Absolute measurements of activation cross sections of 27Al(n,p)27Mg, 27Al(n,α)24Na, 56Fe(n,p)56Mn, 90Zr(n,2n)89m+gZr and 93Nb(n,2n)92mNb at energy range of 13.3-14.9 MeV

The reaction cross sections of 27Al(n,p)27Mg, 27Al(n,α)24Na, 56Fe(n,p)56Mn, 90Zr(n,2n)89m+gZr and 93Nb(n,2n)92mNb have been measured by the activation method in an energy range of 13.3-14.9 MeV using the intense D-T neutron source, FNS. Absolute flux was determined by the associated α-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 27Al(n,α)24Na, 56Fe(n,p)56Mn and 90Zr(n,2n)89m+gZr 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 93Nb(n,2n)92mNb in the JENDL Dosimetry File, and the overestimation and underestimation of the cross section for 27Al(n,p)27Mg in the JENDL Dosimetry File and IRDF-90, respectively. (author)