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铝基碳化硼材料中子屏蔽性能的蒙特卡罗模拟
The Monte Carlo simulation of neutron shielding performance of boron carbide reinforced with aluminum composites
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摘要: 采用蒙特卡罗方法，运用 MCNP4C 程序研究了碳化硼含量20%-40%、中子能量200 eV-15 keV、材料厚度0.3-2 cm 对 B4C/Al 复合材料中子屏蔽性能的影响.结果表明：碳化硼含量与中子透射系数呈一次线性下降关系；同含量的碳化硼， B4C/Al 材料的中子屏蔽效果要大大优于聚乙烯碳化硼材料；在等厚度条件下，模拟试样 B20等的中子屏蔽效果要优于水、铜、混凝土等常规屏蔽材料；材料厚度与中子透射系数呈指数下降关系，且单位厚度的增加对中子透射系数改变很大；含硼量对热中子透射系数影响很大；在热中子能区，中子每单位能量的变化对中子透射系数改变较大；在慢中子能区，中子每单位能量的变化对中子透射系数改变很小.Abstract: Three groups of neutron shielding experiments were set up to study the shielding performance of B4C/Al composite, using the Monte-Carlo method. We have made the following changes: the content of boron carbide 20%-40%, neutron energy 200 eV-15 keV, material thickness 0.3-2 cm, so that we can draw the conclusions: the content of boron carbide and neutron transmission coefficient show a linear relation, with a big drop; under the same neutron energy, the neutron-shielding qualities of simulated specimens are for better than polyethylene boron carbide at the same content of B4C and water, copper, and concrete at the same thickness; an exponential decline relationship is exhibited by material thickness and neutron transmission coefficient, which change greatly with the increase in unit material thickness; the content of boron affects the thermal neutron transmission coefficient seriously. In the thermal neutron energy region, the change of per unit neutron energy(100 eV) has a big influence on neutron transmission coefficient. In the slow neutron energy region, the influence is small.
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