Heavy ions with A>12 (selected coverage)z Photons

Basic structure of the EXFOR format
EXFOR (EXchange FORmat for experimental numerical nuclear reaction data)
presents in a convenient compact form numerical data as well as physical informationnecessary to understand the experiment and interpret the data.
Keywords and codes make the information computer intelligible, while English “freetext” gives additional information for the human user.
The basic unit of EXFOR is an entry, which corresponds to one experiment which isusually described in one or more bibliographic references (journal articles, laboratory
reports, conference proceedings etc.). As the results may consist of several data tables(e.g. cross sections σ(E) for several nuclides), each entry is divided into a number ofsubentries (data sets). Each entry is assigned an accession number; each subentry is
assigned a subaccession number (the accession number plus a subentry number).
The accession numbers are associated with a particular work throughout the life of the
EXFOR system.
The subentries are further divided into:• a text part containing bibliographic, descriptive and bookkeeping information(usually called "BIB" information),• common data that applies to all data throughout the subentry (called“COMMON” section), and• a data table (“DATA” section).
The first subentry contains the information which is common to the whole entry, i.e.
usually the bibliographic reference(s), essentials about the experimental method, andany common data (common parameters for the whole work). The first subentry does
not contain any numerical results.
The following subentries contain the actual experimental results (tables), plus any
bibliographic and experimental information or common parameters specific to theindividual subentry (table). Therefore, any entry consists of at least two subentries:

6

EXFOR Basics

the first subentry with the general information, and one or more following subentries
with data tables.
The text part (bibliographic, experimental and bookkeeping information) is specified
in variable length fields whose content is defined by keywords. An entry contains
only those keywords relevant for the particular work. The information attached to a
keyword may consist of "codes" (standard abbreviations taken from a "dictionary")
and/or unstructured English "free text".
The table below gives a list of the information identifier keywords. For many of these
there is a specific dictionary of permitted standard abbreviations (codes). These
dictionaries are open ended in the sense that new codes may be added whenever needarises. The keywords given in bold in the table below will appear in every entry.
Some of the keywords describing the experiment (such as FACILITY, METHOD,
DETECTOR) will also appear in every entry.

ADD-RESDETECTORINSTITUTE

REFERENCE

ANALYSIS

EN-SECLEVEL-PROP

REL-REFASSUMEDERR-ANALYSMETHODRESULT

AUTHOR

EXP-YEARMISC-COL

SAMPLECOMMENTFACILITY

MOM-SECSTATUS

CORRECTION

FLAGMONIT-REF

TITLE

COVARIANCE

HALF-LIFE

MONITORCRITIQUEHISTORY

PART-DET

DECAY-DATA

INC-SOURCE

RAD-DETDECAY-MON

INC-SPECTREACTION

Data definition
The data of each table in a subentry are defined in the keyword REACTION which
defines both the nuclear reaction as such (e.g. neutron-induced fission on 235U, or the
microscopic production cross section of a certain radionuclide by bombarding a leadtarget with protons) and the quantity measured (e.g. integral or differential crosssection, fission product yield, resonance parameters, etc.) The REACTION code
therefore consists of up to 9 subfields, subfield 1 through 4 for defining the nuclear
reaction, and subfields 5 through 9 for a detailed definition of the quantity
measured and its representation.

7

EXFOR Basics

Subfields 1 through 4 are usually self-explanatory:
1-H-1(N,G)1-H-2=

1

H(n,γ)2H

92-U-235(N,F)=

235

26-FE-56(N,INL)26-FE-56=

28-NI-0(P,X)11-NA-24=

56

U(n,f)

Fe(n,n’)natNi(p,x)24Na production

Subfields 5 through 8 define the quantity measured. They are separated by commas;
only subfield 6 is always present. Simple examples for complete REACTION codes
are:
REACTION(92-U-235(N,F),,SIG) = fission cross section σn,f for 235U

REACTION(28-NI-60(N,P)29-CU-60,,DA) =dσ/dΩ for the reaction 60Ni(n,p)60Cu

The numerical part of a subentry consists of the data table itself (DATA section)
and, most often, of one or more constant parameters given in the COMMON section.
In both cases, it is structured in columns with a constant field length of 11 characters.
All numerical columns are headed and defined by

8•column headings, for example- EN
for incident particle energy- DATAfor the actual data defined under the keyword
REACTION- DATA-ERR for the uncertainty of the data, etc.

•

data units, such as
- EV
- MB

for electron-Volts
for millibarns, etc.

EXFOR Basics

EXFOR examples
The following pages show examples of two EXFOR entries. The examples are given
in two formats, the basic EXFOR Exchange format, and the Interpreted “Exfor+”format, where many of the abbreviations used for bibliographic references, quantities,
detectors,etc., are expanded to full English text. These explanatory lines added by the“Interepreted EXFOR” output program are labelled with a # sign at the beginning.
(For examples of other user output formats see Chapter III.)
Both example entries contain constant parameters in COMMON sections. Note thata COMMON parameter given in subentry 2 is valid only for this particular subentry,
while a COMMON parameter given in subentry 1 is valid for all of the following
subentries.
In any retrieval, always subentry 1, which contains the information common to thewhole entry, is output together with all those other subentries which satisfy the
retrieval criteria. One of the examples shown here (accession number 31439) contains
subentries 1, 5, and 6, which is sufficient to demonstrate a complete set of information
output for a typical retrieval.
Subentry 31439.006 has a more complex structure in two respects:•

The table has data for 3 reactions (quantities). (This is possible if the data areintegrally related to each other and depend on the same independent variables;
here it is the cross sections for production of the ground state and for themetastable state of the same product, and the related isomeric ratio). In suchcases, the 3 REACTION codes are linked with the appropriate DATA columns
by means of “pointers”, in this case the flags “1”, “2” and “3”. Such pointers
may appear in EXFOR also in other places to link related peaces of
information.

•

The data table has 8 columns (the data for all 3 reactions and the monitor
reaction, each with its related uncertainty). Since the Exchange format allows
only 6 physical columns per line, the “logical lines” are broken – in this caseinto a first line of 6 columns and a second line with the remaining 2 columns.
This is inconvenient for the human reader, and the Interpreted EXFOR+
format outputs all 8 columns side by side.

9

EXFOR Basics

EXFOR Example 1 (Exchange Format)
Accession
numberENTRY
SUBENT
BIB
TITLE

C1582
20071127
20080305
20080228
C083C1582000
1
C1582001
20071127
20080305
20080228
C083C1582001
1
10
20C1582001
2
Astrophysically important 31S states studied with
C15820013
the 32S(p,d)31S reaction
C1582001
4
AUTHOR(Z.Ma,D.W.Bardayan,J.C.Blackmon,R.P.Fitzgerald,
C1582001
5
M.W. Guidry,W.R.Hix,K.L.Jones,R.L.Kozub, R.J.Livesay, C1582001
6
M.S.Smith,J.S.Thomas,And D.W.Visser)
C1582001
7
INSTITUTE (1USATEN,1USAORL,1USANCA,1USATTU,1USACSM)
C1582001
8(1USAUSA) Rutgers University, Piscataway, New Jersey
C1582001
9REFERENCE (J,PR/C,76,15803,2007)
C1582001
10
FACILITY(VDGT,1USAORL) HRIBF Facility
C1582001
11
SAMPLEZnS target with a thickness of 285 microgram/cm2
C1582001
12
deposited on 1 microgram/cm2 carbon for measurements
C1582001
13
at laboratory angles 17-48 deg. ZnS target with a
C1582001
14
thickness of 280 microgram/cm2 on 5 microgram/cm2
C1582001
15
carbon backing at laboratory angles 31-75 deg
C1582001
16
DETECTOR(SISD) Silicon detector array SIDAR operated in
C1582001
17
telescope mode with 300-micron-thick dE detectors
C1582001
18
backed by 500-micron-thick E detectors
C1582001
19
METHOD(EDE)
C1582001
20
ERR-ANALYS (DATA-ERR) No information
C1582001
21
HISTORY(20071127C) compiled by S.H.
C1582001
22
ENDBIB
20
C1582001
23
COMMON
1
3
C1582001
24
Common parameter
EN
C1582001
25
for whole entry
MEV
C1582001
26
32.0
C1582001
27
Subaccession
ENDCOMMON
3
C1582001
28
numberENDSUBENT
27
C158200199999
SUBENT
C1582002
20071127
20080305
20080228
C083C1582002
1
BIB
2
2
C1582002
2
REACTION(16-S-32(P,D)16-S-31,PAR,DA)
C1582002
3
STATUS(CURVE) Data taken from Fig 3 in the reference
C1582002
4
ENDBIB
2
C1582002
5
COMMON
1
3
C1582002
6
E-EXC
C1582002
7
Common parameter
Data defined
KEV
C1582002
8
for subentry 2
under REACTION
4085.0
C1582002
9
ENDCOMMON
3
C1582002
10
DATA
3
2
C1582002
11
ANG
DATA
DATA-ERRC1582002
12
ADEG
B/SR
B/SR
C1582002
13
1.857E+01 6.427E-04 8.978E-05
C1582002
14
2.196E+01 5.616E-04 8.567E-05
C1582002
15
ENDDATA
4
C1582002
16
ENDSUBENT
15C158200299999
SUBENT
C1582003
20071127
20080305
20080228
C083C1582003
1
BIB
2
2
C1582003
2
REACTION(16-S-32(P,D)16-S-31,PAR,DA)
C1582003
3
STATUS(CURVE) Data taken from Fig 3 in the reference
C1582003
4
ENDBIB
2
C1582003
5
COMMON
1
3
C1582003
6
E-EXC
C1582003
7
Common parameter
KEV
C1582003
8
for subentry 3
4451.0
C1582003
9
ENDCOMMON
3
C1582003
10
DATA
3
8
C1582003
11
ANG
DATA
DATA-ERRC1582003
12
ADEG
B/SR
B/SR
C1582003
13
1.869E+01 4.963E-05 7.643E-06
C1582003
14
2.042E+01 6.343E-05 7.943E-06
C1582003
15

10

EXFOR Basics

2.241E+01
2.440E+01
2.663E+01
2.837E+01
4.798E+01
5.071E+01
ENDDATAENDSUBENTENDENTRY

5.487E-05
5.132E-05
5.075E-05
5.548E-05
5.306E-05
4.800E-05
102137.930E-06
6.427E-06
5.858E-06
5.854E-06
5.066E-06
4.583E-06

C1582003
16
C1582003
17
C1582003
18
C1582003
19
C1582003
20
C1582003
21
C1582003
22
C158200399999
C158299999999

11

EXFOR Basics

EXFOR Example 1 (EXFOR+ format)
Lines starting with # are explanatory lines added by the “Interpreted EXFOR” output
programENTRY
SUBENTBIB
TITLE
AUTHOR

INSTITUTE

REFERENCE

C1582
20071127
20080305
20080228
C083
C1582001
20071127
20080305
20080228
C083
10
20
Astrophysically important 31S states studied withthe 32S(p,d)31S reaction(Z.Ma,D.W.Bardayan,J.C.Blackmon,R.P.Fitzgerald,
M.W. Guidry,W.R.Hix,K.L.Jones,R.L.Kozub, R.J.Livesay,
M.S.Smith,J.S.Thomas,And D.W.Visser)(1USATEN,1USAORL,1USANCA,1USATTU,1USACSM)(1USAUSA) Rutgers University, Piscataway, New Jersey#(1USACSM) Colorado School of Mines, Golden, CO, USA#(1USANCA) University of North Carolina, Chapel Hill, NC, USA#(1USAORL) Oak Ridge National Laboratory, Oak Ridge, TN, USA
Interpreted abbreviations#(1USATEN) University of Tennessee, Knoxville, TN, USA#(1USATTU) Tennessee Technical Univ., Cookeville, TN, USA#(1USAUSA) United States of America, USA(J,PR/C,76,15803,2007)# (J,PR/C,76,15803,2007) Journ.: Physical Review, Part C, Nuclear Physics, Vol.76, p.15803(2007) USA

URL of electronic journal article#+#URL=http://publish.aps.org/abstract/PRC/v76/p15803(VDGT,1USAORL) HRIBF Facility#(VDGT) Tandem van de Graaff
Interpreted abbreviations#(1USAORL) Oak Ridge National Laboratory, Oak Ridge, TN, USA
SAMPLEZnS target with a thickness of 285 microgram/cm2
deposited on 1 microgram/cm2 carbon for measurements
at laboratory angles 17-48 deg. ZnS target with athickness of 280 microgram/cm2 on 5 microgram/cm2
carbon backing at laboratory angles 31-75 deg
DETECTOR(SISD) Silicon detector array SIDAR operated intelescope mode with 300-micron-thick dE detectors
backed by 500-micron-thick E detectors#(SISD) Silicon strip detector
METHOD(EDE)#(EDE) Particle identification by `E/Delta E` measurement
ERR-ANALYS (DATA-ERR) No information
HISTORY(20071127C) compiled by S.H.
ENDBIB
20
COMMON
1
3
EN
MEV
32.
ENDCOMMON
3
ENDSUBENT
27
SUBENT
C1582002
20071127
20080305
20080228
C083
BIB
2
2
REACTION(16-S-32(P,D)16-S-31,PAR,DA)#(16-S-32(P,D)16-S-31,PAR,DA) Quantity: [DAP] Partial differential cross section d/dA
STATUS(CURVE) Data taken from Fig 3 in the reference
ENDBIB
2
COMMON
1
3
Interpreted abbreviation of quantity
E-EXC
KEV
4085.
ENDCOMMON
3
DATA
3
2
ANG
DATA
DATA-ERR
ADEG
B/SR
B/SR
18.57
6.427E-4
8.978E-5
21.96
5.616E-4
8.567E-5
ENDDATA
4ENDSUBENT
15
SUBENT
C1582003
20071127
20080305
20080228
C083
BIB
2
2
REACTION(16-S-32(P,D)16-S-31,PAR,DA)#(16-S-32(P,D)16-S-31,PAR,DA) Quantity: [DAP] Partial differential cross section d/dA
STATUS(CURVE) Data taken from Fig 3 in the reference
ENDBIB
2
FACILITY

12

EXFOR Basics

COMMON
E-EXC
KEV
4451.
ENDCOMMON
DATA
ANG
ADEG
18.69
20.42
22.41
24.4
26.63
28.37
47.98
50.71
ENDDATAENDSUBENTENDENTRY

1

3

3
3
DATA
B/SR
4.963E-5
6.343E-5
5.487E-5
5.132E-5
5.075E-5
5.548E-5
5.306E-5
4.8E-58
DATA-ERR
B/SR
7.643E-6
7.943E-6
7.93E-6
6.427E-6
5.858E-6
5.854E-6
5.066E-6
4.583E-6

10
21
3

13

EXFOR Basics

EXFOR Example 2 (Exchange format)
Accession
numberENTRY
SUBENT
BIB
TITLE

31439
940712
2005026
000031439000
131439001
940712
20050926
000031439001
111
1431439001
2
Activation cross sections and isomeric ratios in reac- 31439001
3
tions induced by 14.5 MeV neutrons in Sm-152, Sm-154
31439001
4
and Hf-178.
31439001
5
AUTHOR(A.KIROV,N.NENOFF,E.GEORGIEVA,C.NECHEVA,I.EPHTIMOV)
31439001
6
INSTITUTE (3BULSOF)
31439001
7REFERENCE (J,ZP/A,245,(3),285,9305)
31439001
8
FACILITY(CCW)
31439001
9
INC-SOURCE (D-T)
31439001
10
METHOD(ACTIV)31439001
11
DETECTOR(HPGE)
31439001
12
ERR-ANALYS No error analysis given.
31439001
13
STATUS
Data are from table 1 of Z. Phys. A, vol. 345, no. 3, 31439001
14
pp. 285-292.
31439001
15
HISTORY(940610C) HW
31439001
16
ENDBIB
1431439001
17
COMMON2
331439001
18
Common parameters
EN
EN-ERR31439001
19
for whole entry
MEV
MEV
31439001
20
14.54
0.24
31439001
21
ENDCOMMON
331439001
22
Subaccession
ENDSUBENT
213143900199999
numberSUBENT
31439005
940712
20050926
000031439005
1
BIB
6
14
31439005
2
REACTION(62-SM-154(N,D)61-PM-153,,SIG)
31439005
3
DECAY-DATA (61-PM-153,5.3MIN,DG,127.3,.14)31439005
4
SAMPLE
Samariumoxide powder enriched to 99.2% Sm-154, mixed
31439005
5
with ironoxide powder in precise measured weight31439005
6
ratio. 200 mg of the mixture was placed and sealed in 31439005
7
polyethylene capsules in the form of cylinders 10 mm
31439005
8
in diameter and few mm high.
31439005
9
MONITOR(62-SM-154(N,A)60-ND-151,,SIG)
31439005
10
MONIT-REF (,S.M.QAIM+,B,HB.SPEC,3,141,81)31439005
11
CORRECTION Corrections have been made for coincidence summing
31439005
12
and ranged between 2 and 48%. The coincidence summing 31439005
13
correction factors for the lines of interest were ob- 31439005
14tained from the known decay schemes and the total
31439005
15
efficiency of the detector.
31439005
16
ENDBIB
1431439005
17
NOCOMMON31439005
18
DATA
4
1
31439005
19
DATA
ERR-T
MONIT
MONIT-ERR
31439005
20
MB
MB
MB
MB
31439005
21
.43
.08
1.9
0.4
31439005
22
ENDDATA331439005
23
ENDSUBENT
223143900599999
SUBENT
31439006
940712
20050926
000031439006
1
BIB
6
21
31439006
2
REACTION 1(72-HF-178(N,P)71-LU-178-G,,SIG)
31439006
3
2(72-HF-178(N,P)71-LU-178-M,,SIG)
31439006
4
3 reactions (quantities)
3(72-HF-178(N,P)71-LU-178-M/G,,SIG/RAT)
31439006
5
given in one subentry,labelled with “pointers” 1, 2, 3
DECAY-DATA (71-LU-178-M,22.9MIN,DG,213.4,.809,
31439006
6
DG,325.6,.939,
31439006
7
DG,426.4,.969,
31439006
8
DG,331.7,.116)
31439006
9(71-LU-178-G,28.1MIN,DG,1340.8,.0474)
31439006
10
SAMPLE
Hafniumoxide powder enriched to 92.4% Hf-178, mixed
31439006
11
with ironoxide powder in precise measured weight31439006
12

14

EXFOR Basics

ratio. 200 mg of the mixture was placed and sealed in 31439006
13
polyethylene capsules in the form of cylinders 10 mm
31439006
14
in diameter and few mm high.
31439006
15
MONITOR(26-FE-56(N,P)25-MN-56,,SIG)
31439006
16
MONIT-REF (30675002,A.ANTOV+,J,BJP,10,(6),601,83)31439006
17(,N.NENOFF+,J,GUS,78,35,84)31439006
18
CORRECTION Corrections have been made for coincidence summing
31439006
19
and ranged between 2 and 48%. The coincidence summing 31439006
20
correction factors for the lines of interest were ob- 31439006
21
tainedthe forknown
decay 2schemes
the total3
31439006
22
Data for REACTION
1 from Data
REACTION
Dataandfor REACTION
efficiency of the detector.
31439006
23
ENDBIB
2131439006
24
NOCOMMON31439006
25
DATA
8
1
31439006
26
DATA
1ERR-T
1DATA
2ERR-T
2DATA
3ERR-T
331439006
27
MONIT
MONIT-ERR
31439006
28
MB
MB
MB
MB
NO-DIM
NO-DIM
31439006
29
MBMB
31439006
30
1.8
0.4
.98
.08
0.54
0.13
31439006
31
110.9
2.8
31439006
32
ENDDATA
631439006
33
ENDSUBENT
323143900699999
ENDENTRY
33143999999999
DATA table with 8 fields (columns). Since the format
allows only 6 columns per line, each logical line is split
into two physical lines, one with 6 fields and another one
with the remaining 2 fields. The format allows tables withup to 18 fields.
Compare display of the same entry in EXFOR+ format
on following pages.

