The solidification of simulated spent radioactive organic solvent, tri-butyl phosphate/kerosene, was investigated by emulsification-solidification method using sulfoaluminate cement (SAC) and Portland cement (PC). Zeolite, calcium hydroxide and MR-1 type emulsifier were mixed into the cement blends for improving the performance of solidified waste forms (SWF). The properties of SWF were evaluated in terms of mechanical strength, leachability and mineral phase analyses. The hydration products of SWF were characterized by X-ray diffraction (XRD). The experimental results showed that the 28 d compressive strengths of SAC solidified waste forms (SACF) and PC solidified waste forms (PCF) were 14.23 and 19.07 MPa, respectively. Leaching sequence of three radionuclides in two kinds of SWF is Cs+ > Sr2+ > Co2+. Compared with PCF, SACF had better performance in preventing nuclides Co2+ and Cs+ from leaching to the environment. The XRD patterns suggested that simulated spent radioactive organic solvent and emulsifier in SWF did not obviously change the hydration products of the two cements (SAC and PC).
CITATION STYLE
Zhang, W., Li, J., & Wang, J. (2015). Solidification of spent radioactive organic solvent by sulfoaluminate and Portland cements. Journal of Nuclear Science and Technology, 52(11), 1362–1368. https://doi.org/10.1080/00223131.2015.1076747
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