1AW样品的预处理方法  

Pretreatment of 1AW Sample

作　　者：邓惟勤[1] 谈树苹[1] 陶苗苗[1] 吴继宗[1] 

机构地区：[1]中国原子能科学研究院放射化学研究所,北京102413

出　　处：《核化学与放射化学》2012年第1期21-26,共6页Journal of Nuclear and Radiochemistry

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。In order to separate U, Np, and Pu from other radionuclides in lAW high level liquid waste, an extraction chromatography method using silicabased polymeric materials resin coated with TBP, CMP, or CMPO as stationary phase was studied. After pretreatment with silicabased TBPimpregnated 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 7 radioactivity and β radioactivity can be reduced by 1.3× 103 times and 1.18× 103 times, respectively.

关 键 词：1AW 高放废液 萃取色谱 

分 类 号：TL241[核科学技术—核燃料循环与材料]