(W+B_4C)/Al复合材料中子屏蔽性能的蒙特卡罗模拟  

Study on(W + B_4C)/Al composites of neutron shielding properties based on monte carlo simulation

作　　者：王健[1] 马书旺[1] 杨剑[1] 梁秋实[1] 刘坤[1] 杨志民[1] 毛昌辉[1] 

机构地区：[1]北京有色金属研究总院先进电子材料研究所,北京100088

出　　处：《分析试验室》2016年第10期1190-1194,共5页Chinese Journal of Analysis Laboratory

摘　　要：使用MCNP5程序模拟了能量为14.88 Me V的快中子在(W+B_4C)/Al和W/Al复合材料中的输运过程,并与铅硼聚乙烯、聚乙烯以及钨进行对比。计算了各屏蔽材料的中子衰减性能、中子透射能谱以及中子俘获过程中释放γ射线的透射能谱,为中子屏蔽材料的选择提供了理论依据。模拟结果和实际结果吻合,证实了蒙特卡罗方法的可靠性。模拟结果也可以得出,对于快中子,高原子序数材料的屏蔽效果要好于低原子序数材料,含钨45%的复合材料的屏蔽性能与商用铅硼聚乙烯的屏蔽效能相近,但是激发γ射线能量低于铅硼聚乙烯,考虑到成分可调控性、使用温度以及力学性能等因素,(W+B_4C)/Al复合材料是一种极具应用潜力的新型中子屏蔽材料。The transmission process of（ W ＋ B_4C）/Al and W/Al composites with 14. 88 Me V neutron energy was simulated by MCNP5 program and compared with those of lead-born carbide-polyethylene,polyethylene and tungsten. The estimations of neutron attenuation,neutron transmission spectrum and γ transmission spectra induced by neutron capture process provided the theoretical basis of selecting neutron shielding materials. The simulative results were basically consistent with those observed in practice,confirming the reliability of Monte Carlo methods. The results showed that high atomic number materials had a better performance in fast neutron shielding than that of low atomic number materials. The shielding properties of composites with 45% W content were closed to that of commercial lead-born carbide-polyethylene with lower γ energy induced by neutron capturing. With the properties of component adjustment,using temperatures and mechanical behavior,（ W ＋B_4C）/Al composite is a new type of neutron shielding material with great potential application.

关 键 词：蒙特卡罗法 MCNP 中子屏蔽 (W+B4C)/Al复合材料 

分 类 号：TG115[金属学及工艺—物理冶金]