One problem associated with the recovery of spent nuclear fuel is the separation of lanthanides generated during the fission of 235U from the remaining actinides in the nuclear fuel cycle. The process for treating radioactive spent fuel requires a material that has radiolytic stability, is reusable, and generates little extraneous waste.The basis for the separation procedures required is through a group of ion exchangers that are composed of phosphonate-phosphates with the general composition of M(O3PC6H4PO3)0.5(HPO4)�nH2O where M is Zr4+ or Sn4+. These compounds are porous and exhibit low affinity for ions of 1+ and 2+ charge but are highly selective for ions of higher charges (3+,4+). By utilizing oxidation procedures and solution pH, it is proposed that a clean separation of lanthanides of 3+ charge and actinyl ions of 1+ charge can be effected. These ion exchangers are simple to prepare and may ultimately be recycled for increased efficiency.  Early attempts at the separation of lanthanides from actinides will be shown. This work is in collaboration with Los Alamos National Laboratory � Carlsbad Operations (LANL-CO) and Savannah River National Laboratory (SRNL).

Tetravalent metal phosphonate-phosphate hybrids as ion exchange materials for the nuclear fuel cycle

248th National Meeting (2014)

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