关键词: 
辐射屏蔽材料 /
MCNP模拟 /
中子和γ射线 /
稀土-高分子/重金属材料

摘要: 为研究新型复合屏蔽材料的最佳厚度与各种成分最佳配比， 用MCNP计算了中子、 γ射线在稀土 高分子与重金属复合材料中的通量。 对中子、 γ射线在屏蔽体中变化规律进行了深入探索， 同传统复合屏蔽材料的屏蔽性能进行了对比。 结果表明， 中子和γ射线通过屏蔽体时， 其强度遵循指数衰减规律。 新型屏蔽材料对中子的屏蔽效果均优于铅硼聚乙烯， 对γ射线的屏蔽效果均劣于W Ni合金， 且并非稀土含量越高， 材料对中子辐射屏蔽能力越强。 A series of shielding analyses have been performed to estimate the material composition and optimum thickness required for a new radiation shield with various rareearth doped polymer and heavy metal mixtures. The neutron and γ photon fluxes have been calculated by Monte Carlo NParticle(MCNP) transport code. The results indicate that the relative fluxes of γ photon and neutron in both traditional and new composite materials follow an exponential decay rule with the distance of penetration. It can be seen that the composite material consisting of rareearth doped polymer and heavy metal has stronger neutron shielding performance than leadboron polyethylene, but weaker γ shielding effectiveness than WNi alloy. It is also found that materials with more components of rare earth elements don’t always provide better neutron shielding performance.