Investigation of total separations using solvent extraction of actinides and fission products

Sasaki, Yuji

We develop all-inclusive partitioning method for actinides and fission products in high-level radioactive waste. This process is based on the sequential solvent extraction. In order to recover Cs and Sr for the management by interim storage, crown ether compounds are employed. For the removal of Pd and Mo due to production of a stable vitrified object, methylimino-dioctylacetamide (MIDOA) is taken as an extractant. DGA can extract both actinides and trivalent lanthanides. In order to separate each other, dietylenetriamine-triacetic-diamide (DTBA) for the stripping reagent of MA. For the mutual separation of Am/Cm, DGA and DOODA extraction system is taken into consideration.

Language	:	Japanese
Journal	:	Bunri Gijutsu
Volume	:	52
Number	:	2
Pages	:	p.103 - 107
Publication Year/Month	:	2022/03
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Keywords	:	Partitioning Process; DGA; DOODA; MIDOA; DTBA; Extraction; Fission Product; Actinide; Separation
Research Facility	:	第4研究棟
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Article of JAEA R&D Review	:
Cooperating Institute	:	東京工業大学

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Registration No. : AA20200739
JAEA Abstracts No. : 52000196
Paper Submission No. : 27620

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