Strontium and Actinide Separations from High Level Nuclear Waste Solutions Using Monosodium Titanate 2. Actual Waste Testing

Authors: Peters, T.¹; Barnes, M.¹; Hobbs, D.¹; Walker, D.¹; Fondeur, F.¹; Norato, M.¹; Fink, S.¹; Pulmano, R.²

Source: Separation Science and Technology, Volume 41, Number 11, 2006 , pp. 2409-2427(19)

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Abstract:

Pretreatment processes at the Savannah River Site will separate 90 Sr, alpha‐emitting and radionuclides (i.e., actinides) and 137 Cs prior to disposal of the high‐level nuclear waste. Separation of 90 Sr and alpha‐emitting radionuclides occurs by ion exchange/adsorption using an inorganic material, monosodium titanate (MST). Previously reported testing with simulants indicates that the MST exhibits high selectivity for strontium and actinides in high ionic strength and strongly alkaline salt solutions. This paper provides a summary of data acquired to measure the performance of MST to remove strontium and actinides from actual waste solutions. These tests evaluated the effects of ionic strength, mixing, elevated alpha activities, and multiple contacts of the waste with MST. Tests also provided confirmation that MST performs well at much larger laboratory scales (300 - 700 times larger) and exhibits little affinity for desorption of strontium and plutonium during washing.

Keywords: Sorption, ion exchange, strontium, plutonium, nept

Document Type: Research article

DOI: http://dx.doi.org/10.1080/01496390600742963

Affiliations: 1: Savannah River National Laboratory, Westinghouse Savannah River Company, Aiken, SC, USA 2: BP West Coast Products LLC, Carson, CA, USA

Publication date: 2006-01-01