Nuclear Data Services
Evaluated Nuclear Data Library Descriptions
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General Purpose Libraries
Russian evaluated neutron data library, issued in 1992
and updated in 1993. The library is in ENDF-6 format and contains data
for 121 materials from 1-H-1 to 96-Cm-244.
Chinese Evaluated Neutron Data Library issued in 1991,
updated and supplemented in 1993 and 1995. The library is in ENDF-6 format
and contains data for 67 materials from 1-H-1 to 98-Cf-249.
The US evaluated nuclear data library released in December 2006. The library is divided into the following 14 sublibraries:
- N - Incident neutron library (393 materials)
- P - Incident proton library (48 materials)
- D - Incident deuteron library (5 materials)
- T - Incident triton library (3 materials)
- HE3 - Incident 3He library (2 materials)
- GN - Photo-nuclear data (163 materials)
- GAI - Photo-atomic interaction data (100 materials)
- RDD - Radioactive decay data (3838 materials)
- TSL - Thermal scattering law data (20 materials)
- SFY - Spontaneous fission product yields (9 materials)
- NFY - Neutron-induced fission product yields (31 materials)
- STD - Standard cross sections (8 materials)
- EAD - Electro-atomic interaction data (100 materials)
- AR - Atomic relaxation data (100 materials)
The library is in ENDF-6 format and contains data for about 400 materials from
1-H-1 to 100-Fm-255. The reference to the ENDB/B-VII.0 library is Nuclear Data Sheets, Vol. 107, 12(2006).
More information
The Joint Evaluated Fission and Fusion File (JEFF-3.1) is an evaluated library produced via an international collaboration of Data Bank member countries co-ordinated under the auspices of the NEA Data Bank. The general purpose library contains neutron reaction data, incident proton data and thermal neutron scattering law data. JEFF-3.1 contains also special purpose files with radioactive decay data, activation data and fission yields data. JEFF-3.1 combines the efforts of the JEFF and EFF/EAF working groups who have contributed to this combined fission and fusion file. General information on the JEFF and EFF/EAF projects is also available on the NEA website. The JEFF-3.1 documentation can be found in JEFF Report 21, "JEFF-3.1 Nuclear Data Library", published by the NEA in November 2006.
This general purpose library was released in May 2005 and contains:
- Incident Neutron Data for 381 materials from 1-H-1 to 100-Fm-255.
- Thermal Scattering Data for 9 materials.
- Incident Proton Data for 26 materials.
Japanese Evaluated Neutron Data Library, released in
2002. The library is in ENDF-6 format and
contains data for 337 materials from 1-H-1 to 100-Fm-255.
More information
International Neutron cross-section standards are important in the measurement and evaluation of all other
neutron reaction cross-sections. Not many cross-sections can be defined as absolute - most cross-sections
are measured relative to the cross-section standards for normalization to absolute values.
The need to re-evaluate the cross-section standards at the beginning of the 21st century is based on the appearance
of a significant amount of precise experimental data and developments in the methodology of analysis and evaluation.
The evaluations of the neutron cross-section standards were finalized in October 2005.
The new evaluations of the cross-section standards also include covariance matrices of the uncertainties
that contain fully justifiable values. Significant contributions to the experimental database were made by
participants of the WPEC Subgroup 7.
More information
Special Purpose Libraries
Russian activation data library released in 1993. The
library contains 20,049 excitation functions of reactions on stable and
unstable targets for neutron energies up to 20 MeV. The library is in
a psuedo ENDF-6 format - i.e. generally follows ENDF formatting rules,
but with some modifications to allow description of reactions leading
to metastable states.
More information
The Evaluated Atomic Data Library of the Lawrence Livermore
National Laboratory, USA, was released in 1992 in the ENDL format. It
contains evaluated atomic subshell and relaxation data for isolated neutral
atoms, including fluorescence yields, subshell parameters(e.g. binding
energies), both radioactive and non-radioactive transition probabilities,
and energy deposition terms.
The European Activation File, EAF-2007
The European Activation File (EAF) is an extensive data library prepared for the
European Activation System (EASY).
The latest EAF library, EAF-2007, contains a suite of sublibraries. The neutron data library contains 65,565 excitation functions involving 816 different
targets from 1H to 257Fm, atomic numbers 1 to 100, in the energy range 10-5 eV to 60 MeV.
