2002
DOI: 10.1081/sei-120004806
|View full text |Cite
|
Sign up to set email alerts
|

EVALUATION OF DI(2-ETHYLHEXYL)ISOBUTYRAMIDE (D2EHIBA) AS A PROCESS EXTRACTANT FOR THE RECOVERY OF233U FROM IRRADIATED Th

Help me understand this report

Search citation statements

Order By: Relevance

Paper Sections

Select...
5

Citation Types

0
19
0

Year Published

2009
2009
2018
2018

Publication Types

Select...
7
1
1

Relationship

1
8

Authors

Journals

citations
Cited by 42 publications
(19 citation statements)
references
References 25 publications
0
19
0
Order By: Relevance
“…1a) has been found to be a promising alternative to TBP for selective recovery of uranium from THOREX feed solution [9][10][11][12]. Our earlier solvent extraction studies on THOREX feed solution (200 g/L Th, 233 U tracer at 4 M HNO 3 ) employing D2EHIBA/n-dodecane revealed that the separation factor (S.F.…”
Section: Introductionmentioning
confidence: 96%
“…1a) has been found to be a promising alternative to TBP for selective recovery of uranium from THOREX feed solution [9][10][11][12]. Our earlier solvent extraction studies on THOREX feed solution (200 g/L Th, 233 U tracer at 4 M HNO 3 ) employing D2EHIBA/n-dodecane revealed that the separation factor (S.F.…”
Section: Introductionmentioning
confidence: 96%
“…Furthermore, N,N-dialkyl aliphatic amides have received considerable attention as extractants for actinides from acidic media. Branched chain di(2-ethylhexyl) isobutyramide (D2EHIBA) has been synthesized and extensively evaluated as an alternate extractant to TBP for the separation of 233 U from irradiated thorium [20][21][22][23][24]. In addition, carrier mediated transport offers several advantages over classical solvent extraction processes viz.…”
Section: Introductionmentioning
confidence: 99%
“…20,21 We have performed systematic studies using several N,N-dialkyl amides as alternatives to TBP in the plutonium uranium reaction (PUREX) as well as in the thorium extraction (THOREX) processes. 18,[22][23][24][25][26][27][28][29][30] The straight-chain amide, N,N-dihexyl octanamide [DHOA, Figure 1(b)], was found to be the most suitable alternative to TBP for selective recovery of U and Pu from three components (U, Pu and Th) of advanced heavy water reactor (AHWR) spent fuels. [24][25][26] In addition, studies were also carried out to optimize the conditions for the recovery of ~ 100 g L −1 Th(IV) from AHWR raffinate solutions.…”
Section: Introductionmentioning
confidence: 99%