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机构地区:[1]中国原子能科学研究院
出 处:《辐射防护》1999年第2期132-134,共3页Radiation Protection
摘 要:为测量环境γ辐射周围剂量当量,对G-M计数管的自身本底和能量响应特性进行了实验研究。采用铅、锡两种金属材料做为过滤器改变计数管的能量响应,为拓宽仪表量程采用两种尺寸计数管。两种计数管在60keV至662keV范围内,H*(10)/X随能量变化与ICRU47号报告结果最大偏离分别为-23%和+24%,仪表量程为10nSv·h-1~10mSv·h-1,探测下限可达到40nSv·h-1。For measuring H *(10) from environmental γ radiation, the background and energy response of G M counter was studied. The energy response can be improved by a filter consisted of Sn and Pb. In order to extend the measuring range, we used two counters with different size. For two improved G M counters, the maximum deviations of H *(10) varing as energy of γ radiation from the results given by ICRU 47 are -23% and +24%, respectively between 60 keV and 662 keV. The instrument range is 10 nSv·h -1 ~10 mSv·h -1 , and the lower limit of detection is in the order of 40 nSv·h -1 . (
分 类 号:X837[环境科学与工程—环境工程] TL811.3[核科学技术—核技术及应用]
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