Index of /databases/IRDF-2002

There is a part of the International Reactor Dosimetry File (IRDF-2002) - Dosimetry cross sections in groupwise ENDF-6 format for sub-library 10 (incident neutron). Cross sections and covariances are available for 50 nuclides, 64 reactions. The data are compiled by averaging cross sections in the SAND-II type energy intervals without any energy-dependent weighting function.
Complete information on the IRDF-2002 library is available in NDS IAEA. Details were published in IAEA TECHNICAL REPORTS SERIES No. 452