Extraction of uranium (VI), plutonium (IV) and some fission products by tri-iso-amyl phosphate

J. Shukla; M. Gautam; C. Kedari; S. Hasan; D. Rupainwar

doi:10.1007/bf02040266

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Journal of Radioanalytical and Nuclear Chemistry

Volume/Issue:: Volume 219: Issue 1

Extraction of uranium (VI), plutonium (IV) and some fission products by tri-iso-amyl phosphate

Authors:

J. Shukla

J. Shukla Bhabha Atomic Research Centre Radiochemistry Division Tombay 40085 Mumbai India

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M. Gautam

M. Gautam Bhabha Atomic Research Centre Radiochemistry Division Tombay 40085 Mumbai India

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C. Kedari

C. Kedari Bhabha Atomic Research Centre Fuel Reprocessing Division Trombay 400085 Mumbai India

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S. Hasan

S. Hasan B. H. U. Department of Applied Chemistry 221005 Varanasi India

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, and

D. Rupainwar

D. Rupainwar B. H. U. Department of Applied Chemistry 221005 Varanasi India

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Pages:: 61–67

Online Publication Date:: 14 Aug 2005

Publication Date:: 17 May 1997

Article Category:: Research Article

DOI:: https://doi.org/10.1007/bf02040266

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Abstract

The extractive properties of tri-isoamyl-phosphate (TAP), an indigenously prepared extractant, and the loading capacity of extraction solvent containing TAP for U(VI) and Pu(IV) ions in nitric solution have been investigated. The dependence of the distribution ratio on the concentration of nitric acid showed that TAP has an ability to extract these actinides, while the fission product contaminants are poorly extracted. The distribution data revealed a quantitative extraction of both U(VI) and Pu(IV) from moderate nitric acidities in the range 2–7 mol · dm^–3. Slope analysis proved predominant formation of the disolvated organic phase complex of the type UO₂(NO₃). 2TAP and Pu(NO₃)₄·2TAP with U(VI) and PU(IV), respectively. On the contrary, the extraction of fission product contaminants such as¹⁴⁴Ce,¹³⁷Cs,⁹Nb.,¹⁴⁷Pr,¹⁰⁶Ru,⁹⁵Zr was almost negligible even at very high nitric acid concentrations in the aqueous phase indicating its potential application in actinide partitioning. The recovery of TAP from the loaded actinides could be easily accomplished by using a dilute sodium carbonate solution or acidified distiled water (0.01 mol · dm^–3 HNO₃) as the strippant for U(VI) and using uranous nitrate or ferrous sulphamate as that for Pu(IV). Radiation stability of TAP was adequate for most of the process applications.

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Journal of Radioanalytical and Nuclear Chemistry

Print ISSN:: 0236-5731

Online ISSN:: 1588-2780

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Journal of Radionalytical and Nuclear Chemistry
Language	English
Size	A4
Year of Foundation	1968
Volumes per Year	1
Issues per Year	12
Founder	Akadémiai Kiadó
Founder's Address	H-1117 Budapest, Hungary 1516 Budapest, PO Box 245.
Publisher	Akadémiai Kiadó Springer Nature Switzerland AG
Publisher's Address	H-1117 Budapest, Hungary 1516 Budapest, PO Box 245. CH-6330 Cham, Switzerland Gewerbestrasse 11.
Responsible Publisher	Chief Executive Officer, Akadémiai Kiadó
ISSN	0236-5731 (Print)
ISSN	1588-2780 (Online)