الفهرس 
Fast neutron source
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Abstract
Measurement of reaction cross sections is one of the main aims of many experimentalists because of the lake of proven cross section data for many neutron-induced reactions specially in the energy range between 13-15 MeV. Moreover, discrepancies among the available data are still exists. Since these data are essential for the microscopic nuclear data, and standard reference data, measurements of fast neutron reactions with some medium mass elements are of increasing importance in assigning low activation materials related to the fusion reactor technology (FRT), fast neutron breeder reactor (FNBR), and accelerator driven systems (ADS). In calculating the nuclear heating, neutron shielding analysis, activation of reactor components, radiation damage effects and formation of hydrogen, and helium gases in structural materials etc.. So in this work the following reactions were considered; 90Zr(n,a)87Sr,90Zr(n,p)90mY, 91Zn(n,p)91mY,and 93Nb(n,a)90mY. These channels can produce gases (in particular helium and hydrogen) in fusion reactor materials. Gases released in structural materials, due to neutron irradiation, affects the physical and mechanical properties of the materials in terms of Helium or Hydrogen embrittlement, void swelling and weldment ability of the irradiated alloys. Therefore, gas production rate should be evaluated to predict lifetime of the components and weldment ability of the irradiated components. We aimed to have clear and concise data of neutron cross sections for such reactions.