Separation and quantification of chemically diverse analytes in neutron irradiated fissile materials

M. Douglas; J. Friese; L. Greenwood; O. Farmer; M. Thomas; T. Maiti; E. Finn; S. Garofoli; P. Gassman; M. Huff; S. Schulte; S. Smith; K. Thomas; P. Bachelor

doi:10.1007/s10967-009-0263-8

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Journal of Radioanalytical and Nuclear Chemistry

Volume/Issue:: Volume 282: Issue 1

Separation and quantification of chemically diverse analytes in neutron irradiated fissile materials

Authors:

M. Douglas

M. Douglas Pacific Northwest National Laboratory 902 Battelle Blvd P.O. Box 999 Richland WA 99352 USA

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J. Friese

J. Friese Pacific Northwest National Laboratory 902 Battelle Blvd P.O. Box 999 Richland WA 99352 USA

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L. Greenwood

L. Greenwood Pacific Northwest National Laboratory 902 Battelle Blvd P.O. Box 999 Richland WA 99352 USA

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O. Farmer

O. Farmer Pacific Northwest National Laboratory 902 Battelle Blvd P.O. Box 999 Richland WA 99352 USA

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M. Thomas

M. Thomas Pacific Northwest National Laboratory 902 Battelle Blvd P.O. Box 999 Richland WA 99352 USA

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T. Maiti

T. Maiti Pacific Northwest National Laboratory 902 Battelle Blvd P.O. Box 999 Richland WA 99352 USA

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E. Finn

E. Finn Pacific Northwest National Laboratory 902 Battelle Blvd P.O. Box 999 Richland WA 99352 USA

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S. Garofoli

S. Garofoli Pacific Northwest National Laboratory 902 Battelle Blvd P.O. Box 999 Richland WA 99352 USA

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P. Gassman

P. Gassman Pacific Northwest National Laboratory 902 Battelle Blvd P.O. Box 999 Richland WA 99352 USA

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M. Huff

M. Huff Pacific Northwest National Laboratory 902 Battelle Blvd P.O. Box 999 Richland WA 99352 USA

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S. Schulte

S. Schulte Pacific Northwest National Laboratory 902 Battelle Blvd P.O. Box 999 Richland WA 99352 USA

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S. Smith

S. Smith Pacific Northwest National Laboratory 902 Battelle Blvd P.O. Box 999 Richland WA 99352 USA

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K. Thomas

K. Thomas Pacific Northwest National Laboratory 902 Battelle Blvd P.O. Box 999 Richland WA 99352 USA

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P. Bachelor

P. Bachelor Pacific Northwest National Laboratory 902 Battelle Blvd P.O. Box 999 Richland WA 99352 USA

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Pages:: 63–68

Online Publication Date:: 25 Jul 2009

Publication Date:: 01 Oct 2009

Article Category:: Research Article

DOI:: https://doi.org/10.1007/s10967-009-0263-8

Keywords:: Gamma spectrometry; Chemical separations; Fission products

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Abstract

Quantitative measurement of fission and activation products resulting from neutron irradiation of fissile materials is of interest for applications in environmental monitoring, nuclear waste management, and national security. Based on established separation processes involving co-precipitation, solvent extraction, and ion-exchange and extraction chromatography, we have optimized a proposed sequence of separation steps to allow for the timely quantification of analytes of interest. We have recently evaluated this scheme using an irradiated sample to examine the adequacy of separations for measurement of desired analytes by gamma spectrometry. Here we present the radiochemical separations utilized and the yields and purity obtained.

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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)