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机构地区:[1]中国原子能科学研究院放射化学研究所
出 处:《原子能科学技术》1995年第3期193-200,共8页Atomic Energy Science and Technology
摘 要:用逆流萃取串级实验方法研究动力堆乏燃料后处理流程中(包括lA、lB、2A、2B、lC、2D槽)Tc的走向及其影响因素。采用模拟料液的串级实验结果表明,lA槽中影响Tc的回收率的主要因素是料液中的c(HNO_3)及c(Zr(NO_3)_4)。按推荐工艺流程条件,lA槽:DF_(Tc)=6.5,c(HNO_3)=2.0mol/l;DF_(Te)=7.8,c(HNO_3)=3.0mol/l;lB槽:DF_(TC)≈560—770;2A槽:DF_(TC)=370;2B槽:DF_(TC)=1.2;lC槽:DF_(TC)=1.1;2D槽:DF_(TC)=30.3。The subject of the work is an investigation of the routes followed by technetium through thePurex process including 1A,1B,1C,2A,2B,2D,contactors by using cascade counter current ex-traction technique.The influence of nitric acid,zirconium nitrate and plutonium nitrate in lAFfeed on the recovery of technetium are studied emphatically for lA contactor. Among those,theconcentration of nitric acid and zirconium nitrate in lAF feed influences the recovery of tech-netium significantly,The results obtained from cascade experiments show that the technetium de-contamination factor(DF_(Tc))is 6.5,1.1,30.3,370 and 1.2 for the 1A,1B,1C,2D,2A and 2Bcontactor,respectively. The gross DF_(Tc) is 1.67×103 for uranium and plutonium,respectively.Theprobable extration behaviour of technetium in each process step for the Purex process are also discussed.
分 类 号:TL241.14[核科学技术—核燃料循环与材料]
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