硼铝复合材料热中子屏蔽性能分析  

Analysis of thermal neutron shielding performance of boron-aluminum composite material

作　　者：李长园 夏晓彬[2] 杨仲田[3] 刘宇辰[3] 张志宏[2] 王建华[2] 蔡军[2] 胡继峰[2] LI Changyuan;XIA Xiaobin;YANG Zhongtian;LIU Yuchen;ZHANG Zhihong;WANG Jianhua;CAI Jun;HU Jifeng(University of Chinese Academy of Sciences,Beijing 100049;Shanghai Institute of Applied Physics,Chinese Academy of Sciences,Shanghai 201800;China Institute for Radiation Protection,Taiyuan 030006)

机构地区：[1]中国科学院大学,北京100049 [2]中国科学院上海应用物理研究所,上海201800 [3]中国辐射防护研究院,太原030006

出　　处：《辐射防护》2021年第1期39-43,共5页Radiation Protection

摘　　要：硼铝复合材料因制备工艺简单,力学性能良好,原材料价格低廉等诸多优点被广泛研究,并被用作诸多领域的热中子吸收材料。本文采用理论计算、MCNP软件模拟、实验测量等多种方法对硼铝复合材料的热中子屏蔽性能进行了评估分析。通过理论计算发现,对于相同配比的硼铝复合材料,从材料的热中子吸收性能方面,添加硼单质的效果优于添加碳化硼。通过MCNP程序模拟计算和实验测量发现,硼铝复合材料对能量低于10-7 MeV的中子吸收效果比较显著。Boron-aluminum composite material has been widely studied due to its relatively simple preparation process,good mechanical properties,low price of raw material.Boron-aluminum composite material has been used as thermal neutron absorbing materials in many fields.In this paper,the thermal neutron shielding performance of boron-aluminum composites was analyzed by theoretical formula,MCNP software and experimental measurement.Theoretical calculations show that boron is better as a composite additive than boron carbide when the additive content is the same only in terms of thermal neutron absorption properties of the material.Through simulation calculation of MCNP program and through experimental measurement,it is found that the boron-aluminum composite material has excellent neutron absorption performance with neutron energy less than 10-7 MeV.

关 键 词：硼铝复合材料 热中子吸收性能 MCNP程序 实验测量 

分 类 号：TL75+2.3[核科学技术—辐射防护及环境保护]