Miscellaneous Specialized Neutron Data Libraries

INGDB-90

The international neutron nuclear database for geophysics applications. It contains selected neutron cross-section data, spectrum data of selected neutron sources, and the cross-section data processing codes LINEAR and GROUPIE.
Assembled by N.P. Kocherov and P.K. McLaughlin.
Summary see document IAEA-NDS-127.
The full information see N.P. Kocherov, IAEA Technical Report 357: Handbook on Nuclear Data for Borehole Logging and Mineral Analysis (1993).

SGNucDat, Version 2

Safeguards Nuclear Data for Windows. Contains the data of report INDC(NDS)-376 (1997). A: Actinide nuclear data (decay data, selected neutron cross section data, fission-neutron data); B: fission-product nuclear data (decay data and selected neutron cross section data); C: fission-product yield data. PC code by G.Pospischil. Data compiled by M. Lammer, O. Schwerer and N.P.Kocherov, documented in report IAEA-NDS-248 Rev.97/12 (1997). Also available online.

Atlas of Neutron Capture Cross Sections

J. Kopecky et al. Report INDC(NDS)-362, 370 pages. Plots of neutron capture cross sections in the energy range 10-5 eV - 20 MeV as evaluated and compiled in recent activation libraries, compared with available experimental values at thermal energy, 30 keV and 14.5 MeV, for 739 targets from H to Cm. Report available cost-free. The evaluated cross section data are available in pointwise ENDF-5 format and can be downloaded from the NGATLAS page.

JENDL-3 Sublibrary for Gas Production

by T. Nakagawa and T. Narita. Contains neutron-induced hydrogen and helium production cross-sections for elements from 3-Li to 41-Nb.
Summary documentation: IAEA-NDS-139

ENDF/B-5 Gas Production File (Rev. 2)

Neutron cross-sections for gas production for 18 elements or isotopes from 5-B-11 to 29-Cu. Summary documentation: IAEA-NDS-42, Rev. 1.
Data available on magnetic tape.

DAMSIG84

Radiation damage cross sections by ECN Netherlands in 640 group structure.
Documentation by W.L. Zijp et al. in ECN-159

Californium-252 spectrum averaged neutron cross-sections

W. Mannhart - See Handbook on Nuclear Activation Data, IAEA Technical Report Series No. 273, Vienna 1987, p. 413-440.

Reaction cross-sections

induced by 14.5 MeV neutrons and by Cf-252 and U-235 fission spectrum neutrons. Data tables by A.B. Pashchenko. Data considered up to the end of 1989. Report INDC(CCP)-323, English translation of the Russian report FEI-236. Compared to the Russian original, in the English translation a few numbers were updated by the author.
Note a misprint: In the data tables, the column heading "14 MeV" should read "14.5 MeV".

Brenner/Prael

Nonelastic interactions of neutrons between 15 and 60 MeV with carbon and oxygen, calculated differential secondary- particle production cross-sections, by D.J. Brenner and R.E. Prael. - Not available on tape. See Atomic Data and Nuclear Data Tables, vol. 41 nr.1 p.71-130 (Jan. 1989).

Neutron capture reaction rates at 30 keV

Tabulation of calculated values for about 4000 nuclides. See the journal Physics Reports vol. 208 (1991) p. 267-394, J.J. Cowan et al., the r-process and nucleochronology. Data tabulation on tape available from authors, but not available from IAEA-NDS. - Note that the data were derived from theory and that they were not computed from available nuclear data libraries.

Neutron scattering lengths

see experimental neutron data.