一种新型中子周围剂量当量(率)测量装置的性能实验  

PERFORMANCE TEST OF A NEW NEUTRON MEASURING APPARATUS FOR AMBIENT DOSE EQUIVALENT(RATE)

作　　者：李桃生[1] 杨连珍[2] 马吉增[2] 

机构地区：[1]清华大学核能和新能源技术研究所,北京100084 [2]中国辐射防护研究院,太原030006

出　　处：《辐射防护》2005年第5期283-290,共8页Radiation Protection

摘　　要：本文介绍一种新型中子周围剂量当量(率)监测方法,搭接了一套单球多计数器的中子周围剂量当量(率)监测装置,利用蒙特卡罗MCNP4A程序模拟计算了中子注量的响应函数,借用“少道”解谱软件进行解谱并对一些辐射防护量进行了计算。通过对252Cf和Am-Be两种中子参考辐射场的测试,表明对中子注量率、周围剂量当量率、单位注量平均周围剂量当量和剂量当量平均能量的计算结果与参考值相比,偏差均小于10%,这种监测方法较好地解决了中子剂量仪表的能量响应问题。Based on a new monitoring method for neutron ambient dose equivalent （rate） introduced in this report, a neutron measuring apparatus for the ambient dose equivalent （rate） witha single sphere and multicounters was set up. The fluence energy response functions were simulated calculated by Monte Carlo MCNP4A program, some radiation protection quantities were evaluated utilizing “few-channel” unfolding code. Through the test for reference radiation fields of ^252Cf and Am-Be, it shows that deviations of calculated results of the neutron fluence rate, ambient dose equivalent rate, per fluence average ambient dose equivalent and dose equivalent average energy are less than 10% comparing to their reference values. This monitoring method could better improve the energy response of neutron dosemeters.

关 键 词：中子位置灵敏计数器 中子周围剂量当量 能量响应矩阵 少道解谱 辐射防护 

分 类 号：TL818[核科学技术—核技术及应用]