# | Library | Year | Format | Hide Title/Expansion |
1 |
ACTIV87
| 1987 |
ENDF-5
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Fast Neutron Activation Cross section File
This compilation of fast neutron induced activation reaction cross-sections, covering energies from threshold to 20 KeV, is based on evaluated data taken from different evaluated data libraries and individual evaluations. By V.N. Manokhin. A.B. Pashchenko. V.I. Plyaskin V.K. Bychkov. V.G. Pronyaev
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2 |
ADL-3
| 1993 |
ENDF-6
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Hide
Russian Activation Data Library (1993)
Evaluated neutron activation cross-sections of 20049 excitation functions, by O.T. Grudzevich, A.V. Zeleneckij, A.V. Ignatyuk, A.B. Pashchenko, see Yadernye Konstanty, issue 1993 (3-4).
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3 |
ASIYAD
| 1988 |
ENDF-6
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Hide
Fission-product yield library by A.F. Grashin (1988).
Data for thermal and/or fast neutron-induced fission for 22 fissioning nuclides between U-232 and Cm-245.
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4 |
BISERM-2
| 1997 |
ENDF-6
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Hide
Nuclear data library for evaluation of radiation effects in materials.
Nuclear Data Library for Evaluation of Radiation Effects in Materials Induced by Neutrons of Intermediate Energies (1997). Neutron displacement cross sections and hydrogen and helium production cross sections for 259 stable nuclei from Al-27 to Bi-209 at neutron energies up to 1 GeV. By Yu.A. Korovin et al., Obninsk, Russia.
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5 |
BROND-2.2
| 1992 |
ENDF-6
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Hide
USSR evaluated neutron data library, issued in 1992
Russian neutron evaluated data files ver.2 IPPE, Obninks, Russia.
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6 |
BROND-3.1
| 2016 |
ENDF-6
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Hide
Russian evaluated neutron data library, issued in 2016
Russian neutron evaluated data files ver-3.1 IPPE, Obninks, Russia.
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7 |
CENDL-2
| 1991 |
ENDF-6
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Hide
Chinese evaluated neutron data library, issued in 1991
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8 |
CENDL-3.1
| 2009 |
ENDF-6
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Hide
Chinese evaluated neutron data library, issued in 2009
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9 |
DXS
| 2011 |
ENDF-6
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Hide
Damage and gas-production cross section database, 2011-2015
Neutron and protons induced NRT- and arc-displacement and gas production cross-sections up to 3 GeV. 2015 extension: alloys SS-316 and Eurofer data in ENDF6 and ACE formats, by A.Yu.Konobeyev and U.Fischer, Karlsruhe Institute of Technology (KIT), Germany
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10 |
ENDF/B-IV
| 1974 |
ENDF-4
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Hide
U.S. Evaluated Nuclear Data Library, issued in 1974
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11 |
ENDF/B-V
| 1994 |
ENDF-5
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Hide
U.S. Evaluated Nuclear Data Library, issued in 1994
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12 |
ENDF/B-VI.8
| 2001 |
ENDF-6
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Hide
U.S. Evaluated Nuclear Data Library, issued in 1990 (Release 8, Sept.2001)
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13 |
ENDF/B-VII.0
| 2006 |
ENDF-6
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Hide
U.S. Evaluated Nuclear Data Library, issued in 2006
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14 |
ENDF/HE-VI
| 1998 |
ENDF-6
|
Hide
ENDF/B High Energy Library
Special library consiting two files: - neutron reaction data up to 1 GeV incident energy - proton reaction data up to 1 GeV incident energy
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15 |
ENDL-84
| 1984 |
ENDF-5
|
Hide
The Evaluated Nuclear Data Library of the Lawrence Livermore National Laboratory
The library contains evaluated data for all significant neutron reactions in the energy range from 10-4 eV to 20 KeV for 94 elements or isotopes.
