Thermodynamic model for uranium release from hanford site tank residual waste.
A thermodynamic model of U solid-phase solubility and paragenesis was developed for Hanford Site tank residual waste that will remain in place after tank closure. The model was developed using a combination of waste composition data, waste leach test data, and thermodynamic modeling of the leach test data. The testing and analyses were conducted using actual Hanford Site tank residual waste. Positive identification of U phases by X-ray diffraction was generally not possible either because solids in the waste were amorphous or their concentrations were not detectable by XRD for both as-received and leached residual waste. Three leachant solutions were used in the studies: deionized water, CaCO3 saturated solution, and Ca(OH)2 saturated solution. Analysis of calculated saturation indices indicate that NaUO2PO4·xH2O and Na2U2O7(am) are present in the residual wastes initially. Leaching of the residual wastes with deionized water or CaCO3 saturated solution results in preferential dissolution Na2U2O7(am) and formation of schoepite. Leaching of the residual wastes with Ca(OH)2 saturated solution appears to result in transformation of both NaUO2PO4·xH2O and Na2U2O7(am) to CaUO4. Upon the basis of these results, the paragenetic sequence of secondary phases expected to occur as leaching of residual waste progresses for two tank closure scenarios was identified.
Pacific Northwest National Laboratory, Richland, WA 99352, USA. kirk.cantrell@pnl.gov
Kirk J
KJ
Cantrell
William J
WJ
Deutsch
Mike J
MJ
Lindberg
D008962:Models, Theoretical; D011850:Radioactive Waste / Q000032:analysis*; D012995:Solubility; D013816:Thermodynamics; D014501:Uranium / Q000032:analysis*; D014867:Water; D014961:X-Ray Diffraction
D011850:Radioactive Waste; D014867:Water; D014501:Uranium