首页> 外文期刊>Radiochimica Acta: International Journal for Chemical Aspects of Nuclear Science and Technology >Study on the technology of U-Pu Co-stripping process for reprocessing spent fuel of fast reactor
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Study on the technology of U-Pu Co-stripping process for reprocessing spent fuel of fast reactor

机译:U-Pu共提工艺对快堆乏燃料的后处理技术研究

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摘要

To develop an aqueous reprocessing process for spent fuel of fast reactor, a counter current experiment (U-Pu co-stripping) based on a simplified PUREX process was carried out with 30% TBP/Kerosene solution containing U, Pu and HNO3. The experiment was done in a 16-stage miniature centrifugal contactor. The stripping percentage of U was 99.99%, Pu 99.94%. U stripping mainly took place in X1-feeding stage (11.00 mol/L HNO3 feeding stage) to the 16th one, while Pu stripping mainly took place in the first stage to the X1-feeding stage. And a simple method was presented to calculate c(U/X1-feeding stage), (Org) when the X1-feeding stage number is more than 7 and the stripping percentage of U from the X1-feeding stage is more than 99.9% through the rear stages' stripping. The calculation results by this method were validated by Computer Simulation when only changing U concentrations in feed solution from 40.0 g/L to 90.0 g/L or only changing the X1-feeding stage from the 7th stage to the 11th one. Finally the optimized technology was given.
机译:为了发展快堆乏燃料的水后处理工艺,在简化的PUREX工艺基础上,采用含U,Pu和HNO3的30%TBP /煤油溶液进行了逆流实验(U-Pu共汽提)。实验是在16级微型离心接触器中完成的。 U的溶出率为99.99%,Pu为99.94%。 U汽提主要发生在X1进料阶段(11.00 mol / L HNO3进料阶段)至第16阶段,而Pu汽提主要发生在第一阶段至X1进料阶段。提出了一种简单的计算方法,当X1喂入阶段数大于7,且从X1喂入阶段到U的溶出率大于99.9%时,计算c(U / X1喂入阶段)(Org)。后台的脱衣舞。当仅将进料溶液中的U浓度从40.0 g / L更改为90.0 g / L或仅将X1进料阶段从第7阶段更改为第11阶段时,通过计算机仿真验证了此方法的计算结果。最后给出了优化技术。

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