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16 |
FOND-2.2
| 1999 |
ENDF-6
|
Hide
Evaluated data library for generating sets of constants in the ABBN constants system
Evaluated Neutron Data Library for generating sets of constants in the ABBN constants system, by V.N. Koscheev, M.N. Nikolaev, A.M. Tsiboulia, G.V. Savoskina. 679 materials.
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17 |
IRDF-90
| 2002 |
ENDF-6
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Hide
IRDF-90 version-2, International Reactor Dosimetry File
contains 58 cross-sections of dosimetry reactions, all with complete covarianceinformation.
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18 |
IRDF-2002
| 2002 |
ENDF-6
|
Hide
IRDF-2002 Decay data + Dosimetry cross sections in pointwise ENDF-6 format
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
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19 |
IRDFF v-1.03
| 2014 |
ENDF-6
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Hide
International Reactor Dosimetry and Fusion File, IAEA, 2014
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20 |
IRDFF v-1.05
| 2014 |
ENDF-6
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Hide
International Reactor Dosimetry and Fusion File, ver-1.05, IAEA, 2014
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21 |
INDL/TSL
| 2006 |
ENDF-6
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Hide
IAEA Nuclear Data Library / Thermal Scattering Law, 2006
An improved set of thermal scattering law data has been prepared for various elements and compounds. These files were prepared in 2004-06 through an IAEA Contractual Service Agreement with Drs. M. Mattes and J. Keinert, Institut fuer Kernenergetik, Universitaet Stuttgart, GERMANY
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22 |
JEFF-3.1
| 2005 |
ENDF-6
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Hide
Evaluated nuclear data library of the OECD Nuclear Energy Agency, Europe, 2005
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23 |
JEFF-3.1.1
| 2009 |
ENDF-6
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Hide
Nuetron data sub-library, OECD Nuclear Energy Agency, Europe, 2009
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24 |
JEFF-3.1.2
| 2012 |
ENDF-6
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Hide
Joint Evaluated Fission and Fusion File, coord. by NEA Data Bank, 2012
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25 |
JEFF-3.2
| 2014 |
ENDF-6
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Hide
Evaluated nuclear data library of the OECD Nuclear Energy Agency, Europe, 2005
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26 |
JENDL-3.2
| 1994 |
ENDF-6
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Hide
Japanese evaluated nuclear data library, Japan, 1994
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27 |
JENDL-3.3
| 2002 |
ENDF-6
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Hide
Japanese evaluated nuclear data library, Japan, 2002
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28 |
JENDL-4.0
| 2010 |
ENDF-6
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Hide
Japanese evaluated nuclear data library, Japan, 2010
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29 |
JENDL-4.0u2
| 2016 |
ENDF-6
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Hide
Update /20160106/ of Japanese evaluated nuclear data library, Japan, 2016
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30 |
LLCRP
| 1997 |
ENDF-5
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Hide
Excitation functions of 16 long-lived activation reactions of importance in fusion reactor technology, 1997
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31 |
MENDL-2
| 1995 |
ENDF-6
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Hide
Russian transmutation and activation data library (1995)
Russian cross-section data library for transmutation and activation of materials irradiated by neutrons with energies up to 100 MeV. Yu.N. Shubin et al.
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32 |
MENDL-2P
| 1995 |
ENDF-6
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Hide
Proton reaction data library for nuclear activation
Proton reaction data library for nuclear activation by Yu.N. Shubin et al., Obninsk, Russia. Calculated proton cross-sections in ENDF-6 format for 505 nuclei (Z=13-84) for energies up to 200 MeV. The total number of reactions is 87196.
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33 |
PADF-2007
| 2007 |
ENDF-6
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Hide
Proton Activation Data File, 2007
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. A.Yu. Konobeyev, C.H.M. Broeders, U. Fischer, L. Mercatali, I. Schmuck and S.P. Simakov
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34 |
PRONDOS
| 1989 |
ENDF-5
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Hide
Evaluations of selected neutron activation reactions for dosimetry
By V.G. Pronjaev et al., 1988/1989
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35 |
ROSFOND
| 2008 |
ENDF-6
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Hide
Russian library of evaluated neutron data files, issued in 2008
Russian evaluated neutron data library, 683 materials IPPE, Obninks, Russia.
