[en] A new cross section library, the ''International Reactor Dosimetry and Fusion File release1.0 (IRDFF 1.0)'' has been developed for reactor dosimetry and fusion applications. It contains cross sections with uncertainties (covariance matrices) for 74 dosimetry reactions and for B, Cd and Gd cover materials in the form of point-wise linearly interpolable data from 10^-11 MeV up to at least 60 MeV, in ENDF-6 format. For reactor dosimetry applications these pointwise data were processed and made available in the SAND II type 640 group format (10^-10 MeV to 20 MeV). 33 cross section datasets have been adopted with minor modifications from the file IRDF-2002; the others are new evaluations. This report summarizes the characterization of the new cross section evaluations in Maxwellian thermal (300K), 1/E and ²⁵²Cf(sf) neutron fields, and presents the most important features and data of the resulted version of the new international reactor and fusion dosimetry cross section file. (author)