[en] Foils of various fissile and nonfissile materials commonly used in neutron dosimetry have been irradiated in the CFRMF, Idaho and Big-10 Los Alamos. Following these irradiations quantitative γ-ray counting was undertaken by five separate groups at four laboratories. Each group used independently calibrated γ-ray detectors; either Ge(Li) or NaI(Tl). These measurements were made as a part of the Interlaboratory Reaction Rate (ILRR) program. Intercomparison of the reaction rate values obtained by each group show good consistency, with individual variations from the average reaction rates generally being less than +-2%. Based upon this consistency and the estimated uncertainties in the nuclear decay parameters the absolute accuracies of these reaction rates are estimated at +-2% (1 sigma). Integral cross section values have been deduced for these reactions in CFRMF and Big-10