15

EXFOR Basics

EXFOR Example 2 (EXFOR+ format)
Lines starting with # are explanatory lines added by the “Interpreted EXFOR” output
programENTRY
SUBENT
BIB
TITLE

31439
940712
20050926
0000
31439001
940712
200509260000
11
14Activation cross sections and isomeric ratios in reactions induced by 14.5 MeV neutrons in Sm-152, Sm-154
and Hf-178.
AUTHOR(A.KIROV,N.NENOFF,E.GEORGIEVA,C.NECHEVA,I.EPHTIMOV)INSTITUTE (3BULSOF)#(3BULSOF) Univ.of Sofia, Bulgaria
REFERENCE (J,ZP/A,245,(3),285,9305)# (J,ZP/A,245,(3),285,9305) Journ.: Zeitschrift fuer Physik, Section A, Vol.245, Issue.3, p.285(1993) Germany
FACILITY(CCW)#(CCW) Cockcroft-Walton accelerator
INC-SOURCE (D-T)
Interpreted abbreviations
METHOD(ACTIV)#(ACTIV) Activation
DETECTOR(HPGE)#(HPGE) Hyperpure Germanium detector
ERR-ANALYS No error analysis given.
STATUS
Data are from table 1 of Z. Phys. A, vol. 345, no. 3,
pp. 285-292.
HISTORY(940610C) HWENDBIB
14
COMMON
2
3
EN
EN-ERR
MEV
MEV
14.54
0.24
ENDCOMMON
3
ENDSUBENT
21
SUBENT
31439005
940712
20050926
0000
BIB
6
14
REACTION(62-SM-154(N,D)61-PM-153,,SIG)
Interpreted abbreviation of#(62-SM-154(N,D)61-PM-153,,SIG) Quantity: [CS] Cross section
quantity
DECAY-DATA (61-PM-153,5.3MIN,DG,127.3,.14)
SAMPLE
Samariumoxide powder enriched to 99.2% Sm-154, mixed
with ironoxide powder in precise measured weightratio. 200 mg of the mixture was placed and sealed inpolyethylene capsules in the form of cylinders 10 mm
in diameter and few mm high.
MONITOR(62-SM-154(N,A)60-ND-151,,SIG)
MONIT-REF (,S.M.QAIM+,B,HB.SPEC,3,141,81)
CORRECTION Corrections have been made for coincidence summing
and ranged between 2 and 48%. The coincidence summingcorrection factors for the lines of interest were obtained from the known decay schemes and the total
efficiency of the detector.
ENDBIB
14
NOCOMMON
DATA
4
1
DATA
ERR-T
MONIT
MONIT-ERR
MB
MB
MB
MB
.43
.08
1.9
0.4
ENDDATA
3
ENDSUBENT
22
SUBENT
31439006
940712
20050926
0000
BIB
6
21
REACTION 1(72-HF-178(N,P)71-LU-178-G,,SIG)
Interpreted abbreviations of2(72-HF-178(N,P)71-LU-178-M,,SIG)
quantities
3(72-HF-178(N,P)71-LU-178-M/G,,SIG/RAT)#(72-HF-178(N,P)71-LU-178-G,,SIG) Quantity: [CS] Cross section#(72-HF-178(N,P)71-LU-178-M,,SIG) Quantity: [CS] Cross section#(72-HF-178(N,P)71-LU-178-M/G,,SIG/RAT) Quantity: [CS] Cross section ratio
DECAY-DATA (71-LU-178-M,22.9MIN,DG,213.4,.809,
DG,325.6,.939,
DG,426.4,.969,
DG,331.7,.116)(71-LU-178-G,28.1MIN,DG,1340.8,.0474)

16

EXFOR Basics

SAMPLE

Hafniumoxide powder enriched to 92.4% Hf-178, mixed
with ironoxide powder in precise measured weightratio. 200 mg of the mixture was placed and sealed inpolyethylene capsules in the form of cylinders 10 mm
in diameter and few mm high.
MONITOR(26-FE-56(N,P)25-MN-56,,SIG)
MONIT-REF (30675002,A.ANTOV+,J,BJP,10,(6),601,83)(,N.NENOFF+,J,GUS,78,35,84)
CORRECTION Corrections have been made for coincidence summing
and ranged between 2 and 48%. The coincidence summing
Proper display of table withcorrection factors for the lines of interest were obmore than 6 columns
tained from the known decay schemes and the total
efficiency of the detector.
ENDBIB
21
NOCOMMON
DATA
8
1
8
DATA
1ERR-T
1DATA
2ERR-T
2DATA
3ERR-T
3MONITMONIT-ERR
MB
MB
MB
MB
NO-DIM
NO-DIM
MB
MB
1.8
0.4
.98
.08
0.54
0.13
110.9
2.8
ENDDATA
6ENDSUBENT32
ENDENTRY
3

17

EXFOR Basics

History of EXFOR
Systematic collection of experimental neutron nuclear data started in the 1960s at four
data centres, each using its own data storage and retrieval system:•

Brookhaven National Laboratory (BNL), USA (formerly Sigma Center, now
NNDC - National Nuclear Data Center), using “SCISRS”;•

OECD Nuclear Energy Agency, France (formerly Neutron Nuclear Data Centre,
Saclay, now NEA Data Bank, Gif-sur-Yvette), using “NEUDADA”;•

International Atomic Energy Agency (IAEA), Vienna, Austria (formerly Nuclear
Data Unit, now Nuclear Data Section), using “DASTAR”;•

Fiziko-Energeticheskij Institut (IPPE) Obninsk, Russia, (Center Jadernykh
Dannykh), using a USSR computer system incompatible to Western computers.

It became obvious that these activities required coordination, and through discussions
held between software experts and physicists from Saclay, Vienna, Livermore andBrookhaven, a joint nuclear data exchange format “EXFOR” was formulated in its
initial form at a panel meeting in Brookhaven in February 1969. It was accepted at an
IAEA Consultant’s Meeting in Moscow in November 1969, and in 1970 the system went
into operation, including the Obninsk Center, which solved the compatibility problem to
USSR computers. Thus an East-West information exchange on magnetic tapes was
initiated for the first time. Data compiled at any one of the centres were speedilytransmitted to the other centres, making them available to the fast increasing communityof data users throughout the world.
As the name suggests, EXFOR was designed to be the format of data exchange between
centres. The centres were free to use different formats for internal storage and/or for
output retrievals made available to users.
Subsequently, data compiled earlier were converted to EXFOR, and in the 1970s, thescope was widened to include also charged-particle induced nuclear data andphotonuclear data. For this purpose, the original format was modified, and additional
nuclear data centres joined the network. A list of the cooperating data centres is given on
the following page.
The data retrieval services to users were, for many years, done centrally by data centre
staff who received specific data retrieval requests by mail and in turn mailed output
listings on paper or magnetic tapes back to the users. From the late 1980s, online retrieval
systems, using Telnet or other remote access systems, started to be used for nuclear datain parallel to the central retrieval services, including EXFOR (1988 - NNDC, 1992 –IAEA-NDS). In the late 1990s, web-based retrieval systems were introduced (starting
1997 at IAEA-NDS) and are continuously being refined.
While the network of nuclear reaction data centres has been coordinated by the IAEA
Nuclear Data Section since its start, each participating centre independently maintained
and updated its EXFOR master file. This sometimes led to occasional differences in the
database contents due to differences in the synchronisation of updates or other reasons.
Therefore, a common global EXFOR master file has been introduced in 2005 which ismaintained centrally by IAEA-NDS and is the basis for the worldwide EXFOR
operations and services.

18

EXFOR Basics

The Network of Nuclear Reaction Data Centres
National, regional and specialized nuclear reaction data centres, coordinated by theInternational Atomic Energy Agency, cooperate in the compilation, exchange anddissemination of nuclear reaction data, in order to meet the requirements of nuclear data
users in all countries. At present, the following data centres participate in the network:
NNDC
NEA-DB
NDS
CJD
CAJaD
CDFE
CNDC
JAEA
JCPRG
ATOMKIUkrNDCCNPD
KAERI/NDELUS National Nuclear Data Center, Brookhaven, USA
OECD/NEA Nuclear Data Bank, Issy-les-Moulineaux,France
IAEA Nuclear Data Section
Centr Jadernykh Dannykh (= Nuclear Data Centre),
Obninsk, Russia
Russian Nuclear Structure and Reaction Data Centre,
Moscow, Russia
Centr Dannykh Fotojadernykh Eksperimentov (= Centre for
Photonuclear Experiments Data), Moscow, Russia
China Nuclear Data Center, Beijing, China
Nuclear Data Center of the Japan Atomic Energy Agency(formerly Japan Atomic Energy Research Institute, JAERI),
Tokai-Mura, Japan
Japan Charged-Particle Nuclear Reaction Data Group,
Hokkaido University, Sapporo, JapanATOMKI Charged-Particle Nuclear Reaction Data Group,
Debrecen, Hungary
Ukrainian Nuclear Data Center, Institute for Nuclear
Research, Kyiv, Ukraine
Center of Nuclear Physics Data, Russian Federal Nuclear
Center, RFNC-VNIIEF, Sarov, Russia
Nuclear Data Evaluation Laboratory, Korea Atomic Energy
Research Institute, Yusong, Taejon, Republic of Korea

A detailed description of the objectives of the network and the contributions of eachCentre to these activities are given in INDC(NDS)-401 (Rev.4), "The Nuclear Reaction
Data Centres Network".
A summary of the network’s objectives, and hyperlinks to all participating centres can befound on the NRDC web page, see http://www-nds.iaea.org/nrdc/.

19

EXFOR Basics

EXFOR Retrieval Websites•

IAEA-NDS, Vienna, Austria (maintains global master file):
http://www-nds.iaea.org/exfor/exfor00.htm•

NNDC (Brookhaven, USA):
http://www.nndc.bnl.gov/exfor/exfor00.htm•

NEA Data Bank (Issy-les-Moulineaux, France):
http://www.nea.fr/html/dbdata/x4/•

CDFE (Moscow, Russia):
http://cdfe.sinp.msu.ru/exfor/index.php•

JCPRG (Sapporo, Japan):
http://www.jcprg.org/exfor/

Citation Guidelines
When citing data extracted from EXFOR, always both, the original reference, and the
EXFOR dataset with its retrieval source should be cited.
Example:A.B. Author, et al., J. Nucl. Phys. 12, 345 (1979). Data taken from the EXFOR
database, file EXFOR 12345.002 dated April 5, 1980, retrieved from the IAEA
Nuclear Data Services website.
To reference the EXFOR database in general, the present report (IAEA-NDS-206, June2008) may be used.

20

EXFOR Basics

II. Overview of the EXFOR Exchange Format
General Structure of the Exchange Format
Nuclear reaction data is exchanged within the EXFOR System on EXFOR exchange files(transmissions), sometimes also called TRANS files.
This section describes the general structure and the general format of an EXFOR
exchange file. More specific information may be found in the following sections.
An exchange file contains a number of entries (works). Each entry is divided into a
number of subentries (data sets). Each entry is assigned an accession number; eachsubentry is assigned a subaccession number (the accession number plus a subentry
number). The subaccession numbers are associated with a data table throughout the lifeof the EXFOR system.
The subentries are further divided into:•••

bibliographic, descriptive and bookkeeping information (hereafter called BIB
information),common data that applies to all data throughout the subentry , anda data table.

The file may, therefore, be considered to be of the following form:

File

Entry

Subentry
Bibliographic
Information
CommonData
Data Table

In order to avoid repetition of information that is common to all subentries within an
entry or to all lines within a subentry, information may be associated with an entire entry
or with an entire subentry. To accomplish this, the first subentry of each work contains
only information that applies to all other subentries. Within each subentry, theinformation common to all lines of the table precedes the table.

21

EXFOR Basics

Two levels of hierarchy are thereby established:

Entry
CommonSubentry

Subentries
Bibliographic
Information
Common Data

Data
Subentry

Bibliographic
Information
Common Data
Data Table

Permitted character set
The following characters are permitted for use in the exchange format:
All Roman characters, A to Z and a to z
All numbers, 0 to 9
The special characters:+ (plus)- (minus). (decimal point/full stop)) (right parenthesis)( (left parenthesis)* (asterisk)/ (slash)= (equals)' (apostrophe), (comma)% (percent)< (less than)> (greater than): (colon)22; (semi-colon)! (exclamation mark)? (question mark)& (ampersand)# (number symbol)[ (opening bracket)] (closing bracket)" (quotation mark)~ (varies as sign)@ (at symbol){ (left curly brace)} (right curly brace)| (vertical bar)

EXFOR Basics

Identification of Files, Entries, and Subentries
In order to track, access, and identify data within the EXFOR Exchange System, thefollowing labelling systems have been adopted for files, entries and subentries.
•

An EXFOR Exchange File is labelled using a four-character file identification(only in files for exchange between data centres, not for user retrievals)•

An entry is labelled using a five-character accession number.

•

A subentry is labelled using an eight-character subaccession number.

Each of these labels includes a center-identification character as the first character inthe string. The table below lists the center-identification characters that have been
assigned. These characters define both the center at which the information was compiled
and the type of data compiled. (Neutron, charged-particle, and photonuclear reaction data
are compiled in separate entries with appropriate identification, even if they werereported in the same reference.)
Center Identification Characters
1

NNDC (Brookhaven)

Neutron nuclear data

2

NEA-DB (Paris)

Neutron nuclear data

3

NDS (Vienna)

Neutron nuclear data, including also compilations from CNDC,
UkrNDC and India

4

CJD (Obninsk)

Neutron nuclear dataA

CAJaD (Moscow)

Charged-particle nuclear data, including also earlier compilations
from CNPD

B

KaChaPaG (Karlsruhe)

Charged-particle nuclear data (extinct centre)

C

NNDC (Brookhaven)

Charged-particle nuclear dataD

NDS (Vienna)

Charged-particle nuclear data, including also compilations fromATOMKI, UkrNDC and IndiaE

JCPRG (Sapporo)

Charged-particle nuclear dataF

CNPD (Sarov)

Charged-particle nuclear dataG

NDS (Vienna)

Photonuclear data, including also compilations from UkrNDC

J

JCPRG (Sapporo)

Charged-particle nuclear data for projectiles with nonpositive baryon
numberK

JCPRG (Sapporo)

Photonuclear data

L

NNDC (Brookhaven)

Photonuclear data

M

CDFE (Moscow)

Photonuclear dataO

NEA-DB (Paris)

Charged-particle nuclear dataP

NNDC (Brookhaven)

Charged-particle nuclear data from MacGowen file

R

RIKEN (Wako, Japan)

Charged-particle nuclear data (extinct centre)

S

CNDC (Beijing)

Charged-particle nuclear dataT

CNPD/NNDC

Charged-particle nuclear dataV

NDS (Vienna)

Special use for selected evaluated neutron data 'VIEN' file (extinct
series)23

EXFOR Basics

EXFOR Records
EXFOR Exchange files consist of 80 character ASCII records. The format of columns 166 varies according to the record type as outlined in the following sections. Columns 6779 is used to uniquely identify a record within the file. The records on the file are inascending order according to the record identification. Column 80 is presently not used.
Record identification. The record identification is divided into three fields: the accession
number (entry), subaccession number (subentry), and record number within the subentry.
The format of these fields is as follows.
Columns 67-71 Center-assigned accession number
72-74 Subaccession number
75-79 Sequence number

System Identifiers
Each of the following basic system identifiers refers to one of the hierarchy of units
contained on an exchange file. Each of the following system identifiers indicates the
beginning of one of these sections.
- A file is the unit
(only on files for exchange between data centres. In user retrieval files
this identifier may be missing or be replaced by another keyword suchas ‘REQUEST’)ENTRY- An entry (work) is the unit
SUBENT- A subentry (data set) is the unit
BIB
- The Bibliographic Information section (hereafter referred to as the
BIB section) of a complete work or sub-work is the unit
COMMON - The Common Data section of a complete work or sub-work is the unit
DATA
- The Data Table section of a sub-work is the unit
TRANS

These basic system identifiers may be combined with the modifiersNO
END
to indicate three conditions:• The beginning of a unit (basic system identifier only)• The end of a unit (modifier END preceding the basic system identifier)• A positive indication that a unit is intentionally omitted (modifier NO preceding thebasic system identifier)
The following system identifiers are defined.
1. A file is:
Headed by:
TRANS
cxxx
yyyymmdd
C = the center-identification character,xxx = 3-digit sequence number for centre-to-centre transmission files,
yyyymmdd = date on which the transmission file was generated.
Ended by:
ENDTRANS N1
N1 = number of entries (accession numbers) on the file.

24

EXFOR Basics

2. An entry is:
Headed by:
ENTRY
N1
N2
N1 = 5-character accession number
N2 = Date of last update (or date of entry if never updated) (yyyymmdd)
Ended by:
ENDENTRY N1
N1 - The number of subentries in the work.
N2 - Presently unused (may be blank or zero).
3. A subentry is:
Headed by:
SUBENT
N1
N2
N1 = 8-character subaccession number (accession number and subentry number).
N2 = Date of last update (or date of entry if never updated) (yyyymmdd).
Ended by:
ENDSUBENT
N1
N1 - The number of records within the subentry.
If a subentry has been deleted, the following record may be included in the file(should appear only on centre-to-centre transmission files):NOSUBENT N1
N2
N1 = 8-character subaccession number.
N2 = Date of last alter.
4. A BIB section is:
Headed by
BIB
N1N2
N1 =Number of information-identifier keywords in the BIB section.
N2 = Number of records in the BIB section.
Ended by :ENDBIB
N1
N1 Number of records in BIB section.
If no BIB section is given the following record is included:
NOBIB
5. A COMMON section is:
Headed by:
COMMON N1
N2
N1 = Number of common data fields.
N2 = Number of records within the common section.
Ended by:
ENDCOMMON
N1
N1 = Number of records within the common section.
If no COMMON section is given, the following record is included:
NOCOMMON
6. A DATA section is:
Headed by:
DATA
N1
N2
N1 = Number of fields (variables) associated with each line of a data table.
N2 = Number of data lines within the table (excluding headings and units).
Ended by:
ENDDATA N1
N1 Number of records within the data section.
If no DATA section is given, the following record is included:
NODATA

25

EXFOR Basics

BIB, COMMON and DATA Sections
BIB Section
The BIB section contains the bibliographic information (e.g., reference, authors),
descriptive information (e.g., neutron source, method, facility), and administrative
information (e.g., history) associated with the data presented. It is identified on an
exchange file as that information between the system identifiers BIB and ENDBIB.
A BIB record consists of three parts:
columns 1-11: information-identifier keyword field,
columns 12-66: information field, which may contain coded information and/or
free text,
columns 67-79: record identification field.
BIB information for a given data set consists of the information contained in the BIB
section of its subentry together with the BIB information in subentry 001. That is,
information coded in subentry 001 applies to all other subentries in the same entry. A
specific information-identifier keyword may be included in either subentry or both.
Information-identifier keywords
The information-identifier keyword is used to define the significance of the information
given in columns 12-66. The keyword is left adjusted to begin in column 1, and does notexceed a length of 10 characters (column 11 is either blank, or contains a pointer, seepage 29).
These keywords may, in general, appear in any order within the BIB section, however, an
information-identifier keyword is not repeated within any one BIB section. If pointers(see page 29) are present, they appear on the first record of the information to which they
are attached and are not repeated on continuation records.
Coded (machine-retrievable) information
Coded information may be used:• to define the actual BIB information,• as a link to the COMMON and DATA section,• to enter associated numerical data.
Coded information is enclosed in parentheses and left adjusted so that the opening
parenthesis appears in column 12. Several pieces of coded information may be
associated with a given information-identifier keyword.
Codes for use with a specific keyword are found in the relevant dictionary. However, forsome keywords, the code string may include retrievable information other than a codefrom one of the dictionaries.

26

EXFOR Basics

In general, codes given in the dictionaries may be used singly or in conjunction with one
or more codes from the same dictionary. Two options exist if more than one code isused:a) two or more codes within the same set of parenthesis, separated by a comma;
Example: (SOLST,NAICR)b) each code on a separate record, enclosed in it's own set of parenthesis starting incolumn 12, followed by free text.
Example: (SOLST) free text
(NAICR) free text
For some cases, the information may be continued onto successive records. Informationon continuation records does not begin before column 12 (columns 1-10 are blank andcolumn 11 is blank or contains a pointer).
Note that some information-identifier keywords have no coded information associatedwith them and that, for many keywords that may have coded information associated withthem, it need not always be present.
Free text
Free text may be entered in columns 12-66 under each of the information-identifier
keywords in the BIB section. The text follows any coded information on the record or
may begin on a separate record; it may be continued onto any number of records.
The language of the free text is English.

COMMON and DATA Sections
A data table is, generally, a function of one or more independent variables, e.g.,•••

X vs. Y, e.g., energy, cross section
X, X′ and Y, e.g., energy and angle; differential cross section
X, X′ and X″ vs. Y, e.g., energy, secondary energy, angle, partial angular distribution.

