Monte Carlo simulations (MCNP-X) were performed to measure the thermal, epithermal and fast neutron fluxes and the thermal-to-epithermal flux ratio and thermal-to-fast flux ratio in the irradiation channels of a neutron activation facility with 4.3 Ci ²⁴¹Am–Be source, and the neutron source and irradiation channels are housed in a cylindrical barrel filled with a water moderator with a radius determined according to radial neutron flux measurements. The best position for the thermal and fast neutron irradiation channels was determined by investigating the variation trend of the above-mentioned parameters in radial and axial directions in this facility. It was observed that the axial distribution of the neutron flux in the irradiation channel is symmetric with a significant peak at the height in front of the source position, which is consistent with the results obtained in the previous research.

^{进行蒙特卡罗模拟 (MCNP-X) 以测量具有 4.3 Ci 241}的中子活化设施的辐照通道中的热、超热和快中子通量以及热-超热通量比和热-快通量比Am-Be 源，中子源和辐照通道装在一个圆柱形桶中，桶内装有水慢化剂，其半径根据径向中子通量测量值确定。通过考察该设施内上述参数在径向和轴向上的变化趋势，确定了热和快中子辐照通道的最佳位置。观察到辐照通道中中子通量的轴向分布是对称的，在源位置前方的高度处有一个显着的峰值，这与前人研究得到的结果一致。