The EAF-2007 library includes also deuteron-induced data (66,864 reactions) and proton-induced data (67,925 reactions).
The EAF decay data library contains nuclear properties of 2,231 nuclides, such as spin, decay modes,
half-life and mean decay energies.
The EAF biological, clearance and transport libraries are also included. The data contains biological,
clearance and transport coefficients of all the 2,004 radionuclides in the libraries, such as activity,
committed effective doses per unit uptake for ingestion and inhalation, the source of the biological data,
the transport coefficient (A2) and the clearance level value.
Order DVD for free containing EAF-2007, as well as EAF-2001, EAF-2003 EAF-2005, and
EAF-2005.1 (an updated and extended release of EAF-2005). The complete documentation of the different
libraries is also included (in pdf format).
More information
The Evaluated Electron Interaction Data Library of the
Lawrence Livermore National Laboratory, USA, was released in 1992 in the
ENDL format. It contains energy-dependent evaluated electron interaction
cross-section data and related parameters for all elements from 1-H to
100-Fm for incident electon energies from 10 eV, or threshold, to 100
GeV.
The European Fusion File contains data for 80 materials
of interest for fusion neutronic design calculations, from 1-H-1 to 83-Bi-209.
Although the file comforms to the legal ENDF-6 format, the "original"
file contains data in such detail that difficulties may occur during processing
of the data. Hence, some of the evaluations have also been provided in
a "user's version" with lumped reaction mechanisms to allow processing
without any difficulty.
The Evaluated Photon Interaction Data Library of the
Lawrence Livermore National Laboratory, USA, was released in 1992 in the
ENDL format. It contains complete information for particle-transport for
z = 1 to 100 for incident photon energies from 10 eV, or threshold, to
100 GeV.
Fusion Evaluated Nuclear Data Library (FENDL-2.1)
FENDL-2.1 is a comprehensive nuclear data library for fusion applications, developed
in the frame of the international effort coordinated by the IAEA Nuclear Data Section.
FENDL-2.1 consists of 71 materials relevant for fusion. Processed data (300 K) is also available.
The library was released in December 2004.
More information
The International Reactor Dosimetry File (IRDF-2002) was released in 2002.
The objective of the project was to prepare and distribute a standardised, updated and benchmarked evaluated
cross section library of neutron dosimetry reactions with uncertainty information (IRDF-2002) for use in
lifetime management assessments of nuclear power reactors and other applications.
Within the scope of the project the following tasks were considered:
-Intercomparison of reactor dosimetry cross-section data and their uncertainties in various libraries
including IRDF-90.2, JENDL/D-99 and RRDF-98.
-Reaction rates in a standard neutron field were compared. Select best data based on the above comparison of
data for IRDF-2002.
-Evaluate and test new reaction cross sections requested by the reactor dosimetry community for extension of
the database. Include evaluated decay radiation characteristics in the files.
-Comparison of experimental and calculated fission and thermal spectrum averaged cross sections.
More information
The JEFF 3.1/A library is the Activation Data Library in ENDF-6 format
prepared from the European Activation File (EAF-2003).
The JEFF-3.1/A library contains 12,617 excitation functions involving 774 different
targets from 1H to 257Fm, atomic numbers Z=1-100, in the energy range
10-5 eV to 20 MeV.
Uniquely, an uncertainty file is also provided that quantifies the degree of
confidence placed on the data for each reaction channel.
More information (PDF-document)
JEFF-3.1/RDD (Updated Nov 2007: JEFF-3.1.1/RDD)
The JEFF-3.1 Radioactive Decay Data (RDD) library contains 3,852 nuclides from the neutron to 272Rg.
and is described in detail in JEFF report 20 (to be published in 2008). The basis for the selection of isotopes were taken from
the NUBASE-2003 file, which contains basic nuclear properties, hence all known isomers were identified
from here. Three evaluated libraries, UKPADD-6.4, UKHEDD-2.4 (from the UK) and DDEP (from Laboratoire National Henri
Bequerel (LNHB) at Saclay, France, were used instead of NUBASE-2003 for almost 600 nuclei. About 900 nuclei were also selected from the
ENSDF library.