When more than one representation of Y is present, the table may be X vs. Y and Y′, withassociated errors for X, Y and Y′ (e.g., X = energy, Y = absolute cross section, Y′ = relative
cross section), and possible associated information. The criteria for grouping Y with Y′ arethat they both be derived from the same experimental information by the author of the data.
For some data, the data table does not have an independent variable X but only a function Y.
(Examples: Spontaneous⎯ν; resonance energies without resonance parameters)
Additional variables may be associated with the data, e.g., errors, standards.
The format of the common data (COMMON) and data table (DATA) sections is
identical. Each section is a table of data containing the data headings and units associatedwith each field. The difference between the common data and data table is:•

The common data contains constant parameters that apply to each line of a point datatable;

27

EXFOR Basics•

The data table contains fields of information; each field, generally, contains values asa function of one or more independent variables (e.g., angle, angular error, crosssection, cross section error), i.e., one or more lines of data.

Each physical record may contain up to six information fields, each 11 columns wide. If
more than six fields are used, the remaining information is contained on the following
records. Therefore, a data line consists of up to three physical records. The number offields in a data line is restricted to 18.
Records are not packed; rather, individual point information is kept on individual
records; i.e., if only four fields are associated with a data line, the remaining two fields
are left blank, and, in the case of the data table, the information for the next line begins
on the following record. These rules also apply to the headings and units associated witheach field.
The content of the COMMON and DATA sections are as follows:•

Field headings: a data heading left adjusted to the beginning of each field (columns 1,
12, 23, 34, 45, 56), plus, perhaps, a pointer placed in the last (11th) column of a field.

•

Data units: left adjusted to the beginning of each field (columns 1, 12, 23, 34, 45, 56).

•

Numerical data: FORTRAN-readable using a floating-point format, as follows.
• A decimal point is always present, even for integers.
• A decimal number without an exponent can have any position within the 11character field.
• No blank is allowed following a sign (+ or -).
• A plus sign may be omitted, except that of an exponent when there is no E.
• In an exponential notation, the exponent is right adjusted within the 11-character
field. The mantissa may have any position.

The values are either zero or have absolute values between 1.0000E-38 and 9.999E+38.
COMMON Section
The COMMON section is identified as that information between the system identifiers
COMMON and ENDCOMMON. In the common data table, only one value is entered
for a given field, and successive fields are not integrally associated with one another.
An example of a common data table with more than 6 fields:
1
COMMONEN
MONIT-ERR
MEV
MB
2.73
0.123
ENDCOMMON

28

12

23

34

45

56

EN-ERR

EN-RSL

E-LVL

E-LVL

MONIT

MEV

MEV

MEV

MEV

MB

0.02

0.05

2.73

2.78

3.456

66

EXFOR Basics

DATA Section
The DATA section is identified as that information between the system identifiers DATA
and ENDDATA. In the DATA table, all entries on a record are integrally associated withan individual point. Independent variables precede dependent variables, and aremonotonic until the value of the preceding independent variable, if any exist, changes.
Every line in a data table gives data information. This means, for example, that a blankin a field headed DATA is permitted only when another field contains the data
information on the same line, e.g., under DATA-MAX. In the same way, eachindependent variable occurs at least once in each line (e.g., either under data headings ELVL or E-LVL-MIN, E-LVL-MAX, see example below). Supplementary information,such as resolution or standard values, is not given on a line of a data table unless the line
includes data information. Blanks are permitted in all fields.
An example of a point data table is shown below with its associated DATA and ENDDATA
records.
1
DATA
ANG
ADEG
10.7
22.9
39.1
46.7
ENDDATA

12

23

34

45

ANG-ERR
ADEG
1.8
1.2
0.9
0.7

DATA
MB/SR
138.
127.

DATA-ERR
MB/SR
8.5
4.2

DATA-MAX
MB/SR

56

66

83.2
14.8

2.9

Pointers
Different pieces of EXFOR information may be linked together by pointers. A pointer isa numeric or alphabetic character (1,2...9,A,B,...Z) placed in the eleventh column of theinformation-identifier keyword field in the BIB section and in the field headings in the
COMMON or DATA section.
Pointers may link, for example,• one of several reactions with its data field;• one of several reactions with a specific piece of information in the BIB section (e.g.,
ANALYSIS), and/or with a value in the COMMON section, and/or with a field in the
DATA section;• a value in the COMMON section with any field in the DATA section.
In general, a pointer is valid for only one subentry. A pointer used in the first subentry
applies to all subentries and has a unique meaning throughout the entire entry.
Pointers applied to a BIB keyword appear on the first record of the information to which
they are attached and are not repeated on continuation records. A pointer is assumed torefer to all BIB information until either another pointer or a new keyword is encountered.
As this implies, pointer-independent information for each keyword appears first.

29

EXFOR Basics

Nuclide and reaction specification
Coding of nuclides and compounds
Nuclides appear in the coding of many keywords. The general code format is Z-S-A-X,
where:
Z is the charge number; up to 3 digits, no leading zeros
S is the element symbol; 1 or 2 characters
A is the mass number; up to 3 digits, no leading zeroes. A single zero denotes
natural isotopic composition.
X is an isomer code denoting the isomeric state; this subfield is not used if there are
no known isomeric states.
X may have the following values:Gfor ground state (of a nucleus which has a metastable state; may
sometimes be omitted)M
if only one metastable state is regarded
M1
for the first metastable stateM2
for the second, etc.
L
if only one quasi-metastable state 1 is regarded
L1
for the first quasi-metastable state, etc.
Tfor sum of all isomers (limited to use within an isomeric ratio in SF4 ofthe reaction string)
Examples: 92-U-235
49-IN-115-M/T
Compounds may in some cases replace the nuclide code. The general format for coding
compounds is either the specific compound code, taken from a special compounds
dictionary, or the general code for a compound of the form Z-S-CMP. The element codedis the major component of the compound.
Examples:26-FE-CMP
1-H-WTR

Iron compound (details given in free text)
Water

Reaction Specification
The reaction and quantity for the data coded in the data table is specified using the informationidentifier keyword REACTION, therefore, this keyword must always be present in a data set. The
keyword REACTION defines the data given in the DATA section under the heading DATA or asimilar heading such as DATA-MIN, DATA-MAX, etc. The general format of the code is(reaction, quantity, data-type).

1

These are states with a measurable half-life of less than 0.1 seconds

30

EXFOR Basics

Reaction field. The reaction field consists of 4 subfields.
SF1. Target nucleus. Contains either:a) a nuclide code.
A = 0 denotes natural isotopic mixture-G for ground state is not used in this fieldb) a compound codec) a variable nucleus code ELEM and/or MASS
Example: (ELEM/MASS(0,B-),,PN)
SF2. Incident projectile. Contains one of the following:a) a particle code from Dictionary 33b) for particles heavier than an α, a nuclide code.
SF3. Process. Contains one of the following:a) a process code from Dictionary 30, e.g., TOT.
b) a particle code from Dictionary 33 which may be preceded by a multiplicity
factor, whose value may be 2→99, e.g., 4A.
c) for particles heavier than α, a nuclide code.
Examples: 8-O-16
8-O-16+8-O-16d) combinations of a), b) and c), with the codes connected by ‘+’.
Examples:HE3+8-0-16
X+N
If SF5 contains the branch code (DEF) (it is not evident from the publication whether thereaction channel is undefined or defined), the particle codes given in SF3 may represent
only the sum of emitted nucleons, implying that the product nucleus coded in SF4 has
been formed via different reaction channels.
SF4. Reaction Product. In general, the heaviest of the products is defined as the reaction
product (also called residual nucleus). In the case of two reaction products with equal
mass, the one with the larger Z is considered as the heavier product. Exceptions or
special cases are:•If SF5 contains the code SEQ, indicating that the sequence of several outgoingparticles and/or processes coded in SF3 is meaningful, the nuclide to be coded in SF4
is the heaviest of the final products.
Example:•(5-B-10(N,A+T)2-HE-4,SEQ,SIG)

Where emission cross sections, production cross sections, product yields, etc., aregiven for specified nuclides, particles, or gammas, the product considered is definedas the reaction product (even if it is not the heaviest of several reaction products).

This subfield contains:• either a blank (if the product is not defined, as for sum reactions such as
absorption or total, or for resonance parameters)
Example: (26-FE-56(N,EL),,WID)

31

EXFOR Basics•

or a nuclide code
Examples: (51-SB-123(N,G)51-SB-124-M1+M2/T)(28-NI-0(N,X)0-G-0,,SIG) γ production cross section(for total production of gammas or light particles, the particles are written
in SF4 using the Z-S-A formalism)•or, a variable nucleus code:
Example: (92-U-235(N,F)ELEM/MASS,CUM,FY)(Z and A of the various products are given in the DATA table under theheadings ELEMENT and MASS.)•or, if the number of particles emitted is entered into the data table using the data
heading PART-OUT, it contains the code NPART.
Example: (79-AU-197(92-U-238,X)NPART,NUM,SIG,HF) Cross
section for a given number of heavy fragments emitted; the number offragments is given in the DATA section under the heading PART-OUT.

Quantity consists of four subfields, each separated by a comma. All combinations ofcodes allowed in the quantity field are given in Dictionary 236.
SF5 Branch. Indicates a partial reaction, e.g., to one of several energy levels.
SF6 Parameter. Indicates the reaction parameter given, e.g., differential cross section.
SF7 Particle Considered. Indicates to which of several outgoing particles the quantity
refers. 2 When more than one particle or nuclide is entered, they are separated by a slash;
if they are correlated particles, they are separated by a plus sign.
SF8 Modifier. Contains information on the representation of the data, e.g., relative data.
Data Type Field. Indicates whether the data are experimental, theoretical, evaluated, etc.
Codes are found in Dictionary 35. The default value is ‘experimental’, therefore this fieldis very often omitted.
Variable Nucleus. For certain processes, the data table may contain yield or production
cross sections for several nuclei which are entered as variables in the data table. In thiscase, either SF1 or SF4 of the REACTION keyword contain one of the following codes:
ELEM- if the Z (charge number) of the nuclide is given in the data table.
MASS- if the A (mass number) of the nuclide is given in the data table.
ELEM/MASS - if the Z and A of the nuclide are given in the data table.
The nuclei are entered in the common data or data table as variables under the data
headings ELEMENT and/or MASS with the units NO-DIM.

2

Note that the particle considered is not necessarily identical to the particle detected, e.g., the angular
distribution of an outgoing particle which has been deduced from a recoil particle detected.

32

EXFOR Basics

If the data headings ELEMENT and MASS are used, a third field with the data heading
ISOMER is used when isomer states are specified:
0. = ground state (used only if nuclide has also an isomeric state),
1. = first metastable state (or the metastable state when only one is known),
2. = second metastable state, etc.
Decay data for each entry under ELEMENT/MASS(ISOMER) and their related parent ordaughter nuclides may be given in the usual way under the information-identifier
keyword DECAY-DATA. Entries under the data headings ELEMENT/MASS(ISOMER) arelinked to entries under DECAY-DATA (and RAD-DET, if present) by means of a decay
flag. 3
Example:BIB
REACTION
DECAY-DATA
ENDBIBNOCOMMON
DATA
EN
MEV

…
…
…
…

(…(…,F)ELEM/MASS,IND,FY)((1.)60-ND-138,5.04HR,DG,328.,0.65)((2.)60-ND-141,2.49HR,DG,……………………)

ELEMENTNO-DIM
60.
60.
61.
61.
61.
62.

MASS
NO-DIM
138.
140.
148.
148.
149.
149.

ISOMER
NO-DIM

0.
1.

DATA
PC/FIS…
…
…
…
…
…

DECAY-FLAG
NO-DIM
1.
2.

Variable Number of Emitted Particles
If the data table contains yields or production cross sections as a function of the numberof secondary particles, and the number of particles is entered as a variable in the datatable, SF4 of the REACTION keyword contains the code NPART, SF5 contains the code
NUM, and SF7 contains the particle considered.
Example:BIB
REACTION…
ENDBIBNOCOMMON
DATA
EN
MEV
…
…
…
ENDDATA3(…(…,X)NPART,NUM,P)

PART-OUT
NO-DIM

DATA
B

If the half-life is the only decay data given, this may be entered in the data table under the data heading

HL, although this is not recommended.

33

EXFOR Basics

Reaction Combinations. For experimental data sets referring to complex combinationsof materials and reactions, the code units defined in this section can be connected into asingle machine-retrievable field, with appropriate separators and properly balanced
parentheses. The complete reaction combination is enclosed in parentheses.
The following reaction combinations are defined:((------)+(-----))((------)-(-----))((------)*(-----))((------)/(-----))((------)//(-----))((------)=(-----))

Sum of 2 or more quantities.
Difference between 2 or more quantities.
Product of 2 or more quantities.
Ratio of 2 or more quantities.
Ratio of 2 quantities, where the numerator and denominator
refer to different values for one or more independent variables.
Tautologies.

When a reaction combination contains the separator "//", the data table will contain atleast one independent variable pair with the data heading extensions -NM and -DN.
Example:BIB
REACTIONRESULT…
ENDBIB
COMMONEN-DUM-NM
MEV
1.0
ENDCOMMONDATAELEMENT…
ENDDATA34(((92-U-238(N,F)ELEM/MASS,CUM,FY,,FIS)/(92-U-238(N,F)42-MO-99,CUM,FY,,FIS))//((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/(92-U-235(N,F)42-MO-99,CUM,FY,,MXW)))(RVAL)

EN-DUM-DN
EV
0.0253MASS

DATA

EXFOR Basics

Information Identifier Keywords
This section provides a listing of all information-identifier keywords, along with details
about their use. The keywords appear in alphabetical order.
ADD-RES. Gives information about any additional results obtained in the experiment,
but which are not compiled in the data tables. Codes are given in Dictionary 20.
Example: ADD-RES(RANGE) Range of recoils measured.
ANALYSIS. Gives information as to how the experimental results have been analyzed
to obtain the values given under the heading DATA which actually represent the results of
the analysis. Codes are found in Dictionary 23.
Example: ANLAYSIS (MLA) Breit-Wigner multilevel analysis
ASSUMED Gives information about values assumed in the analysis of the data, andabout COMMON or DATA fields headed by ASSUM or its derivatives. The format of
the code is:(heading,reaction,quantity)
Heading field: data heading to be defined.
Reaction field and quantity field: coded as under the keyword REACTION.
Example:ASSUMED(ASSUM,6-C-12(N,TOT),,SIG)

AUTHOR. Gives the authors of the work reported.
Example:AUTHOR (R.W.McNally Jr,A.B.JONES)COMMENT. Gives pertinent information which cannot logically be entered under any
other of the keywords available.
CORRECTION. Gives information about corrections applied to the data in order toobtain the values given under DATA.
COVARIANCE. Gives covariance information provided by the experimentalist, or to
flag the existence of a covariance data file. See page 44 for covariance file format.
Example: COVARIANCE (COVAR) Covariance file exists and may
be obtained on request.

35

EXFOR Basics

CRITIQUE. Gives comments on the quality of the data presented in the data table.
DECAY-DATA. Gives the decay data for any nuclide occurring in the reaction
measured as assumed or measured by the author for obtaining the data given 4 . The
general format of the coding string consists of three major fields which may be precededby a decay flag:((decay flag)nuclide,half-life,radiation).
Flag. A fixed-point number that also appears in the data section under the data heading
DECAY-FLAG. If the flag is omitted, its parentheses are also omitted.
Nuclide field. A nuclide code. For ground states, the use of the extension G is optional.
Half-life field. The half-life of the nuclide specified, coded as a floating-point number,
followed by a unit code with the dimension of TIME.
Radiation field. Consists of three subfields: (type of radiation, energy, abundance).
This field may be omitted, or repeated (each radiation field being separated by acomma). The absence of any subfield is indicated by a comma; trailing commas are notincluded.
SF1. Type-of-radiation. A code from Dictionary 33. Where two or moredifferent decay modes are possible and are not distinguished in the measurement,
two or more codes are given; each separated by a slash. (See Example b below).
SF2. Energy. The energy of the radiation in keV, coded as a floating-point
number. In the case of two or more unresolved decays, two or more energies, or alower and upper energy limit, are given, each separated by a slash. (See Examplee).
SF3. Abundance. The abundance of the observed per decay, coded as a floatingpoint number.
Examples(radiation field omitted)a) DECAY-DATA(60-ND-140,3.3D)b) DECAY-DATA(59-PR-140,,B+/EC,,0.500) (half-life and decayenergy omitted)c) DECAY-DATA(25-MN-50-G,0.286SEC,B+,6610.)(abundance omitted)d) DECAY-DATA((1.)60-ND-138,5.04HR,DG,328.,0.065)(decay flag, all fields present)e) DECAY-DATA(60-ND-139-M,5.5HR,DG,708./738.,0.64)(the abundance given is the total abundance of both γ rays)

4

Decay data relevant to the monitor reaction are coded under the keyword DECAY-MON and not under

DECAY-DATA.

36

EXFOR Basicsf) DECAY-DATA(60-ND-139-G,30.0MIN,B+,,0.257,
DG,405.,0.055)(60-ND-139-M,5.5HR,DG,738.,0.37,
DG,982.,0.29,
DG,708.,0.27,
DG,403.,0.03,
B+,,0.006)

DECAY-MON. Gives the decay data assumed by the author for any nuclide occurringin the monitor reaction used. The coding rules are the same as those for DECAY-DATA,
except that, instead of the flag field, there may be a heading field which links the data to
the heading of the monitor value, if more than one monitors are given.
Example:DECAY-MON((MONIT1)26-SC-46-G,83.81D,DG,889.3,0.99984,
DG,1120.5,0.99870)((MONIT2)26-SC-47,3.345D,DG,159.4,0.683)

DETECTOR. Gives information about the detector(s) used in the experiment. Codes
are found in Dictionary 22. If the code COIN is used, then the codes for the detectors usedin coincidence follow within the same parenthesis;
Example:DETECTOR (COIN,NAICR,NAICR)

Similarly, the code PS (position-sensitive detector) will be followed by a specificdetector code.
EN-SEC. Gives information about secondary energies, and to define secondary-energy
fields given in the data table. The format of the coded information is: (heading,particle).
Heading Field. Contains the data heading or the root of the data heading to be
defined.
Particle Field. Contains the particle or nuclide to which the data heading refers.
The code is:eithera particle code from Dictionary 13.
ora nuclide code.
Example:EN-SEC(E1,G)(E2,N)(E-EXC,3-LI-7)

ERR-ANALYS. Explains the sources of uncertainties and the values given in the
COMMON or DATA sections under data headings of the type ERR- or -ERR. The generalcode format is(heading,correlation factor) free text37

EXFOR Basics

Heading Field. Contains the data heading or the root 5 of the data heading to be
defined.
Correlation Factor Field contains the correlation factor, coded as a floating point
number.
Example:BIB…
ERR-ANALYS(EN-ERR) followed by explanation of energy error(ERR-T) followed by explanation of total uncertainty(ERR-S)followed by explanation of statistical uncertainty

EXP-YEAR. Defines the year in which the experiment was performed when it differs
significantly from the data of the references given (e.g., classified data publishedyears later).
Example:EXP-YEAR (1965)

FACILITY. Defines the main apparatus used in the experiment. The facility code from
Dictionary 18 may be followed by an institute code from Dictionary 3, which
specifies the location of the facility.
Example:FACILITY (CHOPF,1USACOL)(SPECC,1USABNL)

FLAG. Provides information to specific lines in a data table, similar to a footnote.
Example:BIB…
FLAGENDBIB
…
DATA
EN
KEV
1.2
2.3
3.4
ENDDATA(1.) Data averaged from 2 runs
(2.) Modified detector used at this energy

DATA
MB
123.
234.
456.

FLAG
NO-DIM
1.
2.

HALF-LIFE. Gives information about half-life values and defines half-life fields givenin the data table. The general coding format is: (heading,nuclide)
Example:5

HALF-LIFE(HL1,41-NB-94-G)(HL2,41-NB-94-M)

Root means that the data heading given also defines the heading preceded by + or -.

38

EXFOR Basics

HISTORY. Documents the handling of an entry or subentry. The general format of thecode is: (yyyymmddX), where yyyymmdd is the date (year,month,day) and X is a codefrom Dictionary 15.
Example:HISTORY(19940312C)(19960711A) Data units corrected.

