The new version of the International Reactor Dosimetry File IRDF-90 (called “Version April 1993”) has been tested by calculatio of average cross-sections and their uncertainties in a coarse three energy group structure and by neutron spectrum adjustments in reference neutron spectra. This paper presents the results and compares them with the corresponding ones of the old Reactor Dosimetry File IRDF-85 and with the data of the Nuclear Data Guide for Reactor Neutron Metrology. Finally, the applicability of the new library in the field of neutron metrology is discussed.
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