[en] For several reasons--poor hydraulic behavior, unsatisfactory sorption kinetics, unavailability, in some cases of commercial quantities, etc.--inorganic sorbents have not heretofore been used extensively in the backend of the nuclear fuel cycle. A potential breakthrough in plant scale application of such sorbents in nuclear liquid waste treatment may ensue from research currently underway at several U.S. Department of Energy sites. At Mound Laboratories, calcium hydroxyapatite [Ca₁₀(PO₄)₆(OH)₂], obtained from the Kerr-McGee Co., has been shown in both batch and column tests to effectively remove ²³⁸Pu from certain aqueous wastes generated there; costs and benefits of incorporation of one or more beds of Ca₁₀(PO₄)₆(OH)₂ in the Mound Laboratory waste treatment circuit are being evaluated. An ion exchange process which takes advantage of the great affinity and capacity of sodium titanate [Na(Ti₂O₅H)] for greater than or equal to +2 ions from high alkaline salt solutions has been successfully developed and demonstrated for reduction of plutonium and ²⁴¹Am concentrations of Hanford Plutonium Reclamation Facility salt waste to drinking water levels. Batch distribution data obtained at Sandia Laboratories indicates Na(Ti₂O₅H) may also be useful in chromatographic separation of Am³⁺ and Cm3⁺. Pertinent properties of these inorganic sorbents as well as separation process flowsheets and data are reviewed in this paper