核燃料后处理萃取液中铀浓度测量装置设计

摘要

A set of radiation measuring devices for measuring uranium concentration was designed and manufactured,the radiation source is 241Am. A special sampling box was designed and processed,which thickness is 10mm,the γ-ray pass through the sampling box after collimation and reach the detector,NaI (Tl) scintillation detector was used to detector γ-ray. The signal from the detector reaches the host after initial processing. The calibration of the instrument and the calculation of uranium concentration are done by the host. The measuring device is placed in the Analysis room. The uranium solution was sampled and tested,and the measurement error is within 2% with the chemical titration method is used as the standard value.%设计加工了一套用于核燃料后处理萃取液中铀浓度测量的射线测量装置,该装置放射源采用241Am,专门加工特制取样盒,厚度10 mm,射线经过准直后穿过取样盒到达探测器.探测器采用NaI闪烁探测器,信号初步处理后进主机,仪器的标定和铀浓度的计算由主机完成.该测量设备放置在分析室,可以进行采样检测,将化学滴定法测量结果作为标准值,测量误差在2%以内.