INC-SOURCE. Gives information on the source of the incident particle beam used in
the experiment. Codes are found in Dictionary 19.
Example:INC-SOURCE
INC-SOURCE(POLNS,D-T)(MPH=(13-AL-27(N,A)11-NA-24))

INC-SPECT. Provides free text information on the characteristics and resolution of theincident-projectile beam.
INSTITUTE. Designates the laboratory, institute, or university at which the experiment
was performed, or with which the authors are affiliated. Codes are given in Dictionary 3.
Examples: INSTITUTEINSTITUTE(1USAGA, 1USALAS)(2FR SAC)LEVEL-PROP. Gives information on the spin and parity of excited states. The generalformat of the code is((flag) nuclide, level identification, level properties)
Flag. Coded as a fixed-point number that appears in the data section under the data
heading LVL-FLAG. When the flag is omitted, its parentheses are also omitted.
Nuclide. Coded is a nuclide, except that the use of the extension G is optional.
Level identification. Identification of the level whose properties are specified, given
as either a level energy or level number. If the field omitted, its separating comma isomitted.
Level Energy. The field identifier E-LVL= followed by the excited state energy in
MeV, coded as a floating-point number which also appears in the data section
under the data heading E-LVL.
Level Number. The field identifier LVL-NUMB= followed by the level number ofthe excited state, coded as a fixed-point number which also appears in the data
section under the data heading LVL-NUMB.
Isobaric analog state number. The level identifier IAS-NUMB= followed by thelevel number of the isobaric analog state, n, where n has a numerical value which
also appears in the data section under the data heading IAS-NUMB.
Level properties. Properties for the excited state, each preceded by a subfield
identification. At least one of the subfields must be present.
Spin. The field identifier SPIN=, followed by the level spin coded as a floating
point number. For an uncertain spin assignment, two or more spins may be given,each separated by a slash.
Parity. The field identifier PARITY=, followed by the level parity, coded as e.g.,+1. or -1.
39

EXFOR Basics

Examples:LEVEL-PROP (82-PB-206,E-LVL=0.,SPIN=0./1.,PARITY=+1.)(82-PB-206,E-LVL-1.34,SPIN+3.,PARITY=+1.)
LEVEL-PROP ((1.)82-PB-206,,SPIN=0./1.,PARITY=+1.)((2.)82-PB-206,,SPIN=3.,PARITY=+1.)
LEVEL-PROP (82-PB-207,LVL-NUMB=2.,SPIN=1.5,PARITY=-1)

METHOD. Describes the experimental technique(s) employed in the experiment.
Codes are found in Dictionary 21.
Example:METHOD(RCHEM) Radiochemical separation

MISC-COL. Defines fields in the COMMON or DATA sections headed by MISC and its
derivatives.
Example:MISC-COL (MISC1)(MISC2)

Free text describing 1st miscellaneous field
Free text describing 2nd miscellaneous field

MOM-SEC. Gives information about secondary linear momentum, and defines
secondary-momentum fields given in the data table. The general code format is:(heading,particle)
Heading Field: the data heading or root 6 of the data heading to be defined.
Particle Field: the particle or nuclide to which the data heading refers. The code is:either a particle code from Dictionary 33.
ora nuclide code.
Example:MOM-SEC(MOM-SEC1,26-FE-56)(MOM-SEC2,26-FE-57)

MONITOR. Gives information about the standard reference data (standard, monitor)
used in the experiment and defines information coded in the COMMON and DATA
sections under the data heading MONIT, etc. The general coding format is ((heading)reaction)
Heading Field. Contains the data heading of the field in which the monitor value isgiven. If the heading is omitted, its parenthesis is omitted.
Reaction Field. The coding rules are identical to those for REACTION, except that
subfields 5 to 9 may be omitted when only the reaction is known.
Example:MONITOR(92-U-235(N,F),,SIG)

If more than one monitor is given, they are linked to the respective columns in the
COMMON or DATA section either with pointers, or using the heading field.

6

Root means that the data heading given will also define the same heading followed by -MIN, -MAX or -

APRX.

40

EXFOR Basics

Example:MONITOR ((MONIT1)1-H-1(N,EL),,SIG)((MONIT2)13-AL-27(N,A)11-NA-24,,SIG))
MONIT-REF. Gives information about the source reference for the standard (ormonitor) data used in the experiment.
The general code format is((heading)subaccession#,author,reference)
Heading Field: Data heading of the field in which the standard value is given. If theheading is omitted, its parentheses are also omitted.
Subaccession Number Field: Subaccession number for the monitor data, if the data isgiven in an EXFOR entry. Cnnnn001 refers to the entire entry; Cnnnn000 refers to a yet
unknown subentry. This field may be omitted.
Author Field. The first author, followed by "+" when more than one author exists.
Reference Field. May contain up to 6 subfields, coded as under REFERENCE. References
to evaluated data libraries are coded(…,3,code-version,,date) or(…,3,code-version,MAT-number,date)with a code from Dictionary 144 (Data Libraries).
Examples:MONIT-REF ((MONIT1)BOO17005,J.GOSHAL,J,PR,80,939,1950)((MONIT2),A.G.PANONTIN+,J,JIN,30,2017,1968)
MONIT-REF (,L.W.Weston+,3,JEFF-3.1,9228,2005)

PART-DET. Gives information about the particles detected directly in the experiment.
Particles detected in a standard/monitor reaction are not coded under this keyword. The
code is either a code from Dictionary 33, or, for particles heavier than α particles, anuclide code. Particles detected pertaining to different reaction units within a reaction
combination are coded on separate records in the same order as the corresponding
reaction units.
Example:PART-DET (A)PART-DET (3-LI-6)

RAD-DET. Gives information about the decay radiations (or particles) and nuclides
observed in the reaction measured. The general format of the code is((flag)nuclide, radiation).
Flag is a fixed-point number which appears in the data section under the data heading
DECAY-FLAG. If the field is omitted, its parentheses are also omitted.
Nuclide contains a nuclide code.
Radiation contains one or more codes from Dictionary 33, each separated by acomma.

41

EXFOR Basics

Examples:RAD-DETRAD-DETRAD-DET(25-MN-52-M,DG,B+)(48-CD-115-G,B-)(49-IN-115-M,DG)((1.)48-CD-115-G,B-)((2.)49-IN-115-M,DG)

REACTION. Specifies the data presented in the DATA section in fields headed by
DATA or a similar heading such as DATA-MAX, DATA-MIN. See preceding Chapter
for details.
REFERENCE. Gives information on references that contain information about the datacoded. Other related references are not coded under this keyword (see REL-REF, MONITREF). The general coding format is(reference type, reference, date).
The format of the reference field is dependent on the reference type. The general format
for each reference type follows.
Type of Reference = B or C: Books and Conferences.
General code format: (B or C,code,volume,(part),page(paper #),date).
Codes from Dictionary 7 (Conferences) or 207 (Books).
Examples:(C,67KHARKOV,,(56),196702)
Kharkov Conference Proceedings, paper#56, February 1967.
(C,66WASH,1,456,196603) Washington Conference Proceedings, Volume 1,
page 456, March 1966
(B,ABAGJAN,,123,1964) Book by Abagjan, page 123, published in 1964.
Type of Reference = J or K: Journals or Journal Abstracts.
General code format is (J,code,volume,(issue #),page,date).
Codes are from Dictionary 5.
Examples:(J,PR,104,1319,195612) Phys. Rev. Volume 104, page 1319, Dec. 1956
(J,XYZ,5,(2),89,196602) Journals XYZ, Volume 5, issue #2, page 89,
February 1966
Type of Reference = P or R or S: Reports (Progress, Lab, Conference Reports)
General code format: (P or R or S,code-number,date). Codes from Dictionary 6.
Examples:(R,JINR-P-2713,196605) Dubna report, series P, number 2713, May 1966.
(P,WASH-1068,185,196603) WASH progress report number 1068, page 185,
March 1966.
Type of Reference = T, or W or X: Thesis or Private Communication or Preprint
General code format:(W or T or X,author,page,date)42

EXFOR Basics

The page field may be omitted, in which case the following comma is also omitted.
Examples:(W,BENZI,19661104)
private communication from Benzi, November 4, 1966.
(T,ANONYMOUS,58,196802) thesis by Anonymous, page 58, February 1968.
REL-REF. Gives information on references related to, but not directly pertaining to, thework coded. The general code format is:(code,subaccession#,author,reference).
Code: code from Dictionary 17.
Subaccession #: EXFOR subaccession number for the reference given, if it exists.
Cnnnn001 refers to the entire entry Cnnnn. Cnnnn000 refers to a yet unassigned
subentry within the entry Cnnnn.
Author: first author, coded as under AUTHOR, followed by + when more than one
author exists.
Reference: coded as for REFERENCE.
Example:(C,B9999001,A.B.NAME+,J,XYZ,5,(2),90,197701)
Criticalremarks by A.B.Name, et al., in journal XYZ,
volume 5, issue #2, p. 90, January 1977.
RESULT. Describes commonly used quantities that are coded as REACTION
combinations. Codes from Dictionary 37.
Example:REACTION ((Z-S-A(N,F)ELEM/MASS,CUM,FY)/(Z-S-A(N,F)MASS,CHN,FY))RESULT(FRCUM)SAMPLE. Used to give information on the structure, composition, shape, etc., of themeasurement sample.
STATUS. Gives information on the status of the data presented. Entered in one of thegeneral code formats, or, for cross reference to another data set, the general code format
is: (code,subaccession#)
Code: code from Dictionary 16.
Subaccession# Field: cross-reference to an EXFOR subaccession number.
Example:STATUS (SPSDD,10048009) - this subentry is superseded by subentry 10048009.

TITLE. Gives the title for the work referenced.

43

EXFOR Basics

Covariance Data File Format
Covariance data may be stored on a separate covariance file. This is mandatory ifa) the file is too big to be included conveniently as free text within the EXFOR entry (under
the keyword COVARIANCE); and/orb) the file is in a format which does not fit within columns 12 - 66 available for free text (e.g.
ENDF-6 File 33 format).
The covariance file is named
aaaaasss.cov
with aaaaa being the accesssion number, sss the subentry number of the corresponding
subentry (e.g. 35001002.cov).
There are three record types in the covariance file:• comment records,• data records,• end records.
The actual covariance data can be given either in a free format, defined in the comment
records, or in ENDF-6 File 33 format. In the latter case, the cross section may be included
also (in File 3 format) for easy processing.

Comment record format
Column1
2–9
10
11 - 80

C
Data set number (subaccession number)(blank)Comment which includes covariance type and format

Data record formata) Free format:
Column
1
2 -9
10
11 - 80

44

D
Data set number (subaccession number)(blank)Data in format given on comment record

EXFOR Basicsb) ENDF 6 File 3/33 format:
First record:
Column
1
2 -9
10
11 - 1415
16 - 25
26 - 80
Following records:
Column1 - 80F
Data set number (subaccession number)(blank)
MAT number used(blank)File numbers given, separated by commas (e.g. 3,33)
Comment
As in ENDF-6

End record format
Column1
2 -9
10 - 80

E
Data set number (subaccession number)(blank)Example 1: Covariance data in free format as defined in comment records
C10034002
C10034002
C10034002
C10034002
D10034002
D10034002
D10034002
D10034002
D10034002
D10034002
E10034002

Values given only for elements below diagonal ofsymmetric matrix on same energy grid as data
format.
FORMAT(9E5.2)
1.0
0.98 1.0
0.90 0.97 1.0
0.70 0.82 0.93 1.0
0.54 0.68 0.83 0.96 1.0
0.64 0.75 0.85 0.92 0.95 1.0

45

EXFOR Basics

Example 2: Cross section and Covariance data in ENDF-6 File 3/33 format
C35001002 Covariance file for subentry 35001002
C35001002 The file is in ENDF File 33 format, also cross section as File 3
F35001002 6210 3,33
Cross section and covariances in ENDF-6 format
0.000000+0 0.000000+000006210 0 06.215100+4 1.496234+200006210 3102
8.256831+6 8.256831+6001316210 3102
31
26210 3102
0.110000+4 0.244474+2 0.135000+4 0.236065+2 0.162500+4 0.218757+26210 3102
0.187500+4 0.196988+2 0.225000+4 0.153861+2 0.275000+4 0.153043+26210 3102
0.350000+4 0.127367+2 0.450000+4 0.100073+2 0.625000+4 0.865960+16210 3102
0.875000+4 0.656557+1 0.112500+5 0.501474+1 0.137500+5 0.457034+16210 3102
0.175000+5 0.387133+1 0.225000+5 0.394818+1 0.275000+5 0.314252+16210 3102
0.350000+5 0.258191+1 0.450000+5 0.232481+1 0.550000+5 0.184880+16210 3102
0.700000+5 0.157094+1 0.900000+5 0.117749+1 0.110000+6 0.997426+06210 3102
0.135000+6 0.992993+0 0.162500+6 0.757935+0 0.187500+6 0.734009+06210 3102
0.225000+6 0.678500+0 0.275000+6 0.492988+0 0.350000+6 0.418481+06210 3102
0.450000+6 0.372564+0 0.550000+6 0.284066+0 0.700000+6 0.247658+06210 3102
0.900000+6 0.194466+0 0.000000+0 0.000000+0 0.000000+0 0.000000+06210 3102
0.000000+0 0.000000+000006210 0 06.215100+4 1.496234+20000621033102
0.000000+0 0.000000+00100621033102
0.000000+0 0.000000+0
1
5528
32621033102
0.100000+4 0.120000+4 0.150000+4 0.175000+4 0.200000+4 0.250000+4621033102
0.300000+4 0.400000+4 0.500000+4 0.750000+4 0.100000+5 0.125000+5621033102
0.150000+5 0.200000+5 0.250000+5 0.300000+5 0.400000+5 0.500000+5621033102
0.600000+5 0.800000+5 0.100000+6 0.120000+6 0.150000+6 0.175000+6621033102
0.200000+6 0.250000+6 0.300000+6 0.400000+6 0.500000+6 0.600000+6621033102
0.800000+6 0.100000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0621033102……………..
………………
0.300769-2 0.190133-2 0.194659-2 0.199179-2 0.196701-2 0.199724-2621033102
0.208640-2 0.362495-2 0.197938-2 0.202161-2 0.201359-2 0.205954-2621033102
0.216937-2 0.302796-2 0.208438-2 0.207471-2 0.212723-2 0.225324-2621033102
0.345695-2 0.212488-2 0.218017-2 0.231748-2 0.376135-2 0.218460-2621033102
0.232702-2 0.326855-2 0.242255-2 0.444583-2
0.000000+0 0.000000+000006210 0 0
E 35001002

46

0
1
2
3
4
5
6
7
8
9
10
11
12
13
14
15
16
17
18
19
20
21
22
23
24

103
104
105
106
107
108

EXFOR Basics

III. User Output Formats

This chapter describes the various output formats available to users who retrieve EXFOR
data. Not all formats mentioned here are necessarily available from all EXFOR sites, andsome data centres may offer additional formats not described here.

•

EXFOR Exchange format: available from all EXFOR sites. Described in general in
Chapter I and in more detail in Chapter II.

•

EXFOR+ format: Interpreted EXFOR. User friendly output for human reader. See
examples in Chapter I. Will be refined further to give expanded output for more
keywords.

•

Computational format C4. This is the format mainly in use for plotting andprocessing EXFOR data. See following pages for a description

Merely as an illustration, examples of other user output formats are shown also, on pages 54
ff. Since these are not part of the NRDC exchange agreements and are not necessarily
available from all EXFOR centres, they are not described in detail. The examples included
here are:
•
•
•
•
•

Tabular formats:
 T4
 TABLE with XREF and BIB
R33 format (for Ion Beam Analysis community)
Extended C4 computational format
Bibliographic output
Plots

47

EXFOR Basics

Computational Format C4This is the computational format mainly in use for plotting and processing of EXFOR data,
which is available from IAEA-NDS and some of the other data centres. Its main features aredescribed below.
(The following is an edited extract from: Dermott E. Cullen and Andrej Trkov, “Program
X4TOC4”, report IAEA-NDS-80, Rev.1, March 2001)
The C4 computation format 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 ispossible 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 to the table oriented EXFOR format).
Each line of the computation format represents a single data point. This makes it possible to sort datain the computation format into any desired order for use in application, e.g., sort 26-Fe-26 (n,2n) datafrom a number of measurements together into energy order to simplify comparisons.
Relationship to ENDF
It is assumed that one of the major uses of this format will be to prepare data for subsequent use inevaluation 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 amanner similar to ENDF data 7 .
In particular the EXFOR classification of data by the EXFOR keyword REACTION is replaced byclassifying 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 tobe 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 iscomparable 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,
C4 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 suchas 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 appear 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 forratios, 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.
7

For a description of the ENDF format and, in particular, tables of the ENDF MF and MT numbers, see:
M. Herman (ed.), ENDF-6 Formats Manual, report ENDF-102,
http://www-nds.iaea.org/ndspub/documents/endf/endf102/

48

EXFOR Basics

Since EXFOR contains a very large variety of data types, not all EXFOR data can be automatically translated
into C4 format. Tools for handling such cases, i.e. for translating additional data types into C4 format on a caseto-case basis, are available in the translation program X4TOC4 which is distributed as part of the ENDVER
program package 8 . This program allows the user also to change other parameters of the translation to C4. The
following pages describe the default options the user will get when retrieving C4 data directly.

Computation format units
All EXFOR units are converted to ENDF units:eV= energybarns= cross section
steradians= solid angle
seconds= timekelvin= temperature

Computation format fields
The computation format uses a classification system and units which are compatible with ENDF. Datais 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 subaccession number are included in the format. In addition, fields are assigned to define the status of the
EXFOR data (e.g., S = superseded), whether data is in the laboratory or center-of-mass frame ofreference, 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- 5Projectile ZA (e.g. neutron =1, proton =1001)(defined by reaction dictionary).
Target ZA (e.g. 26-Fe-56 = 26056)(defined by EXFOR reaction).
Target metastable state (e.g. 26-FE-56m = M)
(defined by EXFOR reaction).
MF (ENDF conventions, plus additions)(defined by reaction dictionary).
MT (ENDF conventions, plus additions)(defined by reaction dictionary).
Product metastable state (e.g. 26-FE-56M = M)
(defined by EXFOR reaction).
EXFOR status(defined by EXFOR keyword status).
Center-of-mass flag (C=center-of-mass, blank=lab)(defined by EXFOR title dictionary).
8 data fields (each in E9.3 format defined below)(defined by MF and title dictionary).

6- 11
12
13- 1516- 1920
21
22
23- 948

See: ENDVER, ENDF File Verification Support Package, http://www-nds.iaea.org/ndspub/endf/endver/and D.E. Cullen and A. Trkov, Program X4TOC4, report IAEA-NDS-80, Rev.1, March 2001

49

EXFOR Basics

95- 97
98-122
123-127128-130
131

Identification of data fields 7 and 8(e.g., LVL=level, HL=half-life, etc.).
Reference (first author and year)(defined by EXFOR keywords title and reference).
EXFOR accession number(defined by EXFOR format).
EXFOR sub-accession number(defined by EXFOR format).
Multi-dimension table flag (EXFOR pointer)(defined by EXFOR keyword reaction or common fields).

Definition of 8 computation format data fields
The general definitions of the 8 computation format data fields are:Data field

Definition

1
2
3
4
5
6
7
8

Projectile incident energy
Projectile incident energy uncertainty
Data, e.g., cross section, angular distribution, etc.
Data uncertainty
Cosine or Legendre order
Cosine uncertainty
Identified by columns 95-97 (e.g., level energy, half-life)
Identified by columns 95-97 (e.g., level energy, 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 andcolumns 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 toprocess additional types of data the following special conventions have been adopted:
Cross section ratios (MF = 203)

Field 5 = MT of denominator.
Field 6 = ZA of denominator.

Resonance integrals (MF = 213)

Field 1 = lower energy limit.
Field 2 = upper energy limit.

Spectrum averages (MF = 223)

Field 1 = lower energy limit.
Field 2 = upper energy limit.

Fission yield data (MF = 801)

Field 5 = ZA of fission fragment.
Field 6 = mass of fission fragment.

Production data (MT = 9000-9999)

Field 6 = ZA of product.

Metastable states
The computation format allows the metastable state of the target and residual nucleus to be identified.
For ratio data, the 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 residual50

EXFOR Basics

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 numericalform. The possible characters that may appear in columns 12 or 20 and their numerical equivalents
used with ratio denominator ZA and MT include:
Definition
ground
m1
m2
m3
m4
m5
unknownmmore than 1
all or total
all or total

Column 12 or 20
G
1
2
3
4
5
?
M
+
T
blank

Equivalent
0
1
2
3
4
5
6
7
8
9
9

By convention, if an EXFOR reaction does not specify a Metastable state the state is defined in thecomputation 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.
EXFOR Status
Column 21 of each computation format record may contain blank (status not specified) or one of thefollowing characters:
Column 21

DefinitionU

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).
Approved by author
Correlated
Dependent
Outdated
Preliminary
Re-normalized
Superseded

A
C
D
O
P
R
S

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.

