Radionuclide separations for the reduction of high-level waste volume

Applying solvent extraction and chromatographic methods in the separation of Pu, Am, U, 90Sr, and 137Cs from radioactive U.S. defense wastes is described. These wastes consist of large amounts of non-radioactive material (e.g., NaOH, NaNO3, NaNO2, Fe(OH)3, Zr(OH)4, etc.) contaminated with various radionuclides. Separating these radionuclides from the bulk components of the wastes (HLW) to be disposed. The TRUEX solvent extraction process or an analogous extraction chromatographic process can be used to separate Pu, Am, and U from acid-dissolved sludge wastes. The SREX solvent extraction process can be used to separate 90Sr from acid-dissolved sludge wastes. Alternatively, extraction chromatographic techniques can be used to separate 90Sr. Ion exchange methods can be used to separate 137Cs, 90Sr, and Pu from alkaline tank supernates, sludge wash solutions, and dissolved salt cakes