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Research over the past decade has studied the adsorption of plutonium and uranium onto monosodium titanate (MST) in alkaline solutions. Tests showed that MST would remove the targeted radionuclides from simulated alkaline waste. Testing also indicated that Pu removal kinetics and Np capacity of the MST material impacts the size of equipment and waste blending plans for the Salt Waste Processing Facility (SWPF). Additionally, calculations suggested the baseline MST process may not achieve the desired decontamination in wastes containing elevated concentrations of Pu and Np. In this task, the authors investigated the performance of non-baseline process parameters and their effectiveness for treating waste feed in the Salt Waste Processing Facility. The work addresses a DOE request in support of technical needs expressed, in part, by the Engineering, Procurement, and Construction Contractors for the Salt Waste Processing Facility. The work investigated the effect of increased MST addition (up to 1.2 g/L) and the benefit of extra filtration steps with multiple additions of MST to salt waste containing actinides and strontium. Both simulant and actual waste testing occurred. Actual waste tests used a Tank 39H composite waste solution. In addition, testing to determine desorption of actinides from residual MST occurred. The release of sorbed Sr and actinides from loaded MST during the washing stages in the Salt Waste Processing Facility is an unresolved process behavior. Desorption tests assessed this potential problem using loaded MST from the residue of the MST adsorption tests. Analysis of non-radioactive Sr in the tests proved difficult due to the low concentration of nonradioactive Sr and its nearness to the method detection limit for ICP-MS. Efforts to use AMP to minimize dilution of actual waste for removal from the cell did not help for this analysis since instrument dilution still proved necessary due to the salt content

MONOSODIUM TITANATE MULTI-STRIKE TESTING