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