Institute of Chemistry, St. Petersburg State University, Peterhof, Universitetsky prospect, 26, 198504 Saint-Petersburg, Russia.
Khlopin Radium Institute, 2 Murinsky prospect, 28, 194021 Saint-Petersburg, Russia.
Sensors (Basel). 2020 Mar 13;20(6):1604. doi: 10.3390/s20061604.
The quantification of plutonium in technological streams during spent nuclear fuel (SNF) reprocessing is an important practical task that has to be solved to ensure the safety of the process. Currently applied methods are tedious, time-consuming and can hardly be implemented in on-line mode. A fast and simple quantitative plutonium (IV) analysis using a potentiometric sensor array based on extracting agents is suggested in this study. The response of the set of specially designed PVC-plasticized membrane sensors can be related to plutonium content in solutions simulating real SNF-reprocessing media through multivariate regression modeling, providing 30% higher precision of plutonium quantification than optical spectroscopy.
在乏核燃料（SNF）再处理过程中对工艺流中钚的定量分析是一项重要的实际任务，必须加以解决以确保过程的安全。目前应用的方法繁琐、耗时，并且很难实现在线模式。本研究提出了一种使用基于萃取剂的电位传感器阵列快速简便地定量分析（IV）钚的方法。通过多元回归建模，通过一组专门设计的 PVC 增塑膜传感器的响应可以与模拟实际 SNF 再处理介质的溶液中的钚含量相关联，提供比光学光谱法高出 30%的钚定量精度。
