Salako Q, DeNardo S J
Molecular Cancer Institute, University of California, Davis, Sacramento 95816, USA.
Health Phys. 1997 Jan;72(1):56-9. doi: 10.1097/00004032-199701000-00008.
Large hospitals and biomedical research centers utilize decay-in-storage programs to minimize the volume of their low level radioactive waste. However, some medically useful radionuclides often contain small amounts of long-lived radionuclidic impurities which may complicate simple waste management procedures. We have evaluated the extent of this problem in low level radioactive waste involving 67Cu and (111)In over a 6-mo cycle of decay-in-storage by identifying the residual radionuclides in our dry waste using a multichannel analyzer. The multichannel analyzer was also used to quantify the radionuclide constituents of our liquid waste at the beginning of a decay-in-storage cycle. Radionuclides were identified by the presence of characteristic photopeaks of each isotope in the gamma spectrum and quantified by region of interest analysis. After a decay-in-storage cycle, long-lived 58Co, 57Co, and 56Co isotopes were observed in dry 67Cu waste and (114m)In identified in dry (111)In waste. The (114m)In was detected in dry (111)In waste containing initial (114m)In activity of 740 kBq (20 microCi), while the cobalt radionuclides were detected in dry 67Cu waste containing initial 58Co, 57Co, and 56Co activities of 444, 148, and 148 kBq (12, 4, and 4 microCi), respectively. Such dry low level radioactive waste was thus disqualified from short-term radioactive waste storage programs. The radionuclide constituents in the liquid waste were quantified in microCi mL(-1) and confirmed to be within the Nuclear Regulatory Commission set limits of 2 x 10(-4), 6 x 10(-4) and 6 x 10(-5) microCi mL(-1) for 58Co, 57Co, and 56Co, respectively, before disposal. The highest levels of long-lived isotopes that have been found in our liquid low level radioactive waste at the beginning of decay-in-storage were 5.5 x 10(-4), 4.8 x 10(-4), and 1.4 x 10(-4) microCi mL(-1) for 58Co, 57Co, and 56Co, respectively. Gamma spectrometry can be used to aid waste segregation and final management decisions on low level radioactive waste.
大型医院和生物医学研究中心利用储存衰变程序来尽量减少其低水平放射性废物的体积。然而,一些医用放射性核素通常含有少量长寿命放射性核素杂质,这可能会使简单的废物管理程序变得复杂。我们通过使用多通道分析仪识别干废物中的残留放射性核素,评估了在为期6个月的储存衰变周期中,涉及67Cu和(111)In的低水平放射性废物中这一问题的严重程度。多通道分析仪还用于在储存衰变周期开始时对我们的液体废物中的放射性核素成分进行定量。通过γ能谱中各同位素特征光峰的存在来识别放射性核素,并通过感兴趣区域分析进行定量。在一个储存衰变周期后,在67Cu干废物中观察到了长寿命的58Co、57Co和56Co同位素,在(111)In干废物中识别出了(114m)In。在初始(114m)In活度为740 kBq(20微居里)的(111)In干废物中检测到了(114m)In,而在初始58Co、57Co和56Co活度分别为444、148和148 kBq(12、4和4微居里)的67Cu干废物中检测到了钴放射性核素。因此,这种干低水平放射性废物不符合短期放射性废物储存程序的要求。在处置前,对液体废物中的放射性核素成分以微居里每毫升(-1)为单位进行了定量,并确认其分别在核管理委员会规定的58Co、57Co和56Co的限值2×10(-4)、6×10(-4)和6×10(-5)微居里每毫升(-1)范围内。在储存衰变开始时,我们的液体低水平放射性废物中发现的长寿命同位素的最高水平分别为58Co、57Co和56Co的5.5×10(-4)、4.8×10(-4)和1.4×10(-4)微居里每毫升(-1)。γ能谱分析可用于辅助低水平放射性废物的废物分类和最终管理决策。