1AW样品的预处理方法

    Pretreatment of 1AW Sample

    • 摘要: 研究了以包覆有机物的二氧化硅为支持体,TBP、CMP和CMPO等萃取剂为固定相,通过萃取色谱法共萃取样品中待测的铀、镎、钚,分离绝大部分放射性裂片。结果表明:采用硅基TBP溶剂浸渍树脂进行预处理后,铀回收率接近100%,镎和钚总的回收率为99.6%;通过裂变核素去污因子可以估算,样品总γ放射性可以降低1.3×103倍,总β放射性可以降低1.18×103倍。

       

      Abstract: 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.

       

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