51

EXFOR Basics

C4 Example 1: 178Hf(n,p) cross section

Projectile ZA

Target ZA

Subaccession
numberAuthor, year

MF, MT, isomer

1 72178 3 103M
1 72178 3 103G
1 72178 3 103M
1 72178 3 103M
1 72178 3 103M
1 72178 3 103M
1 72178 3 103M
1 72178 3 103M
1 72178 3 103G
1 72178 3 103M
1 72178 203 103M

1.4800+7
1.0200-3 1.0000-4
1.4800+71.7200-3 1.7000-4
1.3400+7 90000.00 2.1000-4 1.1466-4
1.3650+7 90000.00 2.1000-4 1.3020-4
1.3880+7 90000.00 3.7000-4 1.1359-4
1.4280+7 90000.00 4.4000-4 1.9976-4
1.4580+7 90000.00 6.1000-4 1.4152-4
1.4870+7 90000.00 6.3000-4 1.5813-4
1.4540+7 240000.0 1.8000-3 4.0000-4
1.4540+7 240000.0 9.8000-4 8.0000-5
1.4540+7 240000.0 0.540000 0.130000

DATA

EN
MF=203:cross section ratio

52

EN-ERR

DATA-ERRFor ratio: MT and ZA
of denominator103.0 72178.9

Reaction
pointer

J.L.MEASON,ET.AL. (66)
J.L.MEASON,ET.AL. (66)
S.MURAHIRA,ET.AL. (95)
S.MURAHIRA,ET.AL. (95)
S.MURAHIRA,ET.AL. (95)
S.MURAHIRA,ET.AL. (95)
S.MURAHIRA,ET.AL. (95)
S.MURAHIRA,ET.AL. (95)
A.KIROV,ET.AL. (93)A.KIROV,ET.AL. (93)A.KIROV,ET.AL. (93)13039 3113039 32
22311 1122311 1122311 1122311 1122311 1122311 1131439 6131439 6231439 63

EXFOR Basics

C4 Example 2: Partial differential cross section for 56Fe(n,n’)

Projectile ZA

Target ZA
MF=4: angular
distribution

1 26056 4 51 AC 5050000. 10000.00 0.030000 5.0000-3 0.902585
1 26056 4 51 AC 5050000.
10000.00
MT=51:
partial 0.019000 6.0000-3 0.812083
1 26056 4 51 AC 5050000.
10000.00
0.022000 5.0000-3 0.758134
inelasticcs
1 26056 4 51 AC 5050000. 10000.00 0.020000 2.0000-3 0.560638
1 26056 4 51 AC 5050000. 10000.00 0.018000 2.0000-3 0.290701
EN0.018000 2.0000-3-0.019200
1 26056 4 51 AC 5050000. 10000.00
1 26056 4 51 AC 5050000. 10000.00 0.022000 2.0000-3-0.359999
1 26056
4 51 AC 5050000. 10000.00 0.023000 2.0000-3-0.586375
EN-ERR
1 26056 4 51 AC 5050000. 10000.00 0.020000 2.0000-3-0.853553
1 26056 4 51 AC 5580000. 10000.00
0.041000
8.0000-3 0.902585
Next
EN value
1 26056 4 51 AC 5580000. 10000.00 0.028000 4.0000-3 0.860742
1 26056 4 51 AC 5580000. 10000.00 0.026000 5.0000-3 0.812083
1 26056 4 51 AC 5580000. 10000.00 0.020000 2.0000-3 0.758134
1 26056 4 51 AC 5580000. 10000.00 0.019000 1.0000-3 0.560638
1 26056 4 51 AC 5580000. 10000.00 0.016000 2.0000-3 0.290701
1 26056 4 51 AC 5580000. 10000.00 0.013000 1.0000-3-0.019200
1 26056 4 51 AC 5580000. 10000.00 0.015000 2.0000-3-0.359999
1 26056 4 51 AC 5580000. 10000.00 0.014000 1.0000-3-0.586375
1 26056 4 51 AC 5580000. 10000.00 0.014000 1.0000-3-0.853553
1 26056 4 51 AC 5050000. 10000.00 0.017000 3.0000-3 0.902585
1 26056 4 51 AC 5050000. 10000.00 6.0000-3 2.0000-3 0.812083
1 26056 4 51 AC 5050000. 10000.00 0.011000 1.0000-3 0.758134
1 26056 4 51 AC 5050000. 10000.00 6.0000-3 1.0000-3 0.560638
1 26056 4 51 AC 5050000. 10000.00 8.0000-3 1.0000-3 0.290701
1 26056 4 51 AC 5050000. 10000.00 9.0000-3 1.0000-3-0.019200
1 26056 4 51 AC 5050000. 10000.00 7.0000-3 1.0000-3-0.359999
1 26056 4 51 AC 5050000. 10000.00 6.0000-3 1.0000-3-0.586375
1 26056 4 51 AC 5050000. 10000.00 7.0000-3 1.0000-3-0.853553
1 26056 4 51 AC 5580000. 10000.00 0.013000 2.0000-3 0.902585
1 26056 4 51 AC 5580000. 10000.00 9.0000-3 1.0000-3 0.860742
1 26056 4 51 AC 5580000. 10000.00 8.0000-3 2.0000-3 0.812083
1 26056 4 51 AC 5580000. 10000.00 7.0000-3 1.0000-3 0.758134
1 26056 4 51 AC 5580000. 10000.00 7.0000-3 1.0000-3 0.560638
1 26056 4 51 AC 5580000. 10000.00 9.0000-3 1.0000-3 0.290701
1 26056 4 51 AC 5580000. 10000.00 7.0000-3 1.0000-3-0.019200
1 26056 4 51 AC 5580000. 10000.00 6.0000-3 1.0000-3-0.359999
1 26056 4 51 AC 5580000. 10000.00 4.0000-3 1.0000-3-0.586375
1 26056 4 51 AC 5580000. 10000.00 5.0000-3 1.0000-3-0.853553
1 26056 4 51 AC 5050000. 10000.00 0.011000 1.0000-3 0.901832
1 26056 4 51 AC 5050000. 10000.00 9.0000-3 1.0000-3 0.810041
1 26056 4 51 AC 5050000. 10000.00 9.0000-3 1.0000-3 0.754709
1 26056 4 51 AC 5050000. 10000.00 7.0000-3 1.0000-3 0.556294
1 26056 4 51 AC 5050000. 10000.00 7.0000-3 1.0000-3 0.285687
1 26056 4 51 AC 5050000. 10000.00 7.0000-3 1.0000-3-0.026179
1 26056 4 51 AC 5050000. 10000.00 7.0000-3 1.0000-3-0.364879
1 26056 4 51 AC 5050000. 10000.00 8.0000-3 1.0000-3-0.590608
1 26056 4 51 AC 5050000. 10000.00 9.0000-3 1.0000-3-0.855366
1 26056 4 51 AC 5580000. 10000.00 0.011000 1.0000-3 0.901832
1 26056 4 51 AC 5580000. 10000.00 0.011000 1.0000-3 0.860742
1 26056 4 51 AC 5580000. 10000.00 8.0000-3 1.0000-3 0.810041
1 26056 4 51 AC 5580000. 10000.00 7.0000-3 1.0000-3 0.754709
1 26056 4 51 AC 5580000. 10000.00 8.0000-3 1.0000-3 0.556294
1 26056 4 51 AC 5580000. 10000.00 6.0000-3 1.0000-3 0.285687
1 26056 4 51 AC 5580000. 10000.00 6.0000-3 1.0000-3-0.026179
1 26056 4 51 AC 5580000. 10000.00 6.0000-3 1.0000-3-0.364879
1 26056 4 51 AC 5580000. 10000.00 6.0000-3 1.0000-3-0.590608
1 26056 4 51 AC 5580000. 10000.00 6.0000-3 1.0000-3-0.855366
Approved byauthorCenter-ofmass system

Level energy

cos

DATA

846000.0846000.0846000.0846000.0846000.0846000.0846000.0846000.0846000.0846000.0846000.0846000.0846000.0846000.0846000.0846000.0846000.0846000.0846000.02085000.
2085000.
2085000.
2085000.
2085000.
2085000.
2085000.
2085000.
2085000.
2085000.
2085000.
2085000.
2085000.
2085000.
2085000.
2085000.
2085000.
2085000.
2085000.
2658000.
2658000.
2658000.
2658000.
2658000.
2658000.
2658000.
2658000.
2658000.
2658000.
2658000.
2658000.
2658000.
2658000.
2658000.
2658000.
2658000.
2658000.
2658000.

Author,year

Subaccession
number

LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)Next
LVLP.BOSCHUNG,ET.AL.
(71)
level energy
LVLP.BOSCHUNG,ET.AL.
(71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)
LVLP.BOSCHUNG,ET.AL. (71)10037 47
10037 47
10037 47
10037 47
10037 47
10037 47
10037 47
10037 47
10037 47
10037 47
10037 47
10037 47
10037 47
10037 47
10037 47
10037 47
10037 47
10037 47
10037 47
10037 49
10037 49
10037 49
10037 49
10037 49
10037 49
10037 49
10037 49
10037 49
10037 49
10037 49
10037 49
10037 49
10037 49
10037 49
10037 49
10037 49
10037 49
10037 49
10037 51
10037 51
10037 51
10037 51
10037 51
10037 51
10037 51
10037 51
10037 51
10037 51
10037 51
10037 51
10037 51
10037 51
10037 51
10037 51
10037 51
10037 51
10037 51

DATA-ERR

53

EXFOR Basics

Examples of other output formats
Example: T4 format
Simple tabulated cross sections with short bibliography, for single datasets

54

EXFOR Basics

Example: TAB format
Computational format introduced in the 1980s for the CSISRS/EXFOR system in use at NNDC(USA), still available for backwards compatibility. Separate output of tables, reference (XREF) andBIB files.
Table
REQUEST
605001
20080605
31146540 0
0PHYSENT10
6 1.3400E+07 1.4870E+07
1 0
00.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00
1 001.3400E+07 9.0000E+04 9.0000E+04 4.6500E-03 7.3470E-04 7.3470E-04
1 1
1
1.3650E+07 9.0000E+04 9.0000E+04 6.9500E-03 9.9385E-04 9.9385E-04
1 1
1
1.3880E+07 9.0000E+04 9.0000E+04 6.6700E-03 9.2046E-04 9.2046E-04
1 1
1
1.4280E+07 9.0000E+04 9.0000E+04 8.2200E-03 1.0193E-03 1.0193E-03
1 1
1
1.4580E+07 9.0000E+04 9.0000E+04 1.1100E-02 1.3986E-03 1.3986E-03
1 1
1
1.4870E+07 9.0000E+04 9.0000E+04 9.7500E-03 1.2675E-03 1.2675E-03
1 1
1
ENDPHYSENT
199999999
PHYSENT10
6 1.3400E+07 1.4870E+07
2 000.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00
2 001.3400E+07 9.0000E+04 9.0000E+04 2.1000E-04 1.1466E-04 1.1466E-04
2 1
1
1.3650E+07 9.0000E+04 9.0000E+04 2.1000E-04 1.3020E-04 1.3020E-04
2 1
1
1.3880E+07 9.0000E+04 9.0000E+04 3.7000E-04 1.1359E-04 1.1359E-04
2 1
1
1.4280E+07 9.0000E+04 9.0000E+04 4.4000E-04 1.9976E-04 1.9976E-04
2 1
1
1.4580E+07 9.0000E+04 9.0000E+04 6.1000E-04 1.4152E-04 1.4152E-04
2 1
1
1.4870E+07 9.0000E+04 9.0000E+04 6.3000E-04 1.5813E-04 1.5813E-04
2 1
1
ENDPHYSENT
199999999
ENDREQUEST
9999999999999

XREF
REQUEST
605001 20080605
50-SN-118(N,P)49-IN-118-M1+M2,,SIG
72-HF-178(N,P)71-LU-178-M,,SIG

3112903
1.3+07 1.5+07
1.3+07 1.5+07

0 0
6 2JPNNAG
6 2JPNNAG

0S,INDC(JPN)-175/U,171,
S,INDC(JPN)-175/U,171,

9511 S.Murahira,9511 S.Murahira,22311002
22311011

BIB
BIBFILEBIB
INSTITUTE

605001
20080605
311290322311002
102(2JPNNAG) S.MURAHIRA, Y.SATOH, N.HONDA, M.SYIBATA,
H.YAMAMOTO, K.KAWADE(2JPNOSA) A.TAKAHASHI, T.IIDA AND EXPERIMENTAL SITE
TITLE
-MEASUREMENT OF FORMATION CROSS SECTIONS PRODUCINGSHORT-LIVED NUCLEI BY 14 MEV NEUTRONS - PR, BA, CE,
SM, W, SN, HF
AUTHOR(S.MURAHIRA,Y.SATOH,N.HONDA,A.TAKAHASHI,T.IIDA,
M.SHIBATA,H.YAMAMOTO,K.KAWADE)REFERENCE (S,INDC(JPN)-175/U,171,9511) PROCEEDINGS OF THE 1995
SYMPOSIUM ON NUCLEAR DATA, NOV. 16-17, JAERI,TOKAI(S,JAERI-M-92-027,268,9203) EXPERIMENTAL DETAILS(S,INDC(JPN)-157,268,9203) EXPERIMENTAL DETAILSFACILITY(CCW,2JPNOSA) THE INTENSE 14 MEV NEUTRON SOURCEOKTAVIAN AT OSAKA UNIVERSITY.
METHOD(ACTIV) ACTIVATION
INC-SOURCE (D-T ) THE D-BEAM ENERGY WAS 300 KEV AND THE INTENSIT
WAS 5 MILLIAMPS. A SAMPLE TRANSPORT SYSTEM OF SIX
PNEUMATIC TUBES AT ANGLES OF 0, 50, 75, 105, 125 AND

0
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1

0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0

0
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1

55

EXFOR Basics

Example: R33 format
This format was developed for the ion beam analysis (IBA) community and is used e.g. in the
IBANDL database. For the data types relevant for IBA (mainly charged-particle induced differential
cross sections at fixed angles dependent on projectile energy) it is available as EXFOR output format.

Plotting option from R33 output

56

EXFOR Basics

Example: Extended C4 format
Computational format (C4) output with explanatory text lines (labelled with #) added for better
readability.

57

EXFOR Basics

Example: Bibliographic output
Summary of bibliographic information belonging to an EXFOR retrieval. Available as html
bibliography and in BibTex format.

BibTex58

EXFOR Basics

Example: Plots
Several options for plotting data directly from EXFOR retrievals are available, including
comparisons with evaluated data from the ENDF database which can be retrieved together with
EXFOR data.

Quick plot

Advanced plots

Angular distribution,compared withevaluated curves from
ENDF

59

EXFOR Basics

Advanced plots (cont.)

Cross section,compared withevaluated curves from
ENDF

Double-differential
cross section, comparedwith evaluated data from
ENDF/B-VII

60

EXFOR Basics

Appendix: Tables of Dictionaries

The EXFOR System Dictionaries list all keywords and codes used in the EXFOR
entries. Listings are included for the following dictionaries. Where the dictionary islarge, the most used codes are given. A complete listing of all dictionaries and codesis available from the IAEA Nuclear Data Section or any other of the Nuclear Reaction
Data Centers.

Dictionary 3.
Dictionary 4.
Dictionary 5.
Dictionary 7.
Dictionary 15.
Dictionary 16.
Dictionary 17.
Dictionary 18.
Dictionary 19.
Dictionary 20.
Dictionary 21.
Dictionary 22.
Dictionary 23.
Dictionary 24.
Dictionary 30.
Dictionary 33.
Dictionary 34.
Dictionary 35.
Dictionary 37.
Dictionary 207.
Dictionary 236.

Institutes
Reference Type
Journals
Conferences
History
StatusRelated Reference
Facility
Incident Source
Additional Results
MethodDetectors
Analysis
Data Headings
Process
Particles
Modifiers (REACTION SF8)
Data-Type (REACTION SF9)
ResultBooks
Quantities (REACTION SF5-7)

61

EXFOR Basics

Dictionary 3. Institutes: used with the keywords INSTITUTE and FACILITY. The firstcharacter of the codes designates the nuclear data centres’ area of responsibility – related to thecompilation responsibilities for neutron data - , the next three characters designate the country,
and the last three characters specify the institute. A subset containing some of the mostfrequently used codes is given here.
International Institutes
2ZZZCER2ZZZGEL2ZZZISP2ZZZITU
2ZZZNDC3ZZZIAE
4ZZZDUB
Argentina
3ARGCAB
3ARGCNE
Armenia
4ARMJER
Australia
3AULAML
3AULAUA
3AULCBR
Austria
2AUSIRK
Bangladesh
3BANDAC
3BANRAM
Belarus
4BLRIJE
Belgium
2BLGMOL
Brazil3BZLIPE
3BZLUSP
Bulgaria
3BULBLA
3BULSOF
Canada1CANCRC
1CANMCM
1CANTMF
China
3CPRAEP
3CPRBJG
3CPRLNZ
3CPRNIX3CPRNRS3CPRSST
3CPRTSI
Croatia
3CRORBZ
3CROZAG
Czech Republic
3CZRUJV
Denmark
2DENRIS62

CERN, Geneva, Switzerland
Inst. for Ref. Mat. and Meas. (IRNM), Geel, Belgium
E.C. Joint Research Center (JRC), Ispra, Italy
CEC Institute for Transuranium Elements, Karlsruhe, Germany
NEA Data Bank, Paris, France
IAEA, Vienna, Austria
Joint Inst.for Nucl.Res., Dubna, Russia
Inst.Balseiro y Centro Atomico Bariloche, Bariloche
Comision Nacional de Energia Atomica, Buenos Aires
Inst. Fiziki Armenian A.N., Jerevan
Univ. of Melbourne, Melbourne
Australian Nucl. Sci. and Techn.Org., Lucas Heights, SW
Australian National Univ., Canberra
Inst. fuer Isotopenforschung und Kernphysik, Vienna
Dhaka, University
Dhaka, Atomic Energy Centre, Ramna
Inst. Yad. Energetiki A.N.Byeloruss.SSR, Minsk
C.E.N., Mol
Inst.de Pesquisas Energeticas e Nucleares, Sao Paulo
Univ.de Sao Paulo, Sao Paulo
Sofia, Inst. of Nuclear Res. and Nuclear Energy
Univ.of Sofia
A.E.C.L., Chalk River, Ontario
McMaster University, Hamilton, Ontario
Tri University Meson Facility, Vancouver, B.C.
Inst. of Atomic Energy, Beijing
Beijing Univ., Beijing
Lanzhou Univ., Lanzhou
Northwest Inst.of Nucl.Technology, Xian
Inst.of Nucl.Research, Acad.Sinica, Shanghai
Shanghai Univ. of Science and Technology
Tsinghua Univ., Beijing
Inst.Rudjer Boskovic, Zagreb
Univ. of Zagreb, Zagreb
Inst. of Nuclear Research, Rez i Prahy
Riso, Roskilde

EXFOR Basics

Finland
2SF ABA
2SF JYVFrance2FR BRC
2FR CAD
2FR FAR
2FR GRE
2FR PAR
2FR SAC
Germany
2GERFRK2GERGSI
2GERHAM2GERJUL2GERKFK2GERKIL
2GERMUN
2GERPTB
2GERZFK
Greece2GRCATH
Hungary
3HUNDEB
3HUNKFI
3HUNKOSIndia
3INDBOS
3INDMUA
3INDPOO
3INDSAH
3INDTAT
3INDTRM
3INDURJ
Israel
3ISLNEG
3ISLWEIItaly
2ITYBOL
2ITYCAT
2ITYPADJapan
2JPNIPC
2JPNJAE
2JPNKEK2JPNKTO2JPNKYU2JPNLEP
2JPNOSA2JPNTIT2JPNTOH
2JPNTOK
2JPNTSU
Kazakhstan
4KASKAZ
Republic of Korea
3KORDAU
3KORKAE
3KORKNU
3KORKRM

