Abstract Current internal dosimetry monitoring programmes generally feature periodic measurements that are defined for the most commonly-encountered radionuclides. These programmes are not directly applicable to research centres that produce novel and short-lived radionuclides which are then used for the manufacture of radiopharmaceuticals, such as the CERN-MEDICIS facility hosted at CERN. This work presents an in vivo internal dosimetry programme based on the concept of triage monitoring. The programme allows to comply with the annual committed effective dose limit of E 50 = 1 mSv by performing rapid gamma-spectroscopy screening measurements. Two portable spectrometers (HPGe- and NaI-based) were characterised using two different phantoms: a simplified model of the human torso and an anthropomorphic phantom allowing for customised source-filling geometries. The efficiencies of the spectrometers were determined using both phantoms and the minimum detectable activities were computed as a function of the measuring time for a selection of 21 among novel and conventional radionuclides. The minimum detectable activity was then used to calculate the minimum committed effective dose associated to each measurement for a realistic intake scenario. For a single screening measurement of 30 s performed at the end of the working day, the minimum detectable committed effective dose resulting from a radionuclide inhalation ranged between few μ Sv and hundreds of μ Sv for the majority of the considered radionuclides. The suggested approach allows to set up pragmatic in vivo measurements to monitor the workers’ internal contamination in research centres and industries where unsealed conventional and/or novel radionuclides may be handled.

中文翻译：

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使用便携式伽马能谱仪在摄入常规和新型放射性核素后进行分类监测

摘要 当前的内部剂量学监测程序通常具有为最常遇到的放射性核素定义的定期测量。这些计划并不直接适用于生产新型和短寿命放射性核素然后用于制造放射性药物的研究中心，例如在 CERN 托管的 CERN-MEDICIS 设施。这项工作提出了一种基于分类监测概念的体内内部剂量测定程序。该计划允许通过执行快速伽马光谱筛查测量来遵守 E 50 = 1 mSv 的年度承诺有效剂量限制。两个便携式光谱仪（基于 HPGe 和 NaI）使用两种不同的体模进行表征：一个简化的人体躯干模型和一个拟人模型，允许定制的源填充几何形状。光谱仪的效率是使用两种体模确定的，最小可检测活动被计算为测量时间的函数，从新的和传统的放射性核素中选择 21 种。然后使用最小可检测活动来计算与实际摄入情况的每次测量相关的最小待积有效剂量。对于在工作日结束时进行 30 秒的单次筛查测量，对于大多数考虑的放射性核素，吸入放射性核素产生的最小可检测待积有效剂量介于几 μ Sv 和数百 μ Sv 之间。