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 0.9^stat. 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.

使用活化方法，在有效能量范围为1 MeV至11 MeV的²⁴¹ Am-Be源的中子发射光谱上测量了中子辐射俘获和中子裂变截面。In箔用作基于¹¹⁵ In（n，n'）^115m In反应的中子通量监测仪。样品是Cd覆盖的天然UO ₂颗粒。对能量范围从0.1 MeV到11 MeV的收率和反应数据进行了评估，以验证整体实验结果。使用²³⁹ Np衰减的中子俘获截面为32.9 0.9 ^stat。mb。使用来自¹⁴³ Ce，^133的伽玛线探测裂变截面I，¹⁰⁵钌，¹³⁴ I，⁹¹的Sr，¹³⁵ I，和⁹²高级裂变截面的加权平均值为570 24 MB。¹⁴³ Ce，¹³³ I，¹³⁵ I和⁹² Sr在裂变产物中的验证，在应用长寿命Am-Be中子用于核安全和安保应用的定量分析时，具有最高的优点。