摘要
用伴随α粒子的D-T中子飞行时间技术进行爆炸物安全检测过程中,D-T中子和伴生的γ射线会对检测仪器、工作人员和旅客造成辐射损害,并影响环境,因此须对中子源进行有效屏蔽。本文用MCNP5程序计算了D-T中子在不同屏蔽材料组合条件下检测仪器屏蔽效果及人员的有效剂量当量。结果表明,对中子源有效屏蔽后,检测仪器的快中子当量为屏蔽前的3.44%,满足检测要求,人员的剂量当量在不同屏蔽组合下,设定相应活动区域,可满足国家辐射屏蔽规定,且中子活化造成的环境影响可忽略不计。
In developing a neutron generator-based security check system for explosives using associated α particles and neutron flight of time technique,it is important to avoid possible influences by the D-T neutron and secondary γ-rays to the inspection equipment,staffs,passengers and ambient environment.In this paper,the MCNP5 code is used to simulate the coupled transport of neutrons and γ-rays,for calculating the shield effect of inspection equipment and the individual dose equivalent.The results show that after effective shielding,the fast neutron equivalent of inspection equipment can be reduced to 3.44% of the source flux,satisfying the shielding requirement.The individual dose equivalent meets the national regulations in specified access areas.The influences to surrounding environment can be neglected.
出处
《核技术》
CAS
CSCD
北大核心
2010年第9期671-674,共4页
Nuclear Techniques
关键词
爆炸物检测
D-T中子
蒙特卡罗模拟
屏蔽设计
Explosive inspection
D-T neutron
Monte-Carlo simulation
Shielding design
