Development of a Multi-functional Reprocessing Process based on Ion-exchange Method by using Tertiary Pyridine-type Resin

概要

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A series of separation experiment was performed in order to study a multi-functional spent fuel reprocessing process based on ion-exchange technique. The tertiary pyridine-type anion-exchange resin was used in this experiment and the mixed oxide fuel highly irradiated in the experimental fast reactor “JOYO” was used as a reference spent fuel. As the result, 106Ru+125Sb, 137Cs+155Eu+144Ce, plutonium, americium and curium could be separated from the irradiated fuel by only three steps of ion-exchange. The decontamination factor of 137Cs and trivalent lanthanides (155Eu, 144Ce) in the final americium product exceeded 3.9×104 and 1.0×105, respectively. The decontamination factor for the mutual separation of 243Cm and 241Am was larger than 2.2×103 for the americium product and, moreover, the content of 137Cs, trivalent lanthanides and 243Cm included in 241Am product did not exceed 2 ppm.These results prove that the proposed simplified separation process has a reality as a candidate for future reprocessing process based on the partitioning and transmutation concept.
社団法人日本原子力学会の論文
2006-06-25