DOI

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.

Original languageEnglish
Article number1604
Number of pages11
JournalSensors (Switzerland)
Volume20
Issue number6
DOIs
StatePublished - Mar 2020

    Scopus subject areas

  • Analytical Chemistry
  • Instrumentation
  • Atomic and Molecular Physics, and Optics
  • Electrical and Electronic Engineering
  • Biochemistry

    Research areas

  • Plutonium, Potentiometric sensors, PUREX, Sensor array, Spent nuclear fuel, REGRESSION, URANIUM, SPECTROPHOTOMETRIC DETERMINATION, RAMAN, plutonium, MEMBRANE SENSOR, PUREX PROCESS, MIXTURES, sensor array, potentiometric sensors, ELECTRODE, spent nuclear fuel, NITRIC-ACID

ID: 52887110