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The goal of this project is to examine the potential long term performance of the proposed aluminosilicate waste/storage form for the isolation and eventual direct disposal of the cesium and strontium separated from recycled nuclear fuel. In the first phase of this work, researchers will investigate the sintering procedure to prepare the drum-like aluminosilicate waste/storage form from the as-received aluminosilicate powder, and then examine the basic physical properties, phase structure and microstructure of the sintered aluminosilicate with /without mixing solution with several ppm Cs/Sr. In the second phase, researchers will evaluate the interaction of the proposed waste form with structural materials proposed for the storage and disposal containers to determine if the materials are compatible with the loaded aluminosilicate waste form. In the third phase of the work, researchers will examine the leach resistance of the aluminosilicate material, with particular attention to the leachability of barium from the synthesized waste form. As a part of this work, researchers will work with researchers at Argonne National Laboratory to compare the performance of synthesized “cold” materials with archived samples of aluminosilicate minerals containing radiocesium (137Cs, approximately 40 years old) to examine the impact of transmutation on the ability of the proposed waste form to isolate barium (the decay product of 137Cs).


Aluminum silicates; Barium; Cesium; Leaching; Radioactive wastes—Storage; Radioactive wastes — Transmutation; Strontium


Nuclear | Nuclear Engineering | Radiochemistry