The reaction cross sections of Al-27(n, p)Mg-27, Al-27(n, alpha)Na-24, Fe-56(n, P)Mn-56, Zr-90(n, 2n)Z5-89m+g and Nb-93(n, 2n)Nb-92m have been measured by the activation method in an energy range of 13.3 approximately 14.9 MeV using the intense D-T neutron source, FNS. Absolute flux was determined by the associated a-particle counting method incorporated with neutron spectra obtained from both a Monte Carlo calculation and a time-of -flight measurement. Corrections were extensively performed not only for the neutron flux determination, but also for the low energy neutron contribution to the reaction rates. The present data were compared with comprehensive evaluations as well as recent experimental data. The measured cross sections of Al-27(n, alpha)Na-24, Fe-56(n, p)Mn-56 and Zr-90(n, 2n)Zr-89m+g are generally in good agreement within experimental errors with the values in both the JENDL Dosimetry File and IRDF-90. It is also shown that there are the overestimation of the cross sections for Nb-93(n, 2n)Nb-92m in the JENDL Dosimetry File, and the overestimation and underestimation of the cross section for Al-27(n, p)Mg-27 in the JENDL Dosimetry File and IRDF-90, respectively.
