Development of a Multi-functional Reprocessing Process based on Ion-exchange Method by using Tertiary Pyridine-type Resin
Development of a Multi-functional Reprocessing Process based on Ion-exchange Method by using Tertiary Pyridine-type Resin
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DOI：
10.1080/18811248.2006.9711148
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发表时间：
2006-06
影响因子：
1.2
通讯作者：
S. Koyama;M. Ozawa;Tatsuya Suzuki;Y. Fujii
中科院分区：
文献类型：
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作者：
S. Koyama;M. Ozawa;Tatsuya Suzuki;Y. Fujii
为研究基于离子交换技术的多功能乏燃料后处理工艺，进行了一系列分离实验。本实验采用叔吡啶型阴离子交换树脂，实验快堆“JOYO”中高辐照的混合氧化物燃料作为参考乏燃料。结果表明，106Ru+125Sb、137Cs+155Eu+144Ce、钚、镅和curium仅通过三步离子交换就能从辐照燃料中分离出来。最终镅产品中137Cs和三价镧系元素（155Eu, 144Ce）的去污系数分别超过3.9x104和1.0x105。镅产物243Cm和241Am相互分离的去污因子大于2.2 × 103, 241Am产物中137Cs、三价镧系元素和243Cm的含量不超过2 ppm。这些结果证明了所提出的简化分离过程作为基于分划和嬗变概念的未来再处理过程的候选是现实的。
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 3.9x104 and 1.0x105, respectively. The decontamination factor for the mutual separation of 243Cm and 241Am was larger than 2.2x103 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.