Abstract
The average cross-sections in a fission-type reactor neutron spectrum are determined experimentally for the reactions: (92)Mo (n, a) (89)Zr, (90)Zr (n, 2n) (89)Zr and (60)Ni (n, p) (60)Co. The determined cross sections are in the ranges of the reported values in literature. A method for determining the cross sections in relative way is introduced. It replaces the cross sections and the nuclear data by a composite nuclear data constant which can be calculated and determined experimentally. It is shown that the uncertainties of determining these constants experimentally are mainly lower than the calculated ones. The consequences of using this constant in neutron activation analysis are briefly discussed.
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