Abstract The high activity of spent cartridge filters from the cooling water polishing system of a nuclear research reactor precludes, in routine work of a waste characterization program, the usual method of radiochemical analysis of filter samples. For this waste, the dose-to-activity method, using a gamma spectrometer and a dose rate meter, is an alternative for the determination of the activities of the gamma emitters with acceptable accuracy. The ratio of photon peak-areas from different radionuclides, corrected by the detector energy-dependent efficiency, allowed estimating the proportions between the activities of the different radionuclides present. Finally, the simulation of the counting geometry, using the point-kernel method to estimate the air dose rate resulting from an arbitrary concentration of those radionuclides and the comparison of the calculated with the measured air dose rate have yielded the needed estimates of the activity concentrations. The aim of this paper is to report the development of the method applied for the determination of the concentration of the gamma-emitters present in cartridge filters from the IEA-R1 Nuclear Research Reactor.

中文翻译：

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用剂量-活度法清点核研究反应堆初级回路用过的筒式过滤器中的放射性核素

摘要 核研究反应堆冷却水精制系统中的废筒式过滤器的高活性妨碍了在废物表征程序的日常工作中对过滤器样品进行放射化学分析的常用方法。对于这种废物，使用伽马光谱仪和剂量率计的剂量-活度方法是一种以可接受的准确度确定伽马发射体活动的替代方法。来自不同放射性核素的光子峰面积比，由探测器能量相关效率校正，允许估计存在的不同放射性核素的活性之间的比例。最后，模拟计数几何，使用点核法估计由这些放射性核素的任意浓度引起的空气剂量率，并将计算结果与实测空气剂量率进行比较，从而得出所需的活动浓度估计值。本文的目的是报告用于测定 IEA-R1 核研究反应堆筒式过滤器中存在的伽马发射体浓度的方法的发展。