Rapid separation and purification of uranium and plutonium from dilute-matrix samples

Christopher R. Armstrong; Brian W. Ticknor; Gregory Hall; James R. Cadieux

doi:10.1007/s10967-014-3070-9

Rapid separation and purification of uranium and plutonium from dilute-matrix samples

Christopher R. Armstrong, Brian W. Ticknor, Gregory Hall, James R. Cadieux

Research output: Contribution to journal › Article › peer-review

8 Scopus citations

Abstract

This work describes a streamlined approach to the separation and purification of trace uranium and plutonium in environmental swipe samples that contain a small amount of collected bulk material. We describe key modifications to conventional techniques that result in a relatively rapid, safe, cost-effective, and efficient U and Pu separation process. Simulated samples were produced by loading appropriate ²³⁵U, ²³⁸U, and ²⁴⁰Pu onto high purity cotton swipes. Uranium concentration and isotopic composition were measured by multi-collector inductively coupled mass spectrometry. Corresponding plutonium measurements were conducted with a three stage thermal ionization mass spectrometer. Quantitative U and Pu recoveries were observed with this method.

Original language	English
Pages (from-to)	859-866
Number of pages	8
Journal	Journal of Radioanalytical and Nuclear Chemistry
Volume	300
Issue number	2
DOIs	https://doi.org/10.1007/s10967-014-3070-9
State	Published - May 2014
Externally published	Yes

Funding

Acknowledgments This work is supported by the Next Generation Safeguards Initiative, Office of Nonproliferation and International Security, at the Department of Energy’s National Nuclear Security Administration. The authors thank Myra Pettis for her assistance with the column work.

Funders	Funder number
Department of Energy’s National Nuclear Security Administration
Next Generation Safeguards Initiative
Office of Nonproliferation and International Security

Keywords

Environmental samples
Radiochemical separations
Safeguards
Trace plutonium
Trace uranium

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10.1007/s10967-014-3070-9

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abstract = "This work describes a streamlined approach to the separation and purification of trace uranium and plutonium in environmental swipe samples that contain a small amount of collected bulk material. We describe key modifications to conventional techniques that result in a relatively rapid, safe, cost-effective, and efficient U and Pu separation process. Simulated samples were produced by loading appropriate 235U, 238U, and 240Pu onto high purity cotton swipes. Uranium concentration and isotopic composition were measured by multi-collector inductively coupled mass spectrometry. Corresponding plutonium measurements were conducted with a three stage thermal ionization mass spectrometer. Quantitative U and Pu recoveries were observed with this method.",

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AU - Hall, Gregory

AU - Cadieux, James R.

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AB - This work describes a streamlined approach to the separation and purification of trace uranium and plutonium in environmental swipe samples that contain a small amount of collected bulk material. We describe key modifications to conventional techniques that result in a relatively rapid, safe, cost-effective, and efficient U and Pu separation process. Simulated samples were produced by loading appropriate 235U, 238U, and 240Pu onto high purity cotton swipes. Uranium concentration and isotopic composition were measured by multi-collector inductively coupled mass spectrometry. Corresponding plutonium measurements were conducted with a three stage thermal ionization mass spectrometer. Quantitative U and Pu recoveries were observed with this method.

KW - Environmental samples

KW - Radiochemical separations

KW - Safeguards

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Rapid separation and purification of uranium and plutonium from dilute-matrix samples

Abstract

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Keywords

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