This invention discloses a method for
precipitation separation and
ceramic solidification of
divalent strontium and tetravalent
uranium in
radioactive waste liquid, relating to the field of
radioactive waste liquid treatment and disposal. U in high-level
radioactive waste liquid is in the form of hexavalent
uranyl (UO2). 2+ U exists in the form of hydrogenation catalytic reduction, and the present invention uses hydrogenation catalytic reduction to prepare U. 4+ Sr 2+ and U 4+
ionic radius and Ln 3+ Due to the significant differences, CePO4·0.667H2O
cerium phosphate, which has a stronger
nuclide-containing capacity, was selected as the co-
precipitation enrichment agent for Sr. 2+ and U 4+ Separation precipitant. Inexpensive raw materials such as UO2(NO3)2·6H2O, Sr(C2H3O2)2, NH4H2PO4, and Ce(NO3)3·6H2O are selected. By controlling the Sr... 2+ :U 4+
Ion ratio, reaction time, temperature, pH, and preparation of well-developed Sr crystals 2+ / U 4+ The precipitate of
cerium phosphate solid solution with high
solid content is avoided by using spark
plasma solid-state
sintering technology to prevent grain agglomeration and adhesion during high-temperature
dehydration and
crystal transformation of
cerium phosphate. Furthermore, pressure
sintering can promote further growth of nanocrystals and promote U... 4+ and Sr 2+ Homogenization within the
monazite ceramic solidified body enables a one-step preparation of
monazite ceramic solidified body from a lanthanite
solid solution.