B4C-PE复合材料中子屏蔽性能研究  

Study on Neutron Shielding Properties of B4C-PE Composite Materials

作　　者：孟宪芳[1] 孙超[1] 张龙[1] 曹可 秦培中[1] MENG Xian-fang;SUN Chao;ZHANG Long;CAO Ke;QIN Pei-zhong(Beijing Research Center for Radiation Application,Beijing Key Laboratoryof Radiation Advanced Materials,Beijing 100015,China)

机构地区：[1]北京市射线应用研究中心辐射新材料北京市重点实验室

出　　处：《核电子学与探测技术》2019年第3期260-264,共5页Nuclear Electronics & Detection Technology

摘　　要：利用252Cf中子源产生快中子场和热中子场,对系列不同B4C含量B4C-PE复合材料的中子宏观截面进行了实验研究和MCNP模拟计算.结果表明:热中子宏观截面在±5%内相符,快中子宏观截面在±10%内相符;B4C-PE复合材料对热中子的屏蔽效果明显好于聚乙烯.研究结果可为中子屏蔽材料研发和工程设计提供参考.In fast and thermal neutron field produced by a 252Cf source, experiments and MCNP (Monte Carlo N Particle Transport Code, MCNP) calculation were carried out on neutron macroscopic cross section of series B4 C-PE composite materials of different B4C content. Results show that neutron macroscopic cross section values by testing and calculating in the same condition accord in ± 5 % for thermal neutrons and ± 10% for fast neutrons. Shielding properties of B4C-PE are apparently better than PE for thermal neutrons. The results can provide data support and guidance for neutron shielding materials research and neutron shielding projects.

关 键 词：252Cf中子源 中子宏观截面 MC模拟 B4C-PE复合材料 

分 类 号：TL375.7[核科学技术—核技术及应用]