After promising first extraction experiments, the question rises how well this new ligand resists ionizing irradiation. Because the solvent is exposed to highly active solutions of dissolved nuclear fuel, it will undergo degradation and react with radicals formed in the solution. The first fundamental irradiation studies using gamma irradiation were already conducted at SCK CEN, to identify the main degradation compounds of mTDDGA. In the next step, degradation compounds were synthesized at the University of Twente and distributed via a European collaboration in the frame of the GENIORS project. The following step, which is the objective of this master thesis, is to screen and characterize the extraction behavior of these degradation compounds. Here, a parametric study will be performed by changing the acid concentration, the concentration of the ligand, the temperature and extraction time. In addition to the parametric study, the removal of degradation compounds from the irradiated solvent will be studied. This can be achieved by an alkaline washing step, which deprotonates acidic degradation compounds, and makes them water soluble. The evaluation of the extractions will be conducted using techniques such as α-spectrometry, γ-spectrometry and Inductively Coupled Mass Spectrometry (ICP-MS).
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