화학공학소재연구정보센터
Separation Science and Technology, Vol.40, No.15, 3093-3111, 2005
Strontium and actinide separations from high level nuclear waste solutions using monosodium titanate 1. Simulant testing
High-level nuclear waste produced from fuel reprocessing operations at the Savannah River Site (SRS) requires pretreatment to remove Cs-137, Sr-90, and alpha-emitting radionuclides (i.e., actinides) prior to disposal. Separation processes planned at SRS include caustic side solvent extraction, for Cs-137 removal, and ion exchange/sorption of Sr-90 and alpha-emitting radionuclides with an inorganic material, monosodium titanate (MST). The predominant alpha-emitting radionuclides in the highly alkaline waste solutions include plutonium isotopes Pu-238, Pu-239, and Pu-240. This paper provides a summary of data acquired to measure the performance of MST to remove strontium and actinides from simulated waste solutions. These tests evaluated the influence of ionic strength, temperature, solution composition, and the oxidation state of plutonium.