Various Specialized Evaluated Data Libraries
in ENDF and other formats available from the IAEA Nuclear Data Section

ADL-3

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). ENDF-6 format.

Documentation: IAEA-NDS-137

Download full library (33 MB).

MENDL-2

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., report INDC(CCP)-385. ENDF-6 format.

Summary documentation: IAEA-NDS-136 (1995). Download individual materials or whole library (76 MB).

ASIYAD

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. ENDF-6 format.

Documentation: IAEA-NDS-133

Download library (2 MB).

MENDL-2P

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.ENDF-6 format. Summary documentation: IAEA-NDS-204.

Download individual materials or whole library (133 MB).

BISERM-2

Nuclear Data Library for Evaluation of Radiation Effects in Materials Induced by Neutrons of Intermediate Energies (1997). By Yu.A. Korovin et al., Obninsk, Russia. 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. ENDF-6 format.

Documentation: IAEA‑NDS-203

Download library (3 MB).

RRDF-98

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. ENDF-6 format. Documentation and individual reactions available online from IAEA-NDS-193 (1999). Or download whole library.

Cf-252 neutron spectrum

Evaluation of the californium‑252 spontaneous fission neutron spectrum, by W. Mannhart, PTB Braunschweig, FRG, 1986/87. Summary documentation: IAEA‑NDS‑98.

Available for download in free format or from ENDF/B-VII decay data library.

TLAPrfl

Package for Calculation of Depth Profile for Thin Layer Activation, by G. Wallace. The package is available online together with summary documentation IAEA-NDS-192 (September 1999).

DROSG-2000

Package with programs and data for 59 neutron source reactions. Not in ENDF format.

See summary page.

WIND

Neutron nuclear data library for isotopes of U, Np, Pu up to 100 MeV, with one file of proton reaction data for U-238 (WIND-1) and a file for Pu-239 up to 2 GeV which includes also fission product yields (WIND-2). ENDF-6 format. By A.Ju. Konobejev et al., Obninsk, Russia.

Summary documentation: IAEA-NDS-143

Download WIND-1, WIND-2

FOND-2.2

Evaluated Neutron Data Library (1999), for generating sets of constants in the ABBN constants system, by V.N. Koscheev, M.N. Nikolaev, A.M. Tsiboulia, G.V. Savoskina.

Documentation with hyperlinks to data files for 679 materials in ENDF-6 format: IAEA-NDS-199

Yavshits

Theoretical Evaluation of Neutron and Proton Induced Fission Cross Sections for Pb - Pu Targets in Energy Range 20 - 200 MeV, by S. Yavshits. ENDF-6 format. Report and data available from IAEA-NDS-153 (February 2002)

LLCRP

Excitation functions of 16 long-lived activation reactions of importance in fusion reactor technology. ENDF-5 format. Documentation: INDC(NDS)-344 (1997).

Download library (1 MB).

DXS

Displacement Cross Section and Gas Production Files for Structural Materials Irradiated with Neutrons and Protons. Download Documentation and library (2011-2015).