Abo Akademi, Turku
Jyvaeskylae Univ., Jyvaeskylae
CEN Bruyere-le-Chatel
C.E.N. Cadarache
CEA Fontenay-aux-Roses, Seine
Grenoble, Isere, (CEA and Univ.)
Univ. of Paris, (incl.Orsay), Paris
C.E.N. Saclay
J.W.Goethe Univ.,Frankfurt
Gesellschaft fuer Schwerionenforschung, Darmstadt
Hamburg, Universitaet
Kernforschungsanlage Juelich
Kernforschungszentrum, Karlsruhe
Univ. of Kiel, Kiel
Technische Universitaet Muenchen
Phys.Techn.Bundesanst., Braunschweig
Zentralinst.f.Kernforschung, Rossendorf
CNRC Demokritos, Athens
Inst.of Nuclear Research, ATOMKI, Debrecen
Central Research Inst. for Physics, KFKI, Budapest
Inst. for Experimental Physics, Kossuth U., Debrecen
Bose Institute, Calcutta
Muslim Univ., Aligarh
Poona, University
Saha Institute, Calcutta
Tata Institute, Bombay
Bhabha Atom.Res.Centre, Trombay
Univ.of Rajestan, Jaipur
Ben Gurion Univ. of the Negev, Beer-Sheva
Weizmann Inst., Rehovoth
ENEA Centro Ricerche Energia di Bologna
Univ. of Catania
Padua, University and Lab. Nat. LegnaroInst.of Physical and Chemical Res. (RIKEN), Wakou
Japan Atomic Energy Agency (JAEA)
High Energy Accelerator Res. Org. (KEK), Tsukuba
Kyoto Univ., Kyoto
Kyushu Univ., Dept.of Nucl.Eng., Fukuoka
Nat.lab.for High Energy Physics, Oho, Ibaraki
Osaka Univ., Osaka
Tokyo Inst.of Technology, Tokyo
Tohoku Univ., Sendai
Tokyo Univ., Tokyo
Univ. of Tsukuba, Tsukuba
Inst.Yadernoi Fiziki, Alma-Ata
Donga University, Pusan
Korean Atomic Energy Res. Inst., Yusong, Taejon
Kyungpook National University
Korea Inst.Radiol.and Med.Sci.(KIRAMS), Seoul

63

EXFOR Basics

3KORNSU
3KORPNU
3KORPUE
Latvia4LATIFL
Mexico3MEXUMX
The Netherlands
2NEDGRN
2NEDRCN
Norway2NORKJLNew Zealand
3NZLNZH
Pakistan
3PAKNIL
Poland3POLIPJ
3POLWWA
Romania
3RUMBUC
Russia4RUSEPA
4RUSFEI
4RUSFTI
4RUSICP
4RUSITE
4RUSJIA
4RUSKUR
4RUSLEB
4RUSLIN
4RUSMOS
4RUSNIR
4RUSRI
Slovakia
3SLKSLO
3SLKUB
Slovenia
3SLNIJS
South Africa
3SAFITH
3SAFPELSpain
2SPNSAU2SPNSEU
2SPNVAL
Sweden2SWDAE
2SWDFOASwitzerland
2SWTETH
2SWTPSI
Ukraine
4UKRIJI
4UKRKFT4UKRKGU
United Kingdom
2UK ALD
2UK DOU
2UK HAR64

Natl.Seoul Univ., Seoul
Pusan National University, Pusan
Pohang Univ. of Science and Technology, PohangInst. Fiziki Latviyskoi A.N., Riga
Univ. Nacionale Autonoma de Mexico, Mexico City
Groningen
Netherland's Energy Research Foundation, Petten
Inst. foer Atomenergi, Kjeller
Inst.of Nuclear Sciences, Lower Hutt
PINSTECH, Nilore, Rawalpindi
Soltan Inst.Probl.Jadr., Swierk+Warszawa
Warszawa, University
Inst. de Fizica si Inginerie Nucleara, Bucharest
Experimental Physics Inst., Arzamas
Fiziko-Energeticheskii Inst., ObninskFiz.-Tekhnicheskiy Inst.Ioffe, St.Petersburg+Gatchina
Inst.of Chemical Phys., Moscow
Inst.Teoret.+ Experiment. Fiziki, Moscow
Inst.Yadernych Issledovaniy Russian Acad. Sci.
Inst.At.En. I.V.Kurchatova, Moscow
Fiz.Inst. Lebedev (FIAN), Moscow
Leningrad Inst.Nucl.Phys., Russian Acad.Sci., Gatchina
Moscow State Univ., Nuclear Physics Inst., Moscow
NIIAR Dimitrovgrad
Khlopin Radiev.Inst., Leningrad
Slovak Academy of Sciences, Physics Inst., Bratislava
Komenskeho (Comenius) Univ., Bratislava
Inst. Jozef Stefan, Ljubljana
iThemba LABS, Somerset West
Atomic Energy Corp.of South Africa, Pelindaba
Univ.de Santiago de Compostela
Sevilla University
Valencia, University
Studsvik Energiteknik AB
Research Inst. for National Defence, Stockholm
Eidgenossische Technische Hochschule, ZuerichPaul Scherrer Inst., Villigen
Inst. Yadernykh Issledovaniy Acad. Sct. Ukraine, Kiev
Kharkovskii Fiziko-Tekhnicheskii Inst., Kharkov
Gosudarstvennyi Univ.(State Univ.), Kiev
Awre, Aldermaston, England
Dounreay Experimental Reactor Establishment, England
AERE, Harwell, Berks, England

EXFOR Basics

2UK NPL
2UK OXF
United States
1USAANL
1USAARK
1USABNL
1USABNW
1USABRK
1USACOL
1USADAV
1USADKE1USAFSU
1USAGEO
1USAGGA
1USAGIT
1USAHAN
1USAINL
1USAINU
1USAKAP
1USAKTY
1USALAS
1USALRL
1USALTI
1USAMHG
1USAMIT
1USAMRY
1USANBS
1USANIS
1USANOT
1USAOHO
1USAORL
1USARPI
1USATEX
1USATNL
1USAWIS
Vietnam
3VN DAL
3VN IPH

National Phys.Lab., Teddington, England
Univ. of Oxford, Oxford, England
Argonne National Laboratory, Argonne, IL
Univ. of Arkansas, Fayetteville, AR
Brookhaven National Laboratory, Upton, NY
Pacific Northwest Laboratories, Richland, WA
Univ. of Calif. Lawrence Berkeley Lab., Berkeley, CA
Columbia University, New York, NY
University of California, Davis, CA
Duke University, Durham, NC
Florida State University, Tallahasse, FL
University of Georgia, Athens, GA
Gulf General Atomic, San Diego, CA
Georgia Institiute of Technology, Atlanta, GA
Hanford Atomic Products, Richland, WA
Idaho Nuclear Engineering Lab., Idaho Falls, ID
Indiana University, Bloomington, IN
Knolls Atomic Power Laboratory, Schenectady, NY
University of Kentucky, Lexington, KY
Los Alamos National Laboratory, NM
Lawrence Livermore National Laboratory, Livermore, CA
University of Lowell, Lowell, MA
University of Michigan, Ann Arbor, MI
Massachusetts Institute of Technology, Cambridge, MA
University of Maryland, College Park, MD
National Bureau of Standards, Washington, DC
National Inst.of Standards & Techn., Gaithersburg, MD
Univ. of Notre Dame, Notre Dame, IN
Ohio University, Athens, OH
Oak Ridge National Laboratory, Oak Ridge, TN
Rensselaer Polytechnic Institute, Troy, NY
Univ. of Texas, Austin, TX
Triangle Universities Nuclear Lab., Durham, NC
University of Wisconsin, Madison, WI
Nuclear Research Inst., Dalat
Inst.of Phys.and Electronics, Acad. Sci., Hanoi

65

EXFOR Basics

Dictionary 4: Reference type: used as the first subfield for the keyword REFERENCE, and,similarly, for MONIT-REF, and REL-REF.
A
B
C
J
K
P
R
S
T
W
X

Abstract of conferenceBook
Conference
JournalAbstract of journal
Progress report
Report other than progress report
Report containing conference proceedings
Thesis or dissertation
Private communication
Preprint

Dictionary 5: Journal codes: used as the second subfield for the keyword REFERENCE, when thereference type is given as J or K; similarly, for MONIT-REF, and REL-REF. A subset containingsome of the most frequently used codes is given here. The code may have an extension delimited
by a slash; these extensions have the following meanings:/A, /B,..., /G section or series/L
letters section/S
supplement
ACR
ADP
AE
AEJ
AF
AHP
AJ
AK
AKE
ANE
ANP
ANS
AP
APA
APP
ARI
AUJ
BAP
BAS
CHP
CJP
CPL
CR
CZJ
DOK
EPJ
FIZ
HPA
IJP
INC
ISP
IZV
JAE
JEL

66

Acta Crystallographica
Annalen der Physik
Atomnaya Energiya
Journal of the Atomic Energy Society of Japan
Arkiv foer Fysik
Acta Physica Hungarica
Astrophysical Journal
Atomki Kozlemenyek
Atomkernenergie
Annals of Nuclear Energy
Annalen der Physik (Leipzig)
Transactions of the American Nuclear Society
Annals of Physics (New York)
Acta Physica Austriaca
Acta Physica Polonica
Applied Radiation and Isotopes
Australian Journal of Physics
Bulletin of the American Physical Society
Bull.Russian Academy of Sciences - Physics
Chinese Journal of Physics (Taiwan)
Canadian Journal of Physics
Chinese Physics Letters
Comptes Rendus
Czechoslovak Journal of Physics
Doklady Akademii NaukEuropean Physics Journal
FizikaHelvetica Physica Acta
Indian Journal of Physics
Inorganic and Nuclear Chemistry Letters
Israel J.of Physics
Izv.Rossiiskoi Akademii Nauk,Ser.Fiz.
Yadernaya Energetika
Soviet Physics - JETP Letters

EXFOR Basics

JET
JIN
JNE
JNRS
JP
JPJ
JPR
JRC
JRN
KFI
KPS
NC
NCL
NCR
NCS
NIM
NKA
NP
NSE
NST
NWS
PAN
PCJ
PHE
PHY
PL
PNE
PPS
PR
PRL
PRM
PRS
PS
PTE
RCA
RJP
RRL
RRP
SJA
SJPN
SPC
SPD
UFZ
UPJ
YF
YK
ZEP
ZET
ZP

Soviet Physics - JETP
Journal of Inorganic and Nuclear Chemistry
Journal of Nuclear Energy
Journal of Nuclear and Radiochemical Sciences
Jour. of Physics
Journal of the Physical Society of Japan
Journal de Physique (Paris)
J.of Radioanalytical ChemistryJ.of Radioanalytical and Nuclear Chemistry
KFKI Kozlemenyek
Journal of the Korean Physical Society
Nuovo Cimento
Lettere al Nuovo Cimento
Rivista del Nuovo Cimento
Nuovo Cimento, Suppl.
Nuclear Instrum.and Methods in Physics Res.
Nukleonika
Nuclear Physics
Nuclear Science and Engineering
J.of Nuclear Science and Technology, Tokyo
NaturwissenschaftenPhysics of Atomic Nuclei
Journal of Physical ChemistryHigh Energy Physics and Nucl.Physics,Chinese ed.
Physica (Utrecht)
Physics Letters
Progress in Nuclear Energy
Proceedings of the Physical Society (London)
Physical Review
Physical Review Letters
Pramana (India)
Proc. of the Royal Society (London)
Physica Scripta
Pribory i Tekhnika Eksperimenta
Radiochimica Acta
Romanian Journal of Physics
Radiochem.and Radioanal.Letters
Revue Roumaine de PhysiqueSoviet Atomic Energy
Soviet Journal of Particles and Nuclei
Soviet Physics-Cristallography
Soviet Physics-Doklady
Ukrainskii Fizichnii Zhurnal
Ukrainian Physics Journal
Yadernaya Fizika
Vop. At.Nauki i Tekhn.,Ser.Yadernye Konstanty
Zhurnal Eksper. i Teoret. Fiz., Pisma v Redakt.
Zhurnal Eksperimental'noi i Teoret. Fiziki
Zeitschrift fuer Physik

67

EXFOR Basics

Dictionary 7: Conferences: used as the second subfield for the keyword REFERENCE, when thereference type is given as A or C, and similarly, for MONIT-REF, and REL-REF. A subset
containing some of the most frequently used codes is given here.
55GENEVA
55MOSCOW
56KIEV
58GENEVA
58PARIS59CALCUTTA
59LONDON
60BASEL
60VIENNA
60WIEN
61BOMBAY
61BRUSSELS
61DUBNA
61MANCH
61RPI
61SACLAY
62PADUA
63BOMBAY
63KRLSRH
64BOMBAY
64GENEVA
64PARIS65CALCUTTA
65KRLSRH
65SALZBURG
66BOMBAY
66GATLNBG
66MOSCOW
66PARIS
66WASH
67BRELA
67JUELICH
67KARLSR
68BOMBAY
68COPENHGN
68MADRAS
68WASH
69ROORKEE
69VIENNA
70ANL
70HELSINKI
70MADISON
70MADURAI
71KIEV
71KNOX
72BOMBAY
72GRENOBLE
72KIEV
73BANGLO
73KIEV
73MUNICH
73PACIFI
73PARIS
74BOMBAY
74PETTEN

68

1st Conf. on Peaceful Uses Atomic Energy, Geneva 1955
USSR Conf. Peaceful Uses of Atomic Energy, Moscow 1955
Kiev Conf., Kiev 1956
2nd Conf. on Peaceful Uses Atomic Energy, Geneva 1958
Nuclear Physics Congress, Paris 1958
Low Energy Nuclear Physics Symp., Calcutta 1959
Conf.Nuclear Forces and Few-Nucleon Problem, London 1959
Conf. on Polarization Phenom. in Nuclear Reactions, Basel 1960
Pile Neutron Research Symp., Vienna 1960
Neutron Inelastic Scattering Symp., Vienna 1960
Nuclear Physics Symp., Bombay 1961
Neutron Time-of-Flight Colloquium, Brussels 1961
Slow Neutron Physics Conf., Dubna 1961
Rutherford Conf., Manchester 1961
Neutron Physics Symp., Rensselaer Polytech 1961
Time of Flight Methods Conf., Saclay 1961
Nucl. Reaction Mechanisms Conf., Padua 1962
Nuclear and Solid State Physics Symp., Bombay 1963
Neutron Physics Conf., Karlsruhe 1963
Neutron Inelastic Scattering Symp., Bombay 1964
3rd Conf. on Peaceful Uses Atomic Energy, Geneva 1964
Nuclear Physics Congress, Paris 1964
Nuclear and Solid State Phys.Symp., Calcutta 1965
Pulsed Neutron Symp., Karlsruhe 1965
Physics and Chemistry of Fission Conf., Salzburg 1965
Nuclear and Solid State Physics Symp., Bombay 1966
Int. Conf. on Nuclear Physics, Gatlinburg, 1966
Nuclear Spectroscopy Conf., Moscow 1966
Nuclear Data For Reactors Conf., Paris 1966
Neutron Cross-Section Technology Conf., Washington 1966
Light Nuclei Symp., Brela 1967
Neutron Physics at Reactors Conf., Juelich 1967
Symp. on Fast Reactor Physics,Karlsruhe 1967
Nuclear and Solid State Physics Symp., Bombay 1968
Neutron Inelastic Scattering Symp., Copenhagen 1968
Nuclear and Solid State Physics Symp., Madras 1968
Nuclear Cross-Sections & Technology Conf., Washington 1968
Nuclear and Solid State Physics Symp., Roorkee 1969
Physics and Chemistry of Fission Symp., Vienna 1969
Neutron Standards Symp., Argonne 1970
Nuclear Data for Reactors Conf., Helsinki 1970
Polarization Phenomena Conf., Madison 1970
Nuclear and Solid State Physics Symp., Madurai 1970
Neutron Physics Conf., Kiev 1971
Conf. Neutron Cross Sections & Techology, Knoxville 1971
Nuclear and Solid State Physics Symp, Bombay 1972
Neutron Inelastic Scattering Symp., Grenoble 1972
Nuclear Spectroscopy Conf, Kiev 1972
Nuclear and Solid State Physics Symp.,Bangalore,1973
Conf.on Neutron Physics, Kiev 1973
Conf. on Nuclear Physics,Munich 1973
Conf. on Photonuclear Reactions, Pacific Grove 1973
Applications of Nuclear Data Symp., Paris 1973
Nuclear and Solid State Physics Symp., Bombay 1974
Symp. on Neutron Capture Gamma Ray Spectroscopy, Petten 1974

EXFOR Basics

75CALCUTTA
75KIEV
75WASH
75ZURICH
76AHMEDABA
76LOWELL
77BNL
77KIEV
77NBS
77VIENNA
78BNL
78BOMBAY
78HARWELL
79JUELICH
79KNOX
79MADRAS
79SMOLENIC
80BERKELEY
80BNL
80KIEV
80SANTA FE
81ANL
81BOMBAY
81GRENOB
82ANTWER
82SMOLEN
83KIEV
83MYSORE
84GAUSSIG
84KNOX
85JUELIC
85SANTA86DUBROV
86HARROG
87KIEV
88BOMBAY
88MITO89LENING
89WASH
91BEIJIN
91JUELIC
92BOMBAY
94GATLIN
96BUDA
96NOTRED
97TRIEST
98VOLOS
99BUCHAR
99HABAY
99PRAHA
99RAB
99SANTA
99SARAT
99ST.AND
99TSUKUB
99VANCOU
2000PITTSB
2000STPETR
2001BERKEL
2001CASTAP

Nuclear and Solid State Physics Symp.,Calcutta,1975
Conf. on Neutron Phys., Kiev 1975
Conf. on Nuclear Cross Sections and Technology, Washington 1975
Symp. on Polarization Phenomena, Zuerich 1975
Nuclear Physics & Solid State Physics Symp., Ahmedabad,1976
Conf. on Interaction of Neutrons with Nuclei, Lowell 1976
Symp. on Neutron Cross Sections at 10 - 40 Mev, Brookhaven 1977
Conf. on Neutron Physics, Kiev 1977
Symp.on Neutron Standards, Gaithersburg 1977
Symp. on Neutron Inelastic Scattering, Vienna 1977
Symp.on Neutron Capture Gamma Ray Spectroscopy, Brookhaven 1978
Nuclear Physics and Solid State Physics Symp., Bombay 1978
Conf. on Neutron Physics and Nuclear Data, Harwell 1978
Symp. on Physics and Chemistry of Fission, Juelich 1979
Conf. on Nuclear Cross Sections fro Technology, Knoxville 1979
Nuclear Physics and Solid State Physics Symp., Madras 1979
Symp. on Neutron Induced Reactions, Smolenice 1979
Conf. on Nuclear Physics, Berkeley 1980
Symp. on Neutron Cross Sections at 10-50 MeV, Brookhaven 1980
All-Union Conf. on Neutron Physics, Kiev 1980
Symp. on Polarization Phenomena in Nuclear Physics, Santa Fe 1980
Neutron Scattering Conf., Argonne 1981
Nuclear Physics and Solid State Physics .Symp., Bombay 1981
Symp. on Neutron Capture Gamma-Ray Spectroscopy, Grenoble 1981
Conf. on Nuclear Data for Science and Technology, Antwerp 1982
Conf. on Neutron Induced Reactions, Smolenice 1982
All-Union Conf. on Neutron Physics, Kiev 1983
Nuclear Physics and Solid State Physics Symp., Mysore 1983
Symp. on Nuclear Physics, Gaussig 1984
Symp. on Capture Gamma Ray Spectroscopy, Knoxville 1984
Conf. on Neutron Scattering in the Nineties, Juelich 1985
Conf.on Nuclesar Data for Basic and Applied Science, Santa Fe 1985
Conf. on Fast Neutron Phys., Dubrovnik 1986
Nuclear Physics Conf., Harrogate 1986
Conf. on Neutron Physics, Kiev 1987
Nuclear Physics Symp., Bombay 1988
Conf. on Nuclear Data for Science and Technology, Mito 1988
50th Anniversary of Nuclear Fission, Leningrad 1989
50 Years of Nuclear Fission, Washington D.C. 1989
Symp. on Fast Neutron Physics, Beijing 1991
Conf. on Nuclear Data for Science and Technology, Juelich 1991
Nuclear Physics Symp., Bombay 1992
Nuclear Data for Science & Technology, Gatlinburg 1994
Symp. on Capture Gamma Ray Spectroscopy, Budapest, 1996
Nuclei in the Cosmos IV, Notre Dame, IN, 1996
Nuclear Data for Science & Technology, Trieste, Italy, 1997
Nuclei in the Cosmos V, Volos, Greece, 1998
Symp.on Adv.in Nucl.Phys., Bucharest, Romania, 1999
Sem.on Fission, Habay-la-Neuve, Belgium, 1999
Conf.on Accelerator Driven Transmutation, Prague 1999
Conf.Cluster.Aspects of Nucl.Struct.& Dynam.,Rab 1999
Symp.on Capt.Gamma Ray Spectroscopy, Santa Fe,NM 1999
Workshop on Beam Dynamics and Optimiz, Saratov 1999
Conf.on Fission+Neutron-Rich Nucl.,St.Andrews, 1999
Conf.on Radi9ation Shielding, Tsukuba, Japan, 1999
Int.Conf.on Isotopes (3ICI), Vancouver, Sept.1999
PHYSOR 2000, Pittsburgh, PA, 2000
Conf.Nucl.Spectr.Nucl.Struct.,St.Petersbg.,June 2000
Nucl.Physics in the 21st Cent.,Berkeley, CA,USA,2001
Dyn.Aspects of Nucl.Fiss.,Casta-Papiernicka 2001

