Separation of Trivalent Actinides from High-Active Waste

被引:8
作者
Antony, M. P. [1 ]
Venkatesan, K. A. [1 ]
Suneesh, A. S. [1 ]
Nagarajan, K. [1 ]
Rao, P. R. Vasudeva [1 ]
机构
[1] Indira Gandhi Ctr Atom Res, Div Fuel Chem, Kalpakkam 603102, Tamil Nadu, India
来源
ATALANTE 2012 INTERNATIONAL CONFERENCE ON NUCLEAR CHEMISTRY FOR SUSTAINABLE FUEL CYCLES | 2012年 / 7卷
关键词
High active waste; Trivalent actinide partitioning; Lanthanide-actinide separation; glycolamic acid; carbamoylmethylphosphine oxide; solvent extraction; LIGANDS;
D O I
10.1016/j.proche.2012.10.023
中图分类号
O65 [分析化学];
学科分类号
070302 ; 081704 ;
摘要
A typical high-active waste (HAW) arising from reprocessing of (U0.3Pu0.7) C fuel irradiated to the burn-up of 155 GWd/Te in a fast breeder test reactor (FBTR) was characterized. Partitioning of trivalent actinides from HAW was demonstrated using a solvent, 0.2 M n-octyl(phenyl)-N, N-diisobutylcarbamoylmethylphosphine oxide (CMPO) - 1.2 M tri-n-butylphosphate (TBP) in n-dodecane (n-DD), in a mixer settler. The results established quantitative separation of trivalents (Am(III) + Ln(III)) from HAW and recovery (> 99 %) using a citric acid-nitric acid formulation. The mutual separation of lanthanides and actinides from the stripped product was studied by using bis(2-ethylhexyl) diglycolamic acid (HDEHDGA), synthesized in our laboratory. (C) 2012 Elsevier B.V. .. Selection and/ or peer-review under responsibility of the Chairman of the ATALANTE 2012 Program Committee
引用
收藏
页码:130 / 138
页数:9
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