Estimation of 90Sr in reprocessed uranium oxide samples

S. Ravi; S. Ravi; A. K. Deepa; A. K. Deepa; S. Susheela; S. Susheela; P. V. Achuthan; P. V. Achuthan; S. Anil Kumar; U. Jambunathan

doi:10.1007/s10967-006-0127-4

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Journal of Radioanalytical and Nuclear Chemistry

Volume/Issue:: Volume 268: Issue 1

Estimation of ⁹⁰Sr in reprocessed uranium oxide samples

Authors:

S. Ravi

S. Ravi Fuel Reprocessing Division; Bhabha Atomic Research Centre Trombay, Mumbai 400 085, India

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S. Ravi

S. Ravi Fuel Reprocessing Division; Bhabha Atomic Research Centre Trombay, Mumbai 400 085, India

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A. K. Deepa

A. K. Deepa Radiation Safety Systems Division, Bhabha Atomic Research Centre Trombay, Mumbai 400 085, India

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A. K. Deepa

A. K. Deepa Radiation Safety Systems Division, Bhabha Atomic Research Centre Trombay, Mumbai 400 085, India

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S. Susheela

S. Susheela Radiation Safety Systems Division, Bhabha Atomic Research Centre Trombay, Mumbai 400 085, India

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S. Susheela

S. Susheela Radiation Safety Systems Division, Bhabha Atomic Research Centre Trombay, Mumbai 400 085, India

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P. V. Achuthan

P. V. Achuthan Fuel Reprocessing Division; Bhabha Atomic Research Centre Trombay, Mumbai 400 085, India

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P. V. Achuthan

P. V. Achuthan Fuel Reprocessing Division; Bhabha Atomic Research Centre Trombay, Mumbai 400 085, India

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S. Anil Kumar

S. Anil Kumar Radiation Safety Systems Division, Bhabha Atomic Research Centre Trombay, Mumbai 400 085, India

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, and

U. Jambunathan

U. Jambunathan Fuel Reprocessing Division; Bhabha Atomic Research Centre Trombay, Mumbai 400 085, India

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Pages:: 79–82

Online Publication Date:: 09 Mar 2006

Publication Date:: 17 Apr 2006

Article Category:: Research Article

DOI:: https://doi.org/10.1007/s10967-006-0127-4

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Summary

A method has been developed for the estimation of ⁹⁰Sr in reprocessed uranium oxide samples obtained from the Purex processing of natural uranium spent fuel discharged from the research reactor. The method employs a combination of precipitation and solvent extraction procedure to eliminate other beta-impurities prior to resorting to the estimation of ⁹⁰Sr by beta-counting. ¹⁰⁶Ru was eliminated by volatalizing with perchloric acid, uranium was removed by carrier precipitation with strontium as sulphate. The sulphate precipitate was converted to carbonate and dissolved in nitric acid. ²³⁴Th and ²³⁴Pa were eliminated by synergistic solvent extraction using tri-n-butyl phosphate and thenoyl trifluoroacetone extractant mixture in xylene. An iron scavenging step was included to remove any residual impurities. Finally, strontium is precipitated as SrC₂O₄^. H₂O. The separated ⁹⁰Sr activity was followed to check the equilibrium growth of ⁹⁰Y.

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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)