Assessing the potential of online ICP–MS analysis to optimize Ca/matrix separation using DGA Resin for subsequent isotopic analysis

Ca isotopes have gained increasing interest as a diagnostic tool for bone diseases due to the variations in abundances as a consequence of changes in bone-mineral balance. Optimized Ca/matrix separation prior to analysis is a prerequisite for reliable isotope ratio measurements in complex biological matrices such as blood, serum, or urine. The online analysis of analyte/matrix separation by ICP-MS enables direct assessment of elution profiles supporting the optimization process. The integration of transient signals and signal suppression challenge the quantification and interpretation of the elution profiles. Mn and Co remain unretained by the DGA Resin (TrisKem International) from nitric acid. Hence, in the present study, these elements were investigated for their application as standards to monitor signal suppression. Successful analyte quantification was accomplished using a dynamic correction strategy applying a linear gradient of a suppression factor based on Mn and Co intensities. An optimized Ca/matrix separation procedure using DGA Resin is proposed based on the results during online ICP-MS analysis. Graphic abstract

High-precision stable zirconium isotope ratio measurements by double spike thermal ionization mass spectrometry

A new method for stable zirconium isotope ratio measurements was achieved based on the combination of a single DGA resin column and the double-spike TIMS technique.

A concept for disposal of highly acidic spent nuclear fuel solutions at PSI

During previous radioanalytical studies at Paul Scherrer Institute ca. 30 L of acidic waste containing spent nuclear fuel was produced, and now they need to be disposed A flow sheet for conditioning of these waste was designed and the extraction chromatography technique is evaluated. Suitable sorbents, such as AMP_PAN, TBP impregnated resin and DGA resin, were selected for the task of Cs-removal, extraction of U and Pu, and extraction of minor actinides and lanthanides, respectively. A pilot device will be built for preliminary tests with simulated solutions, and the facility will be built and evaluated with the real spent fuel solutions.