69

EXFOR Basics

2001DUBNA
2001SARAT
2001SAROV
2001TSUKUB
2002BERKEL
2002DUBNA
2002MOSCOW
2002PRUHON
2002SANIB
2002SANTA
2002SEOUL
2003DARMST
2003HABAY
2003MOSCOW
2003SDIEGO
2004ARGON
2004BELGOR
2004BORMIO
2004EURAD
2004SANTA
2005BRUSS
2005KOS
2005NOTRED2005PAVIA
2005SANTA
2005SEVILL
2006BOROVE
2006CERN
2006MANGAL
2006VANCOU
2007NICE
2007TOKAI

70

Interaction of Neutrons with Nuclei, Dubna 2001
Workshop on Beam Dynamics and Optimiz, Saratov 2001
Conf.Nucl.Spectrosc.Nucl.Struct.,Sarov, Russia,2001
Conf.on Nucl.Data for Sci.and Techn., Tsukuba 2001
Conf. on Frontier of Nuclear Physics, Berkeley 2002
Int.Sem.Interaction of Neutrons w.Nuclei,Moscow,2002
Conf.Nucl.Spectrosc.Nucl.Struct.,Moscow,Russia,2002
Symp.on Capt.Gamma Ray Spectroscopy, Pruhonice, 2002
Fission,Prop.of Neutron-Rich Nucl.,Sanibel,USA,2002
Meeting on Radiation Shielding,Santa Fe,NM,USA, 2002
PHYSOR 2002, Physics of Reactors, Seoul, Korea, 2002
Worksh.Nucl.Data for Transmutation, Darmstadt, 2003
Sem.on Fission, Habay-la-Neuve, Belgium, 2003
Conf.Nucl.Spectrosc.Nucl.Struct.,Moscow,Russia,2003
Int.Meet.on Nucl.Appl.of Accel.Tech., San Diego 2003
Conf.on Nuclei at the Limits, Argonne, July 2004
Conf.Nucl.Spectrosc.Nucl.Struct.,Belgorod,Russia,2004
Int.Meeting on Nucl.Physics, Bormio, Italy, 2004
Conf.Manag.and Disposal of Rad.Waste,Luxembourg 2004
Conf.on Nucl.Data for Sci.and Techn., Santa Fe 2004
Int.Conf.on Isotopes (5ICI), Brussels, April 2005
Frontiers in Nucl.Structure,Kos,Greece,Sept.2005
Symp.on Capt.Gamma Ray Spectroscopy, Notre Dame 2005
Nucl.Phys.Divisional Conf., Pavia, Italy, Sept.2005
Int.Collab.on Adv.Neutron Sources,Santa Fe,April 2005
Int.Conf.on Ion Beam Analysis, Sevilla, 2005
Workshop Neutron Meas., Eval.& Appl., Borovets, 2006
9.Int.Symp.Nuclei in the Cosmos, CERN, Geneva, 2006
Nucl.Data f.Adv.Nucl.Systems, Mangalore, India, 2006
Advances in Nucl.Analysis and Simul.,Vancouver 2006
Conf.on Nucl.Data for Sci. and Technology, Nice 2007
Symp.on Nuclear Data, Tokai, Japan, Jan. 2007

EXFOR Basics

Dictionary 15: History codes: used with the keyword HISTORY.
A
C
D
E
L
R
S
T
U

Important alterations
Complied at the data center
Entry or subentry deleted
Transmitted to other data centersEntered into data library
Data received at the data center
Data restored from archive
Converted from previous compilation
Unimportant alterations

Dictionary 16: Status codes: used with the keyword STATUS.
APRVD
COREL
CPX
CURVE
DEP
NACRE
NCHKD
NDD
OUTDT
PRELM
RCALC
RIDER
RNORM
SCSRS
SPSDD
TABLE
UNOBT

Approved by author
Data correlated with another data set
Data taken from data file of McGowan, et al.
Data read from a curve
Dependent data
Converted from NACRE files
Original reference not checked
Data converted from NEUDADA file
Normalization out-of-date
Preliminary data
Ratio to standard calculated by other than author
Data converted from file of B.F. Rider
Data renormalized by other than author
Data converted from SCISRS file
Data superseded
Data received by center in tabular form
Data unobtainable from author

Dictionary 17: Related Reference codes: used with the keyword REL-REF.
A
C
D
E
N
R

Reference with which data agree
Critical remarks
Reference with which data disagree
Reference used in the evaluation
Reference from which data were used71

EXFOR Basics

Dictionary 18: Facility codes: used with the keyword FACILITY.
ACCEL
BETAT
CCW
CHOPF
CHOPS
CYCLO
CYCTM
CYGFF
DYNAM
ESTRG
FNS
FRS
ICTR
INTFM
ISOCY
LASER
LINAC
MESON
MICRT
OLMS
OSCIP
PRJFS
REAC
SELVE
SPECC
SPECD
SPECM
SRING
SYNCH
SYNCY
VDG
VDGT

72

Accelerator
Betatron
Cockcroft-Walton accelerator
Fast chopper
Slow chopper
Cyclotron
Tandem cyclotrons
Cyclograaff
Dynamitron
Electron storage ring
Fusion neutron source
Fragment separator
Insulated core transformer accelerator
Interferometer
Isochronous cyclotron
Laser system
Linear accelerator
Meson facility
Microtron
On-line mass separator
Pile oscillator
Secondary beam from projectile fragment separator
Reactor
Velocity selector
Crystal spectrometer
Double mass spectrometer
Mass spectrometer
Storage ring
Synchrotron
Synchro cyclotron
Van de Graaff
Tandem van de Graaff

EXFOR Basics

Dictionary 19: Incident Source codes: used with the keyword INC-SOURCE.
A-BE
ARAD
ATOMI
BRST
CF252
CM244
CM246
CM248
COMPT
D-BE
D-C12
D-C14
D-D
D-LI
D-LI7
D-N14
D-N15
D-T
EVAP
EXPLO
HARD
KINDT
LAMB
LASER
LCS
MPH
P-BE
P-D
P-LI7
P-T
PHOTO
POLIS
POLNS
POLTR
PU240
PU242
QMPH
REAC
SPALL
TAGD
THCOL
THRDT
VPH

Alpha-Beryllium
Annihilation radiation
Atomic beam source
Bremsstrahlung
Spontaneous fission of 252Cf
Spontaneous fission of 244Cm
Spontaneous fission of 246Cm
Spontaneous fission of 248Cm
Compton scattering
Deuteron-Beryllium
Deuteron-12C
Deuteron-14C
Deuteron-Deuterium
Deuteron-Lithium
Deuteron-7Li
Deuteron-14N
Deuteron-15N
Deuteron-Tritium
Evaporation neutrons
Nuclear explosive device
Hardened
Kinematically determined
Lamb-shift source
Laser scattering
Laser Compton scattered photons
Monoenergetic photons
Proton-Beryllium
Proton-Deuterium
Proton-7Li
Proton-Tritium
Photo-neutron
Polarized ion source
Polarized neutron source
Polarized target
Spont. fission of 240Pu
Spont. fission of 242Pu
Quasi-monoenergetic photons
Reactor
Spallation
Electron tagged
Thermal column
Determined by threshold technique
Virtual photons

73

EXFOR Basics

Dictionary 20: Additional Result Codes: used with the keyword ADD-RES.
A-DIS
AMFF
ANGD
COMP
DECAY
E-DIS
G-SPC
LD
N-SPEC
P-SPEC
POT
RANGE
RECIP
STRUC
THEO
TRCS
TTY-C
Z-DIS

Mass distribution
Angular momentum of fission fragments
Angular distribution
Comparison with calculated values
Decay properties investigated
Energy distribution
Gamma spectra
Level density
Neutron spectra
Proton spectra
Parameters of nuclear potential
Range of recoils measured
Reciprocal data
Nuclear structure data
TheoryTotal reaction cross section
Calculated thick target yield
Charge distribution

Dictionary 21: Method Codes: used with the keyword METHOD.
ABSFY
ACTIV
AMS
ANC
ASEP
ASPEC
ASSOP
BCINT
BGCT
BSPEC
BURN
CADMB
CHARG
CHRFL
CHSEP
COINC
DIFFR
DSCAT
EDE
EDEG
EXTB
FISCT
FLUX
FNB
FPGAM
GSPEC
HADT
HATOM
HE-AC
HEJET
INTB
JET
LRASY

74

Absolute fission yield measurement
Activation
Accelerator mass spectrometry
Asymptotic normalization constant
Separation by mass-separator
Alpha spectrometry
Associated particle
Beam current integrated
Beta-gamma coincidence technique
Beta ray spectrometryBurn-upCadmium bath
Measurements in gas discharge
Christiansen filter
Chemical separation
Coincidence
Diffraction
Double scattering
Particle identification by 'E/Delta E' measurement
Energy degradation by foils
Irradiation with external beamAbsolute fission counting
Neutron flux monitoring
Filtered neutron beam
Direct gamma-ray spectrometry
Gamma ray spectrometry
Heavy atom difference technique
Hot atom method
Helium accumulation method
Collection by He jet
Irradiation with internal beam
Collection by gas jet
Left-right asymmetry

EXFOR Basics

MAGFR
MANGB
MASSP
MOMIX
MOSEP
OLMS
PHD
PLSED
PSD
RCHEM
REAC
REC
REFL
RELFY
RINGR
RVAL
SFLIP
SHELT
SITA
SLODT
STATD
STTA
THERM
TOF
TRN
TROJA
TTM
XSPEC

Magnetic field rotation
Manganese bath
Mass spectrometry of a product
Mixed monitor
Separate monitor foil
On-line mass separation
Pulse-height discrimination
Pulse die-away
Pulse-shape discrimination
Radiochemical separation
Reactivity measurement
Collection of recoils
Total reflection from mirrors
Relative fission yield measurement
Ring ratio method
R-value measurement
Spin flip
Shell transmission
Single target irradiation
Slowing-down time
Statistically determined
Stacked target irradiation
Gas thermochromatographic separation
Time-of-flight
Transmission method
Trojan-horse method
Thick-target method
X-ray spectrometry75

EXFOR Basics

Dictionary 22: Detector Codes: used with the keyword DETECTOR.
BAF2
BF3
BGO
BPAIR
BUBLC
CEREN
COIN
COMPL
CSICR
D4PI
DRFTC
FISCH
GE
GE-IN
GELI
GEMUC
GLASD
HE3SP
HORBU
HPGE
IMPSI
IOCH
LEGE
LONGC
MAGSP
MCPLT
MOXR
MTANK
MWDC
MWPC
MWSC
NAICR
PGAC
PHVC
PLATE
PPAC
PROPC
PS
SCIN
SIBAR
SILI
SI
SISD
SOLST
SPEC
STANK
SWPC
TELES
TFBC
TRD
XHPGE

76

Scintillator BaF2
Boron Trifluoride neutron detector
Bismuth-Germanate crystal detector
Electron-pair spectrometer
Bubble chamber
Cerenkov detector
Coincidence counter arrangement
Compton Polarimeter
Cesium-Iodide crystal
4pi detector
Drift chamber
Fission chamber
Germanium detector
Germanium intrinsic detector
Germanium-Lithium detector
Geiger-Mueller counter
Glass detector
He-3 spectrometer
Hornyak button detector
Hyperpure Germanium detector
Passivated implanted planar Si detector
onization chamber
Low energy Germanium Detector
Long counter
Magnetic spectrometer
Microchannel plate
Moxon-Rae detector
Moderating tank detector
Multi-wire drift chamber
Multi-wire proportional counter
Multi-wire spark counter
Sodium-Iodide crystal
Parallel-grid avalanche detector
Photovoltaic Cell
Nuclear plates
Parallel plate avalanche counter
Proportional counter
Position sensitive detector
Scintillation detector
Silicon surface barrier detector
Silicon-Lithium detector
Silicon detector
Silicon strip detector
Solid-state detector
Large spectrometer system
Scintillator tankSingle-wire proportional counter
Counter telescopeThreshold detector
Track detector
Extended range Germanium gamma detector

EXFOR Basics

Dictionary 23: Analysis Codes: used under the keyword ANALYSIS.
4PI1A
AREA
CORAB
DECAY
DIFFR
DTBAL
INTAD
INTED
LEAST
MLA
PHDIF
PLA
REDUC
REGUL
RFN
SHAPE
SLA
THIES
TTUNF
UNFLD
WSP

4p times differential cross section at one angle
Area analysis
Correction for isotopic abundance
Decay curve analysis
Difference spectrum
Detailed balanceIntegration of angular distribution
Integration of energy distribution
Least-structure method
Multilevel analysis
Photon difference
Penfold-Leiss method
Reduction method
Regularization method
R-function formalism
Shape analysis
Single level analysis
Thies's method
Calculated from thick target using unfolding proced.
Unfolding procedure
Woods-Saxon potential77

EXFOR Basics

Dictionary 24: Data Headings: used at the beginning of the COMMON and DATA fields toindicate the significance of the variable given; also used under the keywords ASSUMED, MONITOR,
HALF-LIFE, MISC, and ERR-ANALYS as links to the data field.
The codes given in this dictionary may be followed by one of the following suffixes.
-1, -2, etc. 1st, 2nd, etc., value, when more than one defined-APRX
value is approximate-CMvalue is in center-of-mass (quantities without this suffix are in the laboratory
system-DN
value for denominator of a reaction ratio-ERR
uncertainty on value-ERR-DIG, -ERR-D Digitizing error-MIN
minimum value-MAXmaximum value-MEAN mean value-NMvalue for numerator of a reaction ratio-NRM
value at which data is normalized-RSL
resolution of value
ANAL-STEPANG
ANG-AZ
ANG-RL
ASSUM
COS
DATA
DECAY-FLAG
E
E-DGD
E-EXC
E-GAIN
E-LVL
E-LVL-FIN
E-LVL-INI
ELEMENTEN
EN-DUMMY
EN-RES
EN-RSL-FW
EN-RSL-HW
ERR
ERR-DIG
ERR-EDD
ERR-IDD
ERR-HL
ERR-S
ERR-SYS
ERR-T
FLAG
GRP-NUM
HL
IAS-NUMBISOMERKT
LVL
LVL-FLAG

78

Analysis energy step
Angle
Azimuthal Angle
Relative Angle
Assumed value, defined under ASSUMED
Cosine of angle
Value of quantity Specified under REACTION
Decay flag. link to information under DECAY-DATA
Energy of outgoing particle
Degradation in secondary particle energy vs. incident energy
Excitation energy
Gain in secondary particle energy vs. incident energy
Level energy
Final level of ? transition
Initial level of ? transition
Atomic number of element
Energy of incident projectile
Dummy incident projectile energy, for broad spectrum
Resonance energy
Incident projectile energy resolution (FWHM)
Incident projectile energy resolution (?? FWHM)
Systematic uncertainty, defined under ERR-ANALYS
Digitizing error (of DATA)
Error of energy value given under DECAY-DATA
Error of intensity value given under DECAY-DATA
Error of half-life value given under DECAY-DATA
Statistical uncertainty (1 s)
Total Systematic Uncertainty
Total uncertainty (1 s)
Flag, link to information under FLAG
Group number (of delayed neutrons)
Half-life of nuclide specified
Level Number of Isobaric Analog State
Isomeric state for nuclide given
Spectrum temperature
Level Energy as additional information
Level flag, link to information under LEVEL-PROPEXFOR Basics

LVL-NUMB

Level number

MASS
MASS-RATIO
MISC
MOM
MOM-SEC
MOM-TR
MOMENTUM L
MONIT
MU-ADLERNUMBERPARITY
PART-OUT
POL-BM
POL-TR
POLAR
q
Q-VAL
S
SPIN J
STAT-W G-t
TEMP
THICKNESS
WVE-LN

Atomic mass of nuclide
Ratio of atomic masses of fission fragments
Miscellaneous information, defined under MISC-COL
Linear momentum of incident projectile
Linear momentum of outgoing particle
Momentum transfer (in units MeV/c or equiv.)
Angular momentum (l) of resonance
Normalization value, for reaction given under MONITORµ (for Adler-Adler resonance parameters)
Fitting coefficient number
Parity (p) of resonance
Number of Emitted Particles
Beam polarization
Target polarization
Polarity
Momentum transfer, q
Q-value
Distance along S-curve for range of E1 and E2Spin (J) of resonance
Statistical-weight factor (g)4-momentum transfer squared
Sample temperature
Sample thickness
Wave length of incident particle

Dictionary 30: Process Codes: used in REACTION subfield 3, and simarly under ASSUMED and
MONITOR.
ABS
EL
F
FUS
INL
NON
PAI
SCT
TCC
THS
TOT
X

Absorption
Elastic scattering
FissionTotal fusion
Inelastic scattering
Nonelastic (= total minus elastic)
Pair production (for photonuclear reactions)
Total scattering (elastic + inelastic)
Total charge changing
Thermal neutron scattering
Total
Process unspecified

79

EXFOR Basics

Dictionary 33: Particle Codes: used in REACTION quantity subfields 2, 3, 7, and simarly under
ASSUMED and MONITOR. Also used under the keywords DECAY-DATA, DECAY-MON, PART-DET and
RAD-DET, and as the second field under the keywords EN-SEC, EMS-SEC, and MOM-SEC.
0
A
AN
AP
AR
B
B+
BD
DG
DN
E
EC
ER
ETA
FF
G
HCP
HE2
HE3
HE6
HF
ICE
K
KN
KP
LCP
LF
N
P
PI
PI0
PIN
PIP
PN
RSD
SF
T
XR

80

(no incoming/outgoing particle)
αAntineutrons
Antiprotons
Annihilation radiation
Decay βDecay β+Decay βDeuterons
Decay γDelayed neutrons
Electrons
Electron capture
Evaporation Residues
Eta mesons
Fission fragmentsγ
Heavy Charged Particle
2
He
3
He
6
He
Heavy fragment
Internal-conversion electrons
Kaons,unspecified
Kaons,negative
Kaons,positive
Light charged particle (Z<7)
Light fragment
Neutrons
Protons
π, unspecifiedπ, neutral
ππ+Prompt neutrons
Residual nucleus
Fragments from spontaneous fission
Tritons
X-raysEXFOR Basics

Dictionary 34: Modifier Codes: used in REACTION the 4th quantity subfield (REACTION SF8),and similarly, under ASSUMED and MONITOR.
(A)
1K2
2AG
2G
2L2
2MT
2PT
4AG
4PI
A
AA
AG
AL1
AMP

uncertain if corrected for natural isotopic abundance
form: k2 dσ/dΩ = Σ (a(L)*p(L))
times 2 * isotopic abundance and statistical weight factor
times 2 * staistical weight factor
form: dσ/dΩ = 1/2 Σ (2L+1)*a(L)*p(L)times 2p * transverse secondary mass
times 2p* transverse secondary momentum
times 4 * isotopic abundance and statistical weight factor
times 4πtimes natural isotopic abundance
Adler-Adler formalism
times isotopic abundance and statistical weight factor
Associated Legendre polynomials of the first kind
Amplitude (for resonance parameters)

ANA analyzing power
ASY
AV
BRA
BRS
C
COS
CS2
D
DSP
DT
EPI
FCT
FIS
FST
G
K
L4P
LEG
LIM
MOT
MSC
MXW
NCP
NSF
PHY
PP
RAW
REL
RES
RG
RM
RMT
RNV
RS
RS0
RSD
RSL
RTE
RTH
RV
S0

asymmetry of polarization of outgoing particles
average
Bremsstrahlung spectrum average
average over part of Bremsstrahlung spectrum
Spin correlation parameter
Cosine coefficients
form: a0 + a1*sin2 + a2*sin2*cos + a3*sin2*cos2
Spin rotation parameter
Difference for spins parallel - antiparallel
production thick/thin target yield
epi-thermal neutron spectrum averagetimes a factor (see text)
fission spectrum average
fast reactor neutron spectrum averagetimes statistical weight factor
Spin transfer parameter
form: 4π ds/dΩ = Σ (2L+1)*a(L)*p(L)Legendre coefficients
given for a limited energy range
relative to Mott scattering
approximate definition only (see text)
Maxwellian average
Non-coplanar
Non-spin-flip
Physical yield
Incident projectile parallel/perpendicular to reaction plane
raw data (see text)
relative dataat peak of resonancetimes (2J(i)+1) * (2J(j)+1)
Reich-Moore formalism
R-matrix formalism
non-1/v parttimes 4π/σ
(dσ/dΩ)/(dσ/dΩ at 0°) = Σ a(L)*p(L)relative to 90° data
form: (4p/σ)*(dσ/dΩ) = Σ (2L+1)*a(L)*p(L)times square-root(E)relative to Rutherford scattering
1/v part only
times total peak cross section

81

EXFOR Basics

S2T
SF
SFC
SN2
SPA
SQ
SS
TAP
TM
TST
TT
VAP
VGT

form: dσ/dΩ = a0 + a1*sin2(T) + a2*sin2(2*T)
Spin flip
S-factor
sum in the power of sin2
spectrum averagequantity squared
spin-spin
Tensor analyzing power, spherical coordinates
per 1 MeV target thickness (for thick target yields)
Total spin transfer
measured for thick target
Vector analyzing power, spherical coordinates
Vogt formalism

Dictionary 35: Data Type Codes: used in REACTION subfield 9.
CALC
DERIV
EVAL
EXP
RECOM

Calculated data
Derived data
Evaluated data
Experimental data (default)
Recommended data

Dictionary 37: Result Codes: used with the keyword RESULT.
DFRCT
FRCUM
FRIND
RVAL

Delayed neutron fraction
Fractional cumulative yield
Fractional independent yield
R-value

Dictionary 207: Books: used as the second subfield for the keyword REFERENCE, when thereference type is given as B, and similarly, for MONIT-REF, and REL-REF. A subset containingsome of the most frequently used codes is given here.
ACT.EL
EXP.NUC.P.
FAST N.PH.
NB.GS.COMP
NEJTRONFIZPR.NUC.EN.
RCS
SPN
TRANSU.EL.