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36 |
ROSFOND-2010
| 2010 |
ENDF-6
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Hide
Russian library of evaluated neutron data files, updated in 2010
Russian evaluated neutron data library, 686 materials IPPE, Obninks, Russia.
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37 |
RRDF-98
| 1998 |
ENDF-6
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Hide
Russian Reactor Dosimetry File.
Cross sections and uncertainties for 22 reactions used for neutron flux dosimetry by foil activation. By K.I. Zolotarev, A.V.Ignatyuk, V.N. Manokhin, and A.B. Pashchenko.
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38 |
RNAL
| 2000 |
ENDF-6
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Hide
Reference Neutron Activation Library.
Contains cross sections for the 255 neutron induced reactions relevant to a wide range of applications. IAEA-CRP (co-ordinated research project).
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39 |
TENDL-2008
| 2008 |
ENDF-6
|
Hide
TALYS-based Evaluated Nuclear Data Library
Complete nuclear data libraries for about 350 nuclides between 19F and 209Po for incident neutrons, protons, deuterons, tritons, helium-3, alpha particles and photons up to 200 MeV (neutrons up to 20 MeV).
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40 |
TENDL-2009
| 2009 |
ENDF-6
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Hide
TALYS-based Evaluated Nuclear Data Library
Complete nuclear data libraries for about 2400 nuclides between 6Li and 281Ds for incident neutrons, protons, deuterons, tritons, helium-3, alpha particles and photons up to 200 MeV.
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41 |
TENDL-2010
| 2010 |
ENDF-6
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Hide
TALYS-based Evaluated Nuclear Data Library
Complete nuclear data libraries
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42 |
TENDL-2012
| 2012 |
ENDF-6
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Hide
TALYS-based Evaluated Nuclear Data Library
Complete nuclear data libraries
|
43 |
TENDL-2014
| 2014 |
ENDF-6
|
Hide
TALYS-based Evaluated Nuclear Data Library
Complete nuclear data libraries
|
44 |
UKPADD-2
| 1993 |
ENDF-6
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Hide
Activation Product Decay Data.
Recommended data include half-life, branching fractions, alpha, beta and gamma-ray energies and emission probabilities, total decay energy, mean alpha, beta and gamma energies, internal conversion coefficients, and all associated uncertainties. By A.L.Nichols
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45 |
WIND-1
| 1998 |
ENDF-6
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Hide
Nuclear data library for isotopes of U, Np, Pu and U-238.
The WIND nuclear data library (Waste Incineration Nuclear Data) contains evaluated data of neutron induced fission and threshold reactions for isotopes of U, Np, and Pu, and one file of proton induced reactions for U-238, in the energy range up to 100 MeV, primarily designed for the study of incineration of longlived radioactive materials. By A.Yu. Konobeyev et al., Obninsk, Russia
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46 |
WIND-2
| 1998 |
ENDF-6
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Hide
Neutron activation data for Pu-239 at energies up to 2 GeV.
The WIND nuclear data library (Waste Incineration Nuclear Data) WIND-2 contains neutron activation data for Pu-239 at energies up to 2 GeV By A.Yu. Konobeyev et al., Obninsk, Russia
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47 |
Yavshits
| 2002 |
ENDF-6
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Hide
Theoretical Evaluation of Neutron and Proton Induced Fission Cross Sections for Pb - Pu Targets
Theoretical Evaluation of Neutron and Proton Induced Fission Cross Sections for Pb - Pu Targets in Energy Range 20 - 200 MeV, by S. Yavshits, V.G. Khlopin Radium Institute, St. Petersburg, Russia
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