Gamma radiolytic stability of the novel modified diglycolamide 2,2 '-oxybis(N,N-didecylpropanamide) (mTDDGA) for grouped actinide extraction KU Leuven
Reprocessing of spent nuclear fuel aims at improving resource efficiency and reducing its radiotoxicity and heat production in the long term. The necessary separation of certain metal ions from the spent fuel solutions can be achieved using different solvent extraction processes. For the scenario of the EURO-GANEX process, the use of the new, modified diglycolamide 2,2'-oxybis(N,N-didecylpropanamide) (mTDDGA) was recently proposed to simplify ...