辐射防护 ›› 2021, Vol. 41 ›› Issue (1): 39-43.

• 辐射防护方法 • 上一篇    下一篇

硼铝复合材料热中子屏蔽性能分析

李长园1,2, 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   

  1. 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
  • 收稿日期:2019-11-25 出版日期:2021-01-20 发布日期:2021-03-15
  • 通讯作者: 夏晓彬。E-mail:xiaxiaobin@sinap.ac.cn
  • 作者简介:李长园(1984—),男,2008年本科毕业于新疆大学理论物理专业,2011年硕士毕业于新疆大学核技术及应用专业,博士就读于中国科学院大学核技术及应用专业,高级工程师。E-mail:lichangyuan@sinap.ac.cn

Analysis of thermal neutron shielding performance ofboron-aluminum composite material

LI Changyuan1,2, XIA Xiaobin2, YANG Zhongtian3, LIU Yuchen3, ZHANG Zhihong2, WANG Jianhua2, CAI Jun2, HU Jifeng2   

  1. 1. University of Chinese Academy of Sciences, Beijing 100049;
    2. Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800;
    3. China Institute for Radiation Protection, Taiyuan 030006
  • Received:2019-11-25 Online:2021-01-20 Published:2021-03-15

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。

关键词: 硼铝复合材料, 热中子吸收性能, MCNP程序, 实验测量

Abstract: 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.

Key words: boron-aluminum composite material, thermal neutron absorption performance, MCNP program, experimental measurement

中图分类号: 

  • TL75+2.3