Senaratne U P, Jester W A, Bleistein C D
Department of Nuclear Engineering, Penn State University, University Park, 16802, USA.
Health Phys. 1997 Oct;73(4):601-10. doi: 10.1097/00004032-199710000-00003.
An analytical method utilizing ion chromatography, a non-radioactive strontium carrier, and liquid scintillation spectroscopy to individually quantify 89Sr and 90Sr in nuclear reactor effluent is presented. It is observed that this method is less time consuming than traditional procedures for quantifying radio-strontium, deals comprehensively with separation and subsequent isotopic quantification of strontium, and avoids difficulties reported in previous research. The equipment, solutions and operating conditions for the chromatographic separation of strontium in aqueous solution are identified, and the strontium fraction is shown to elute between 7 and 7.5 min after injection. The beta spectra of 90Sr, 89Sr and 90Y are obtained using liquid scintillation spectroscopy, and the effects of quenching are shown to be negligible. The positions of the liquid scintillation windows within the combined beta spectra facilitating isotopic analysis of 89Sr and 90Sr are identified, followed by the system of equations to quantify 89Sr and 90Sr within a sample. The performance of the method is evaluated using five solutions representing effluent containing radio-strontium at known concentrations. It is observed that when the 89Sr and 90Sr concentrations each are approximately 37 Bq mL(-1) or more, the method over-estimates the 89Sr activity by 15-20% and under-estimates the 90Sr activity by 10-30%, while yielding the total radio-strontium activity to within 1-4% of expected. The lower limit of detection of the system for either 89Sr or 90Sr is shown to be approximately 0.8 Bq mL(-1) of effluent.
本文介绍了一种利用离子色谱法、非放射性锶载体和液体闪烁光谱法对核反应堆流出物中的89Sr和90Sr进行单独定量分析的方法。据观察，该方法比传统的放射性锶定量方法耗时更少，能全面处理锶的分离及后续同位素定量问题，且避免了先前研究中报道的困难。确定了水溶液中锶色谱分离的设备、溶液和操作条件，结果表明锶组分在进样后7至7.5分钟之间洗脱。利用液体闪烁光谱法获得了90Sr、89Sr和90Y的β能谱，结果表明猝灭效应可忽略不计。确定了组合β能谱中便于对89Sr和90Sr进行同位素分析的液体闪烁窗口位置，随后给出了用于定量样品中89Sr和90Sr的方程组。使用五种代表已知浓度含放射性锶流出物的溶液对该方法的性能进行了评估。据观察，当89Sr和90Sr的浓度均约为37 Bq mL(-1)或更高时，该方法对89Sr活度的高估幅度为15 - 20%，对90Sr活度的低估幅度为10 - 30%，而总放射性锶活度的测定结果与预期值的偏差在1 - 4%以内。该系统对89Sr或90Sr的检测下限显示约为流出物0.8 Bq mL(-1)。
