Extraction of ²⁴¹ Am ³⁺ from ¹⁵⁴–¹⁵² Eu ³⁺ using a TODGA-inspired, BTP complexant in an octanol: Kerosene diluent system

Nuclear energy is a highly energy-dense, low-greenhouse gas power source whose long-term sustainability depends on advanced fuel cycle strategies which enable efficient and proliferation-resistant separation of actinides from lanthanides. In this work, a new class of amide-functionalized bis-1,2,4-triazinyl-2,6-pyridine (BTP) complexants, inspired by N,N,N′,N′-tetraoctyldiglycolamide (TODGA), for the selective partitioning of 241Am3+ from 154–152Eu3+ in a 1-octanol/kerosene (1:1 v/v) biphasic diluent system is presented. The optimized system achieves rapid extraction in a mere ten minutes of contact time, high Am distribution values and separation factors, while surpassing previously reported performance metrics of BTP analogues of this class, and others. Importantly, decomplexation studies revealed efficient actinide recovery and excellent complexant recyclability, underscoring the potential of these hybrid amide–triazine architectures for sustainable spent nuclear fuel reprocessing. Equilibration, acid and complexant concentration dependency, back-extraction, and recyclability are reported herein.