An updated Radioactive Decay Data Library, JEFF-3.1.1/RDD, was released in November 2007. 59 Isotopes were modified and minor corrections where made.
More information
The fission product yield libraries include independent and cumulative yields for the
neutron-induced fission of 232Th, 233,234,235,236,238U, 237,238Np, 238,239,240,241,242Pu, 241,242m,
243Am, 243,244,245Cm and the spontaneous fission of 242,244Cm and 252Cf.
The data represent a development of the UKFY3 file. The principle changes from earlier libraries includes;
an extended experimental database, calculation of the cumulative yields using the JEFF-3.1 decay data,
improved calculation of uncertainties in the yields, improved adjustment to the physical constraints
and the inclusion of new ternary yield data for 3H and 4He from Serot, Wagemans et al,
"New Results on Helium and Tritium Gas Production From Ternary Fission", ND2004,AIP,CP-769,857(2005).
More information
The Medium Energy Nuclear Data Library (MENDL) is a neutron
reaction data library for nuclear activation and transmutation at intermediate
energies. The library contains, for 505 stable and unstable target nuclides,
production cross-sections for the formation of radioactive product nuclides
for incident neutrons with energies up to 100 MeV. The nuclide cover the
range from 13-Al-26 to 84-Po-210 with half-lives larger than one day,
and contains data for 57500 threshold reactions. The format generally
follows ENDF formatting rules,
but with a free choice of MT number to identify different reactions.
More information
To satisfy the increasing needs of nuclear data at intermediate energies the Proton Activation
Data File (PADF-2007) has been generated. It contains 418,575 excitation functions of nuclear reactions for 2355 target
nuclei from Mg to Ra at proton energies up to 150 MeV. The data are given for stable and unstable target nuclei
including isomeric targets with half-lifes more than one second. The cross-sections were obtained on the basis of model
calculations using the TALYS and the ALICE/ASH codes and available experimental data.
More information
The Russian Reactor Dosimetry File, RRDF-98, contains evaluations of cross section data performed at the
Institute of Physics and Power Engineering, Obninsk, for 22 neutron induced dosimetry reactions:
12C(n,2n), 16O(n,2n), 19F(n,2n), 24Mg(n,p), 46Ti(n,2n),
46Ti(n,p), 47,48,49Ti(n,x), 48Ti(n,p),51V(n,α), 54Fe(n,2n),
54Fe(n,α), 56Fe(n,p), 59Co(n,α), 63Cu(n,α),
75As(n,2n), 93Nb(n,2n), 93Nb(n,n'), 103Rh(n,n'),
115In(n,n'), 141Pr(n,2n). The dataset also contains the corresponding covariance matrices.
For estimation of correlations between experimental data the total uncertainties of measured cross sections
have been separated into statistical and systematic parts and correlation coefficients between components of
systematic parts were assigned according to information given in the original publications and EXFOR library.
Then the correlation matrix of cross sections measured within one experiment was calculated and approximated by
matrix with a constant (average) correlation coefficient. The overall correlation matrix was composed of such
submatricies in the assumption that the cross sections measured in different experiments do not correlate with
each other. It should be noted that such procedure of the statistical analyses guarantees positive definiteness
of the covariance matrices of evaluated cross sections.
The library is in ENDF-6 format (MF=3 and MF=33).
The UKFY-4.1 library extends the UKFY-4 library to include photon induced fission, and spontaneous fission yields
for 39 nuclides identified in the JEFF-3.1.1 decay data library as undergoing spontaneous fission. It should be noted that heavier
nuclides exist that spontaneously fission, but due to their short half-lives and extremely low production in applied science it was
decided to ignore them. The library was produced using the CYFP code from LANL, but with some modifications to allow the photon induced
and spontaneous fission to be handled easily.
In addition to the extra data, the UKFY-4.1 cumulative yields have been made consistent with
the JEFF-3.1.1 decay data. It should be noted that this calculation of cumulative yields
ignored decays from nuclides with half-lives of greater than 1000 years, as in the JEFF-3.1
fission yield library.
The library is in ENDF-6 format.
The UK Heavy Element Decay Data library (UKHEDD)
contains recommended decay data for 125 actinides that constitute reactor fuels and are formed through an extensive
series of neutron reactions prior to and including their natural radioactive decay. No new evaluations have been undertaken
for this release, with the changes being confined to the basic structure of the files.
