中子剂量当量仪的设计  

A neutron dose equivalent meter at CAEP

作　　者：田时海[1,2] 卢艳[1,2] 王和义[1] 陈旭[2] 袁永刚[1] 

机构地区：[1]中国工程物理研究院核物理与化学研究所,绵阳621900 [2]四川大学原子核科学技术研究所辐射物理及技术教育部重点实验室,成都610065

出　　处：《核技术》2012年第9期665-669,共5页Nuclear Techniques

基　　金：国家磁约束核聚变能研究专项资助(2011GB111001)

摘　　要：为了提高中子剂量当量测量的准确度,利用MCNP5程序模拟优化了一种球形中子剂量当量仪的能量响应曲线。模拟结果表明,当聚乙烯厚度为10 cm,镉片处于聚乙烯慢化体中0.9–1.0 cm、半径为0.45 cm、长度0.1 cm时,在能量为2.53×10–8–10 MeV,能量响应因子为0.2–1.8,并与相关剂量仪性能进行比较,从而验证了此中子剂量当量仪设计的准确性。The measurement of neutron dose equivalent has been a widespread need in industry and research. In this paper, aimed at improving the accuracy of neutron dose equivalent meter, a neutron dose counter is simulated with MCNP5, and the energy response curve is optimized. The results show that the energy response factor is from 0.2 to 1.8 for neutrons in the energy range of 2.53× 10-8 MeV to 10 MeV. Compared with other related meters, it turns that the design of this meter is right.

关 键 词：剂量当量 能量响应 响应因子 

分 类 号：O571.5[理学—粒子物理与原子核物理]