基于蒙特卡罗方法的中子屏蔽材料设计

摘要

基于蒙特卡罗粒子输运程序MCNP,设计了一种强度高、密度低、具有优异中子屏蔽性能的新型玻璃纤维/B4C/环氧树脂复合材料,模拟计算了镅-铍(Am-Be)中子源产生中子对该材料的透射率；研究了该材料的中子屏蔽性能与传统屏蔽材料的差异以及不同B4C质量分数对该材料的屏蔽性能影响；根据模拟结果分析了该材料对不同能区中子(慢中子、中能中子、快中子)具有的不同屏蔽性能.研究发现:B4C质量分数为10％的该种新型玻璃纤维/B4C/环氧树脂复合材料的中子屏蔽性能,尤其是慢中子屏蔽性能较传统的含硼聚乙烯和Al-B4C合金材料更为优异；但随着B4C质量分数的增大,屏蔽性能提升不明显.结果验证了蒙特卡罗方法用于中子屏蔽材料优化设计的可行性.%Based on the Monte Carlo particle transport program MCNP, a noveL glass fiber/B4 C/epoxy resin composite for neutron shielding with high strength and low density was developed. Its neutron transmissivity was calculated under the Am-Be neutron source condition to study the difference of neutron shielding performance between the glass fiber/B4 C/epoxy resin composite and traditional shielding materials. Furthermore, effects of B4 C mass fraction of the composite on the shielding performance for neutrons with different energy(slow neutron, intermediate neutron, fast neutron) were analyzed. The results show the composites with 10% B4C mass contents have more advantages on the neutron shielding performance , especially the slow neutron shielding performance in comparison with polyethylene/boron containing composites and Al-B4 C alloy. With the further increasing of the B4C contents, no remarkable increase is observed. Monte Carlo method is demonstrated feasible in optimization design of neutron shielding materials and the results provide a theoretical basis for design and preparation of a new neutron shielding composite.