High-level nuclear waste produced from fuel reprocessing operations at the Savannah River Site (SRS) requires pretreatment to remove 134,137 Cs, 90 Sr, and alpha-emitting radionuclides (i.e., actinides) prior to disposal onsite as low level waste. Separation processes at SRS include the sorption of 90 Sr and alpha-emitting radionuclides onto monosodium titanate (MST) and caustic side solvent extraction of 137 Cs. The MST and separated 137 Cs is encapsulated along with the sludge fraction of high-level waste (HLW) into a borosilicate glass waste form for eventual entombment at a federal repository. The predominant alpha-emitting radionuclides in the highly alkaline waste solutions include plutonium isotopes 238 Pu, 239 Pu, and 240 Pu; 237 Np; and uranium isotopes, 235 U and 238 U. This paper describes recent results evaluating the performance of an improved sodium titanate material that exhibits increased removal kinetics and capacity for 90 Sr and alpha-emitting radionuclides compared to the current baseline material, MST.