The library is in ENDF-6 format.
More information
The UK Activation Product Decay Data library (UKPADD)
contains radioactive decay data for 573 activation products (including
some fission products). The library is in
ENDF-6 format.
More information
The Waste Incineration Nuclear Data library (WIND) contains
evaluated data for 576 neutron induced fission and threshold reactions
for isotpes of U, Np and Pu, and one file containing data for 32 proton
induced reactions for U-238, in the energy range up to 100 MeV. The format
generally follows ENDF formatting rules,
but with a free choice of MT number to identify different reactions.
More information
Older Nuclear Data Libraries
This library, released in 1982, was part of the ENDL
library. It contains neutron activation cross-sections for 255 targe nuclei
for incident energies up to 20 MeV.
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The 1974 version of the US Evaluated Nuclear Data library
(ENDF/B) library conatins neutron reaction data and differential data
for 90 materials in the energy range 10-5 eV to 20 MeV. The
library is in ENDF-4 format.
US Evaluated Nuclear Data Library of 1979. The library is structured according to tapes, with the following allocations:
- 509 - fission product yields
- 510 - fission product yields
- 511 - standard materials
- 514 - actinides
- 521 - actinides
- 522 - actinides
- 531 - dosimetry
- 532 - activation
- 533 - neutron cross-sections only, gas production file
- 541-546 - fission product file
- 564 - special purpose activation (on 532)
- 565 - special purpose actinide (on 521 + 522)
- 566 - special purpoe fission product (on 541 - 546)
- 567 - update of 509
- 568 - update of 510, 511, 514
US evaluated nuclear data library released in 1990, with revisions in 1991, 1993, 1995, 1996, 1998, 1999, 2000 and 2002. The library is divided into the following sublibraries; incident neutron data (general purpose library), radioactive decay data, fission yields data, thermal scattering law data, photo-atomic interaction data, incident charged-particle data, activation data, and dosimetry data. Two high-energy data libraries also exist, containing neutron and proton reaction data up to 1 GeV incident energy.
The general purpose library is in
ENDF-6 format and contains data for 440 materials from 1-H-1 to 99-Es-253, with approximately
30 materials having evaluations upto 150 MeV. The proton sub-library has
been significantly increased and now contains 34 evaluations.
More information
The 1978 version of the Evaluated Neutron Data Library of the Lawrence Livermore National Laboratory (LLNL) contains evaluated neutron cross sections and differential data and neutron induced photon production data for 85 materials for incident energies from 10-4 eV to 20 MeV. The library is in ENDF-5 format.
The 1986 version of the Evaluated Neutron Data Library
of the Lawrence Livermore National Laboratory in
ENDL Transmittal Format.
Evaluated nuclear data library for calculations in fusion
(and other) applications, produced by the IAEA Nuclear Data Section, in
collaboration with several national nuclear data centres and research
groups. Sub-libraries exist for activation (FENDL/PA), decay (FENDL/D),
dosimetry (IRDF-90v2), fusion (FENDL/C) and transport applications (FENDL/E).
FENDL-2.0 is a comprehensive nuclear data library for
fusion applications, developed in the frame of the international effort
coordinated by the
IAEA Nuclear Data Section and released in December 1998. Sub-libraries
exist for activation (FENDL/A), decay (FENDL/D), dosimetry (FENDL/DS),
fusion (FENDL/C), transport applications (FENDL/E) and validation (VALIDATION)
containing a collection of benchmarks.
More information
This library is the IAEA Nuclear Data Library for Various
neutron data evaluations in ENDF-5 format.
It is not a comprehensive file of recommended and consistent evaluations, but rather a collection of
available evaluations which are "complete" in the sense that they are
suitable for neutron transport calculations. The file contains evaluations
for 196 materials.
This is a supplement to the INDL/A library (IAEA Nuclear
Data Library for evaluated neutron reaction data of Actinides). It contains
five evaluations by V.A. Konshin for U-235, Pu-239,240,241,242 . The data
are in ENDF-5 format.
The 1985 version of the International Reactor Dosimetry
File (IRDF). The data are in a a 640 group-structure (SAND-II extended
to 20 MeV) in ENDF-5 format.
