U, Pu Co-Recovery Process Ⅰ. Cascade Experiments
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Graphical Abstract
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Abstract
FR fuel reprocessing differs from thermal reactor fuel reprocessing in many respects, such as high Pu content, and requires more extraction cycles to give a sufficiently decontamination factor. To elucidate the behavior of uranium and plutonium in extraction/co-strip process, several cascade experiments were carried out with a simulative solution containing U and Pu. The experiment results show that the yeild of U and Pu in 1A are 99.995% and 99.996%, respectively, the yeild of U and Pu in 1B are 99.936% and 99.996%, respectively. And through the use of dual strip, the possibility of Pu polymerization is reduced by maintaining sufficient acid concentration commensurate with Pu concentration.
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