中子源屏蔽体尺寸和源室结构对本底的影响  

Influence on background counts by the shielding body and structure of the room for a neutron source

作　　者：曾心苗[1] 周鹏[1] 许自炎[1] 秦培中[1] 胡祥[1] 郑金美[1] 王炳林[1] 

机构地区：[1]北京市射线应用研究中心,北京100012

出　　处：《核技术》2008年第5期344-347,共4页Nuclear Techniques

摘　　要：采用蒙特卡罗粒子输运计算程序(Monte Carlo N-partical transport code,MCNP),就中子源屏蔽体和中子源室结构对屏蔽体不同探测位置的中子透射和反射情况进行了计算机模拟计算。计算采用的入射粒子分别为14 MeV和5 MeV的单能中子以及252Cf自发裂变中子。从计算结果看,屏蔽体的尺寸和结构对中子透射的影响都比较明显;源室的结构和地坑也对本底产生较大影响。通过理论计算可以了解屏蔽体结构和源室情况对测量本底的影响,可为源室设计以及中子实验研究提供重要参考。The MCNP code was used to simulate neutron transmission and reflection from neutron sources of 14 MeV, 5 MeV and ^252Cf with a shielding body of different sizes in a room of different structures. The results show that both the size and the structure of the shielding body have quite big influence on the transmission of the neutron, and that the room structure and pit have quite big influence on the background reflection. The study provides a valuable reference for designing a neutron source room for experiment with a neutron source.

关 键 词：中子屏蔽体 源室结构 中子透射 本底 MCNP程序 

分 类 号：O571.53[理学—粒子物理与原子核物理]