The chemical analysis of spent nuclear fuels is essential to design future nuclear fuelscycle and reprocessing methods but also for waste management. The analysis cycle consistsof several chemical separation steps which are time consuming and difficult to implement dueto confinement in glove boxes. It is required that the separation steps be automated and thatthe volume of radioactive waste generated be reduced. The design of automated, miniaturizedand disposable analytical platforms should fulfill these requirements.This project aims to provide an alternative to the first analytical step of the spent fuelsanalysis: the chromatographic separation of Uranium and Plutonium from the minor actinidesand fission products.The goal is to design a miniaturized platform showing analytical performancesequivalent to the current process, and to reduce both the exposure of workers throughautomation, and the volume of waste produced at the end of the analysis cycle. Thus, theseparation has been implemented on a disposable plastic microsystem (COC), specificallydesigned for automation: a lab on a Compact Disk or lab-on-CD.The developed prototype incorporates an anion-exchange monolithic micro-columnwhose in-situ synthesis as well as surface functionalization have been optimized specificallyfor the desired separation. The development of an adapted separation protocol was carried outusing a simulation tool modeling the elution of the various elements of interest. This tool isable to predict the column geometry (length and cross section) suited to obtain pure fractionsof Uranium and Plutonium as a function of the sample composition.Finally, the prototype is able to automatically carry out four separationssimultaneously reducing the number of manipulations, the analysis time and reducing thevolume of liquid waste by a factor of 1000.
