A method of measuring the neutron energy spectrum by activation detectors

This work analyzes a general direct method of calculating a neutron energy spectrum using efficiency of reactions of activation detectors. Our interest was focused on the study of the influence of input experimental errors and uncertainty of cross sections on output errors. The experimental data are taken from the KWINTA experiment in JINR, Dubna. The obtained results of the neutron flux spectrum in range 0.7-200 MeV are compared with calculation results from the MCNPX code.