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The neutron radiative capture and neutron fission cross-sections were measured over the neutron emission spectrum of an 241Am-Be source with an effective energy range between 1 MeV and 11 MeV using the activation method. In foils were used as a neutron flux monitor based on 115In(n, n′)115mIn reaction. The sample was a Cd-covered natural UO2 pellet. Evaluations of the yield and reaction data in the energy range from 0.1 MeV to 11 MeV had been done to validate the integral experimental results. The neutron capture cross-section, using 239Np decay, was 32.9 ± 0.9stat. mb. The fission cross-section was probed using gamma lines from 143Ce, 133I, 105Ru, 134I, 91Sr, 135I, and 92Sr. The weighted average value of the fission cross-section was 570 ± 24 mb. 143Ce, 133I, 135I, and 92Sr had the highest merit among fission products for the validation, use upon application of long-lived Am-Be neutrons in quantification for nuclear safeguard and security applications.

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