The International Reactor Dosimetry File (IRDF-90) version
2, was released in 1993. The library contains neutron cross section data
for 58 reactions used for reactor dosimetry by foil activation. The data
is in ENDF-6 format, processed into 640 group structure. It also contains
radiation damage cross-sections for 4 materials in ENDF-V format, and
spectra daa files in ENDF-5 format
for 10 benchmark neutron fields.
The previous version of the Joint Evaluated Fission and Fusion File (JEFF-3.0)
included a general purpose library released in April 2002. It is in
ENDF-6 format and contains data for 340 materials from 1-H-1 to 99-Es-255 as well as thermal scattering law data for 5 materials.
More information
The Joint Evaluated File (JEF-2.2) is an evaluated library produced via an international collaboration of Data Bank member countires co-ordinated under the auspices of the NEA Data Bank. The JEF-2.2 library comprises several sublibraries; incident neutron data (general purpose library), radioactive decay data, fission yields data, thermal scattering law data and photo-atomic interaction data.
The general purpose library was released in 1992. It
is in ENDF-6 format and
contains data for 313 materials from 1-H-1 to 99-Es-253.
More information
Japanese Evaluated Neutron Data Library, released in 1989 and modified in 1990 and 1994. The library is in ENDF-6 format and contains data for 340 materials from 1-H-1 to 100-Fm-255.
The data library, which constitutes part A of the Reference
Nuclear Parameter Library (RNPL), consists of calculated, and in most
cases also measured, ground-state masses of 4685 nuclei ranging from 16
O to 318122 .
UK fission product decay data file by Crouch, version
3 - 1979
UK fission product yield file, version 1 (adjusted)
- 1986
UK fission product yield file, version 1 (unadjusted)
- 1986
Version 2 of the UK fission product yield file (1993).
Fission product yeilds data for 21 fissile nuclides giving 39 sets of
evaluated independent and cumulative yields for a total of 672 fission
product nuclei. The library is in ENDF-6 format,
and was adopted as the JEF-2.2 fission product yields sub-library.
The UKFY-3.-0 library was produced as part of the UK
fission product yield evaluation programme. It contains independent and
cumulative yields sets for 39 fissioning systems. A second file containing
chain yields is also available. The library is in ENDF-6 format.
The UKFY4.0 library includes energy dependent fission product yield data resulting from fission induced by neutron, proton, deuteron and alpha particle induced yields for 21 fissioning systems (232Th, 233U, 234U, 235U, 236U, 238U, 237Np, 238Np, 238Pu, 239Pu, 240Pu, 241Pu, 242Pu, 241Am, 242mAm, 243Am, 242Cm,243Cm, 244Cm, 245Cm and 252Cf). The range of particle energies considered is from 10-5 eV to 150 MeV. The required data were produced using the CYFP code from the Los Alamos National Laboratory in the U.S.A.
UK fission product decay data file, version 2 (1980),
in ENDF-5 format.
UK Heavy Element Decay Data file, version1 (1982). Contains
evaluations for 125 heavy element nuclide of interest in nuclear fuel
cycle calculations. The library is in ENDF-5 format.
This is a re-issue of the decay data in UKHEDD-1, following
re-evaluation of the major decay parameters within the file. The library
is in ENDF-6 format.
UK Heavy Element Decay Data file, version 2.1 (1995).
Contains evaluations for 125 heavy element nuclide of interest in nuclear
fuel cycle calculations. This is a re-issue of the decay data in UKHEDD-2,
following minor corrections to some of the spontaneous fission data and
includes newly recommended data for Pa-234g and Pa-234m. The library is
in ENDF-6 format.
UK activation product decay data library (UKPADD) version
1 (1977), in ENDF-5 format.
The UK activation product decay data library (UKPADD)
version 2 (1992) contains evaluations for 236 nuclides in ENDF-6 format.
The UK activation product decay data library (UKPADD)
contains radioactive decay data for 328 activation products (including
some fission products). The library is in
ENDF-6 format.
The 1981 edition of the UK Nuclear Data Library, contains neutron cross section data for 82 reactor materials, as well as capture, elastic, inelastic and transport cross sections in the energy range 1.0263 meV to 15 MeV for 192 fission products, and 63 files of neutron cross section data, mainly for activation detectors. The library is in UKNDL format.
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