FENDL/DS-2.0 DOSIMETRY SUBLIBRARY
(IRDF-90)
This directory contains the International Reactor Dosimetry File
( IAEA-NDS-141, Rev. 2, Oct. 1993) or in short IRDF-90 Version 2,
as assembled by N.P. Kocherov and P.K. McLaughlin, which has been
adopted for FENDL-2.0 as the dosimetry sublibrary FENDL/DS-2.0.
Files:
IRDF90V2_XSECT.DAT - recommended neutron cross-section data to be used
for reactor neutron dosimetry by foil activation.
IRDF90V2_DAMAGE.DAT - recommended values for radiation damage cross-sections.
IRDF90V2_SPECTRA.DAT - recommended values for benchmark neutron spectra.
IRDF90V2_WRITEUP.TXT - IRDF-90 Version 2 writeup
page modified: 13.3.1998