论文部分内容阅读
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 MCNP5 program was used to simulate the transport of fast neutron energies of 14.88 MeV in (W + B_4C) / Al and W / Al composites and compared with lead-boron polyethylene, polyethylene and tungsten. The neutron attenuation properties, the neutron transmission spectra and the emission spectra of the γ-rays released during the neutron capture are calculated, which provide a theoretical basis for the selection of neutron shielding materials. The simulation results are in good agreement with the actual results, confirming the reliability of the Monte Carlo method. The simulation results also show that, for fast neutron, the shielding effect of high atomic number material is better than that of low atomic number material. The shielding performance of 45% tungsten-containing composite is similar to that of commercial lead-boron polyethylene, but the excitation γ Ray energy is lower than that of lead-boron-polyethylene. Considering the compositional controllability, service temperature and mechanical properties, the (W + B_4C) / Al composite is a promising neutron shielding material.