82

Actinide Elements
Experimental Nuclear Physics
Fast Neutron Physics
Noble Gas Compounds, Chicago Press 1963
Neitronnaya Fizika, Moskva 1961
Progress in Nucl.Energy
Radiochemical Studies, Fission Products
Sov.Progr.in Neutr.Phys.,New York 1961
Transuranium Elements

EXFOR Basics

Dictionary 236: Quantity Codes: used for quantity (REACTION subfields 5-7), and simarlarly
under ASSUMED and MONITOR. They may be combined with modifier codes from Dictionary 34
to form the complete quantity string; if more than one code applies, they are separated by /(slash). The code * in the 3rd field (SF7) signifies that any particle code from Dictionary 33 may
be given in place of the character.
The following branch codes may appear at the beginning of the string:CUM
cumulative(CUM)
uncertain if reaction is cumulative
IND
independent formation of productM+
including decay from metastable state
Mexcluding decay from metastable state(M)
uncertain if decay from metastable state included.
PAR
partialSEQ
given for reaction sequence specified
UND
reaction is undefined, only the sum of outgoing nucleons is known.
(DEF)
Compiler is uncertain whether the reaction is defined.
Branch codes used for analyzing power / polarization:
20,21,22,31,32,33
Coefficients T20, T21, T22, etc., for analyzing power
LL
Longitudinal-longitudinal (zz) component
LS
Longitudinal-sideward (zx) component
NL
Normal-longitudinal (yz) component
NN
Normal-normal (yy) component
SL
Sideward-longitudinal (xz) component
SS
Sideward-sideward (xx) component,AG,,AA,AH,,AA,AKE,AKE/DA,*
,ALF
,AMP
,AP
,AP,*
,ARE
,COR
,COR,*/*,COR,*/*/*
,D
,DA
,DA,*
,DA/CRL,DA/DA,DA/DA,*/*,DA/DA/DE,DA/DA/DE,*/*/*,DA/DE,DA/DE,*,DA/DE/DE,*/*/*,DA/KE,*,DA/TMP,*,DA/TYA,P

Adler-Adler symmetry coefficient
Adler-Adler asymmetry coefficient
Average kinetic energy of outgoing particle
Avgerage kinetic energy of fission fragment at given angle
Capture-to-fission cross section ratio
Scattering amplitude
Most probable mass of fission products
Most probable mass of fragment specified
Resonance area
Angular correlation
Angular correlation between particles specified
Angular correlation between particles specified
Average level spacing
Differential cross section with respect to angle
Differential cross section with respect to angle for particle specified
Angular correlation
Double differential cross section d2σ/dΩ/dΩDouble diff. cross section d2σ/dΩ(*1)/dΩ(*2)
Triple diff.cross section d3σ/dA/dO/dE
Triple diff.cross section d3σ/dΩ(*1)/dO(*2)/dE(*3)
Double diff.cross section d2σ/dΩ/dE
Double diff.cross section d2σ/dΩ/dE of particle specified
Triple diff.cross section d3σ/dΩ(*1)/dE(*2)/dE(*3)
Kinetic energy of fission fragment specified with respect to angle
Differential cross section, temperature dependent
Differential cross section with respect to Treiman-Yang angle

83

EXFOR Basics,DA2/DE2,*/*
,DE
,DE,*
,DP
,EN
,ETA
,ETA/NU,FM/DA,FM2/DA,INT,IPA,IPA/DE,IPA/DP,IPP/DA,J,KE,*,KE/CRL,LF/HF,KEM,*,KEP,*
,KER
,L
,LDP
,MCO
,MLT
,MLT,*,MLT/DA,MLT/DE
,NU
,PHS
,PN
,POL
,POL,*,POL/DA,POL/DA,*,POL/DA/DA/DE,,ANA,POL/DA/DE,POL/DA/DE,,ANA,POL/DA2/DE2,*/*,ANA,POL/DT,,ANA,PTY,PY,PY/DA,PY/DA/DE,PY/IPA
,RAD
,RI
,SCO
,SGV
,SIF
,SIF/TMP,SIG,SIG,*,SIG/RAT,SIG/TMP,SPC,SPC/DA
,STF
,SWG
,TEM
,TRN

84

Quadruple differential cross section
Energy spectrum of outgoing particles
Energy spectrum of particle specified
Diff. cross section with respect to linear momentum
Resonance energy
Neutron yield (η)η /⎯νAngular distribution, of 1st kind
Spin-polarization probability of 1st kind
Cross-section integral over incident energy
Diff.cs integrated over partial angular range
Double-diff.cs integr.over partial ang.range
Double-diff.cs d2/dp/dA integr.over partial ang.range
Double-diff.cs d2/dp/dA int.over part.mom.range
Spin J
Kinetic energy of fission fragments specified
Total kinetic energy of light/heavy frag. pair
Temp.of Maxwell.distr.of outgoing particles
Most probable kinetic energy of outgoing particles
Kerma factor
Momentum l
Level density parameter
Linear momentum correlation
Multiplicity of outgoing particle
Multiplicity of particle specified
Particle multiplicity d/dA
Particle multiplicity d/dE
Total neutron yield (⎯ν)
Relative phase
Delayed neutron emission probability
Spin-polarization probability
Spin-polarization probability of particle specified
Spin-polarization probability dσ/dΩDiff. spin-polarization probability dσ/dΩ of particle specified
Analyzing power dA1/dA2/dE1
Diff.spin-pol.probab.w.resp.to angle and energy
Analyzing power / dE
Analyzing power d4/dA(*)/dA(*)/dE(*)/dE(*)
Analyzing power with respect to 4-momentum transfer
ParityProduct yield
Differential product yield d/dA
Differential product yield d/dA/dE
Product yield d/dA, integrated over partial angular range
Scattering radiusResonance integral
Spin-cut-off factor
Reaction rate (s*velocity)
Self-indication function
Temperature-dependent self-indication function
Cross section
Cross section for production of particle specified
Cross section ratio
Temperature-dependent cross section
Gamma spectrum
Gamma spectrum as function of angle
Strength function
Statistical weight factor g
Nuclear temperature
Transmission

EXFOR Basics,TRN/TMP,TTT,TTT/DA,TTY,TTY/DA,TTY/DA/DE,TTY/DE,TTY/MLT,TTY/MLT/DA,TTY/MLT/DA/DE,TTY/MLT/DE,TTY/PY,TTY/PY/DA,TTY/PY/DA/DE,WID,WID/RED,WID/STR
,ZP
1,WID
2,DE
2,WID
3,WID
4,WID
BA,AMP
BA,SIG
BA,SIG/TMP
BA/COH,AMP
BA/PAR,AMP
BIN,AKE,*
BIN,AP,*
BIN,SIG
BIN/TER,DA/RAT,*BIN/TER,SIG/RAT
CHG,FY
CHG,FY/DE
CHN,FY
CHN,FY/DE
CHN,SIG
CN,DA
CN,FY
CN,NU
CN,PY
CN,SIG
CN/PAR,SIG
COH,AMP
COH,SIG
CON,SIG
CUM,FY
CUM,FY/RAT
CUM/TER,FY
DI,DA
DI,DA/DE
DI,DE
DI,SIG
DIS,SIG
DL,AKE,*
DL,DE,*DL,NU
DL,SIG,*DL,SPC

Transmission, temperature dependent
Thick-target yield per unit timeThick-target yield per unit time dY/dΩThick-target yield
Differential thick target yield dY/dΩ
Differential thick target yield dY/dΩ/dE
Differential thick target yield dY/dE
Particle multiplicity for thick target, as fct. of beam current
Thick target particle multiplicity d/dA, as fct. of beam current
Thick target particle multiplicity d2/dA/dE, as fct. of beam current
Thick target particle multiplicity d/dE, as fct. of beam current
Thick-target product yield, as fct. of beam current
Thick-target product yield d/dA, as fct. of beam current
Thick-target product yield d2/dA/dE, as fct. of beam current
Resonance width, Γ
Reduced width, Γ0Resonance strength
Most probable charge of fission products
Resonance width for channel 1
Energy spectrum of 2nd secondary particle
Resonance width for channel 2
Resonance width for channel 3
Resonance width for channel 4
Bound-atom scattering amplitude
Bound-atom cross section
Bound-atom cross section, temperature dependent
Bound-atom coherent scattering amplitude
Partial bound-atom scattering amplitude
Average kinetic energy of fission fragment specified
Most prob. mass of fission fragment specified in binary fission
Binary fission cross section
Binary/ternary differential dist. dσ/dΩ of fission fragment specified
Binary/ternary cross section ratio
Total element yield of fission products
Total element fission yield, differential dY/d(fragment energy)
Total chain yield of fission products
Total chain fission yield, differential dY/d(fragment energy)
Total chain yield cross section f. fission products
Differential cross section dσ/dΩ, compound nucleus contribution
Fission-product yield, compound nucleus contribution?v, compound nucleus contribution
Product yield, compound nucleus contribution
Cross section, compound nucleus contribution
Partial cross section, compound nucleus contribution
Coherent scattering amplitude
Coherent cross section
Production cross section for continuous gammas
Cumulative fission-product yield
Cummulative fission-product yield isomeric ratio
Cumulative fission product yield for ternary fission
Differential c/s dσ/dΩ, direct interaction contribution
Double diff. c/s d2σ/dΩ/dE, direct interaction contribution
Energy spectrum of outgoing particles, direct interaction contrib..
Cross section, direct interaction contribution
Production cross section for discrete gammas
Average kinetic energy of delayed particle specified
Delayed energy spectrum of particle specified
Delayed neutron yield
Delayed emission cross section of particle specified
Intensity of delayed gammas

85

EXFOR Basics

DL/GRP,AKE,N
DL/GRP,DE,N
DL/GRP,NU
DL/GRP,SIG,N
DL/PAR,AKE,*
DL/PAR,DE,*
DL/PAR,NU
DL/PAR,SIG,*
EM,DA
EM,DA/DE
EM,DE
EM,POL/DA/DE,,ANA
EM,SIG
EM/PAR,POL/DA
EP,DA
EP,SIG
EP/PAR,INT
FA,AMP
FA,SIG
FA,SIG/TMP
FA/COH,SIG
FA/INC,SIG
FIS,AKEFIS,SIG
HEN,SIG
INC,AMP
INC,SIG
IND,FY
IND,FY,*
IND,FY/DE
IND,FY/RA
IND/TER,FY
LEN,SIG
LON,POL,,DSP/ASY
LON,POL/DA,,ANA
LON,SIG,,DSP
LON,SIG,,SS
LP,DP
LP,IPA/DP
MAS,FY
MP,SIG
MP,STF
NUM,NU
NUM,PYNUM,SIG,*
PAR,DP,*+*
PAR,FY/DE,LF/HF
PAR,INT/DA,*
POT,RAD
POT,SIG
PR,AKE,N
PR,AKE/DE,N/FF
PR,COR,N/N
PR,COR/DE,N/FF
PR,DA,*
PR,DA/DE,N
PR,DE,N
PR,KE/CRL,N/HF
PR,KEM,N
PR,NU

86

Average kinetic energy for specific delayed neutron group
Energy spectrum for specific delayed neutron group
Delayed neutron yield for given half-life group
Delayed neutron emission cs for given half-life group
Average kinetic energy for specified delayed particle group
Energy spectrum for specific delayed particle group
Partial yield of delayed neutrons
Partial delayed emission cross section for particle specified
Particle emission angular distribution
Double differential emission cross section, dσ/dΩ/dE
Particle emission energy spectrum
Analyzing power / dE for particle emission
Emission cross section (excluding elastic scattering)
Partial emission diff.spin-polar.prob.
Partial differential cross section dσ/dΩ for electric polarity
Cross section for electric polarity
Cross section integral over incident energy for electric polarity
Free-atom scattering amplitude
Free-atom cross section
Free-atom cross section, temperature dependent
Free-atom coherent scattering cross section
Free-atom incoherent scattering cross section
Avg.kin.energy of outg.part.for high en.fission
Partial cross section due to high-energy fission'High-energy' component of cross section
Incoherent scattering amplitude
Incoherent scattering cross section
Independent fission yield
Independent yield of particle specified from prompt fission prod.
Differential independent fission yield dY/d(fragment energy)
Independent fission yield ratio
Independent fission yield for ternary fission'Low-energy' component of cross section
Spin-spin asymmetry for longitud. spin states
Longitudinal analyzing power A(z)Cs diff.(longit.spins, parallel - antiparallel)
Spin-spin cs, longitudinal to beam direction
Diff. cs with respect to longitudinal secondary momentum
Cross section diff.by long.sec.lin.mom.,integr.over part. ang.range
Mass yield of fission fragments as sum of independent yields
Cross section for magnetic polarity given
Strength function for magnetic polarity given
Probability for emission of N neutrons
Probab. for the production of N product particles
Cross section for production of specified no. of particle specified
Diff.cs with respect to secondary momentum of particle pairFission product yield at given light and heavy fragment energy
Integral over incident en. of partial diff. c/s, dσ/dΩ, of particle specified
Potential scattering radius
Potential scattering cross section
Average kinetic energy of prompt neutrons
Average energy of prompt neutrons dep.on fiss.fragment energy
Angular correlation of prompt neutrons
Angle-energy correlation of prompt neutrons with fission fragments
Differential cross section, dσ/dΩ of prompt particles
Double differential cross section of prompt neutrons, d2σ/dΩ/dE
Energy spectrum of prompt fission neutrons
Energy correlation neutron / heavy fission fragment
Temperature of Maxwellian distribution of prompt neutrons
Prompt neutron yield (⎯ν)

EXFOR Basics

PR,NU/DE,FF
No.of prompt neutrons emitted by fiss. fragments of given E
PR/NUM,NU
Probability for emission of N prompt neutrons
PR,SIG
Prompt cross section
PR,SPC
Intensity of prompt gammas
PR/PAR,NU
Partial prompt neutron yield (⎯ν)
PR/TER,DA,N
Ang.dist.of prompt neutrons from ternary fission
PR/TER,NU
Prompt⎯ν for ternary fission
PR/TER,NU/DE,A
Prompt⎯ν for ternary fission as a function of alpha energy
PR/TER,SPC
Prompt gamma spectrum from ternary fission
PRE,AKE,*
Average kinetic energy of fragment specified
PRE,AKE/DA,FF
Average kinetic energy of primary fragm., function of angle
PRE,AP,*
Most probable mass, pre-neutron-emission, of fragment specified
PRE,AP/DA,FF
Centr.of mass distr. of primary fiss.fragm.,dep. on angle
PRE,DA,*
Differential cross section, dσ/dΩ, of primary fragments specified
PRE,DA/KE,*
Kinetic energy distribribution, dσ/dΩ, of primary fragment specified
PRE,DA/TMP,FF
Ang. distr. of primary fiss. fragm., temperature dependent
PRE,DE,*
Energy spectrum of primary fragments specified
PRE,FY
Primary fission yield
PRE,FY/CRL
Primary fission product yield of correlated fragment pairs
PRE,FY/DE
Primary fission yield dY/d(kinetic energy)
PRE,KE,*
Kinetic energy of primary fragments specified
PRE,KE/CRL,*/*
Total kinetic energy of primary fragment pair
PRE/BIN,FY
Primary fission yield, binary fission
PRE/TER,AKE/CRL,A/FF Avg.kin.energy of ternary alphas correl.with prim.fragm.energy
PRE/TER,FY
Primary fission yield, ternary fission
PRE/TER,KE/CRL,FF/A
Energy correlation prim.fragment/tern.alphas
PRE/TER,KEP/CRL,A/FF Most probable energy of alphas correl.with prim.fragm.energy
PRE/TER/PAR,FY/CRL,A/FF
Yield of alphas of giv.energy correl.w.prim.fragm.energy
QTR,FY
Fission-product yield, quaternary fission
QTR,KE
Kinetic energy for quaternary fission
SEC,AKE,FF
Average kinetic energy of post-neutron-emission fragment
SEC,AP,*
Most probable mass of post-neutron-emission fragment specified
SEC,FY
Post-neutron-emission fission yield
SEC,FY/CRL
Post-neutron-emission yield of correl.fragm.pairs
SEC,FY/DE,HF
Post-neutr.emiss.heavy fiss.fragm.yield ,diff.w.fragm.kinet.energy
SEC,ZP
Most probable charge of fission fragment, post-neutron-emission
SEC/CHN,FY
Pre-delayed-neutron chain yield
SEC/CHN,FY/DE
Pre-delayed-neutron chain yield dY/d(kinetic energy)
SPL,AKE
Average kinetic energy of spallation products
SPL,SIG
Partial cross section due to spallation
TER,AKE,*
Average kinetic energy of particle specified, ternary fission
TER,AP
Most probable mass of fragment, ternary fission
TER,AP,*
Most prob. mass of ternary fission fragment specified
TER,COR,*/*
Angular correlation of particle *1 & particle *2, ternary fission
TER,DA,*
Differential cross section, dσ/dΩ, of particle specified, ternary fission
TER,DA/DE,*
Double-diff. cross sect. d2σ/dΩ/dE of particle spec., ternary fission
TER,DA/KE,*
Kinetic energy distrib., dEkin/dΩ, of particle specified, ternary fission
TER,DE,*
Energy spectrum of particle specified, ternary fission
TER,FY
Fission yield, ternary fission
TER,FY,*
Fission yield of fragment specified, ternary fission
TER,FY/CRL,*/*F(particle)/(fragment) correl., ternary fission
TER,KE
Kinetic energy for ternary fission
TER,KEP,*
Most probable kin.energy of ternary fission particle
TER,SIG
Cross section, ternary fission
TER,SIG,*
Cross section of particle specified, ternary fission
TER,ZP
Most probable charge of fragment, ternary fission
TER/BIN,FY/RAT,*
Ternary/binary fission particle yield ratio
TER/BIN,SIG/RAT
Ternary/binary fission cross section ratio
TER/CHG,FY
Total element yield of fiss.prod.,ternary fiss.
TER/PAR,MLT,G/LCP
Gamma mult.,tern.fiss.with light charged part.energy given

87

EXFOR Basics

TP,DP
TRS,POL/DA,,ANA
TRS,SIG,,DSP
UNW,INTUNW,SIG88

Diff.cs w.resp.to transv.secondary momentum
Transverse vector analyzing power, A(x)Cs difference (transv.spins, parallel - antiparallel)
Unweighted prod.cs integral over incid.energy
Unweighted production cross section