Measurement of neutron activation cross section data for materials relevant to reactor technology using neutron generator facility

Abstract

Cross sections of seven (n,2n), (n,p) and (n,a) reactions in the neutron energy range 13.90 - 14.71 MeV were measured by the activation technique for the isotopes of scandium, nickel, copper and zirconium all of which are the probable structural materials of fusion reactors. In every case samples of natural abundance was used. Neutrons were produced via 3H(d,n)4He reaction using solid tritium target at J-25 neutron generator at the Institute of Nuclear Science and Technology (INST), Savar, with a deuteron energy of 110 keV and steady beam current of 100 - 120 I-tA Neutrons of different energies were obtained at the different angular positions with respect to the direction of incoming deuteron beam. Activities of the reaction products were determined by measuring the gamma-ray counts of the product nuclei using high resolution HPGe detector gamma-ray spectrometry system. Neutron flux at each sample position was determined by using 27Al(n,a)24Na monitor reaction with known cross section of the monitor reaction taken from the works ofR. Vonach. The experimental values of the cross sections were determined using activation equation. Uncertainties in the measured cross section values include statistical and systematic errors. In the present experiment cross sections of 45Sc(n,2nt4gsc, 45Sc(n,a)42K, 58Ni(n,2n)57Ni, 58Ni(n,p)58m+gCo,61Ni(n,p)61Co, 65Cu(n,2n)64Cu and 90Zr(n,p?Omy reactions were measured in the same experimental configuration. Nuclear Cross Section Calculation System with Simplified Input Format, Version-II (SINCROS-II) was used to calculate theoretical reaction cross sections. Measured cross sections were compared with the literature data and were found in fairly good agreement with the values quoted. Measured data were also compared with the calculated cross sections to justifY the validity of model calculation. Measured data will help to remove existing discrepancies in the cross section values and will contribute to the further evaluations of cross sections of these reactions