Seven shape memory alloys, together with AISI 321 stainless steel and polyethylene, were investigated as moderators for a241Am–Be neutron source. Monte Carlo simulations were performed to estimate the neutron spectra at 100 cm from the source, with the aim of producing realistic neutron radiation fields comprising thermal, epithermal, and fast neutrons suitable for calibration of neutron radiation protection instruments. In addition, γ-ray spectra induced by neutron interactions with, the source, alloy, steel, and polyethylene nuclei were evaluated. Using the calculated neutron spectra, the ambient dose equivalent, isotropic effective dose, and ambient dose were determined, while the ambient dose equivalent and ambient dose were also calculated for the γ-ray spectra. The neutron spectra of alloy-moderated 241Am–Be sources, including configurations with thin and thick polyethylene shells, exhibited neutron absorption features associated with 55Mn present in all alloys. Neutron spectra produced by thin and thick alloy shell–polyethylene moderated 241Am–Be sources showed well-defined thermal, epithermal, and fast neutron components, with mean neutron energies ranging from 1.53 to 2.48 MeV. Among the investigated configurations, the thick ASH4P/241Am–Be source produced the highest neutron fluence, with a mean energy of approximately 2.16 MeV and a balanced contribution of thermal, epithermal, and fast neutrons. These results demonstrate that shape memory alloys, in combination with polyethylene, can be effectively used to tailor 241Am–Be neutron fields, enabling the generation of realistic spectral and dosimetric characteristics suitable for extending the calibration capabilities of neutron calibration facilities.
扫码关注我们
求助内容:
应助结果提醒方式:
