Pretreatment of 1AW Sample

In order to separate U, Np, and Pu from other radionuclides in 1AW high level liquid waste, an extraction chromatography method using silica-based polymeric materials resin coated with TBP, CMP, or CMPO as stationary phase was studied. After pretreatment with silica-based TBP-impregnated resin column the recovery of U is about 100%, the total recovery of Np and Pu can reach 99.6%. According to the decontamination factor of fission products, the total γ radioactivity and β radioactivity can be reduced by 1.3×10³ times and 1.18×10³ times, respectively.