Measurement of activation cross sections for quasi-monoenergetic neutron induced reactions of 89 Y

The neutron induced cross sections of the 89Y(n,2n)88Y, 89Y(n,3n)87Y and 89Y(n,4n)86Y reactions were measured in the neutron energy range of 15.2 to 37.2 MeV by using an activation and off-line \(\gamma\)-ray spectrometric technique. The quasi-monoenergetic neutrons used for the above reactions are based on a 9Be(p,n) reaction. Simulations of the neutron spectra from the Be target were done using the MCNPX 2.6.0 program. Theoretical calculations were performed for the 89Y(n,2n)88Y, 89Y(n,3n)87Y and 89Y(n,4n)86Y reaction cross sections using nuclear model code Talys 1.8. The measured and calculated cross sections were compared with the literature data given in EXFOR and the TENDL-2015 data libraries. The present data of the 89Y(n,xn) reaction were also compared with the similar data of the 89Y(\(\gamma\),xn) reaction to examine the effect of the entrance channel parameters as well as the role of projectiles and ejectiles.