便携式 ^(235)U 丰度仪的改进与应用研究  

APPLICATION RESEARCH OF IMPROVED 235 U ENRICHMENT METER

作　　者：刘大鸣[1] 吴昕[1] 吕钊[1] 唐培家[1] 吕峰[1] 王允美 

机构地区：[1]中国原子能科学研究院放射化学研究所

出　　处：《原子能科学技术》1998年第3期208-213,共6页Atomic Energy Science and Technology

摘　　要：对基于ＮａＩ（Ｔｌ）探测器的铀丰度测量原型仪器进行了改进。改进后的仪器可以运用计算机进行在线数据获取。利用标准燃料棒对仪器进行了刻度实验，运用刻度结果对大亚湾核电厂的燃料棒进行了测量，丰度测量值与标称值在－１．０％—２．８％以内符合。A prototype 235 U enrichment meter based on NaI(Tl) γ spectroscopy is improved and it works under the principle of that the enrichment of 235 U is proportional to the radioactivity of 185 keV γ ray when the sample is thick infinitely. The data of radioactivity from 235 U can be collected by a notebook computer and the interface control software is written using C++ language. The meter was tested and calibrated using standard fuel rods in fuel fabrication plant. For single fuel rod, the measured value of 235 U enrichment is agreeable with declared value within-1 0 %—2 8 %.

关 键 词：铀丰度仪 核保障 非破坏分析 燃料元件 

分 类 号：TL271[核科学技术—核燃料循环与材料] TL816.2