Rapid quantitation of uranium from mixed fission product samples
Chemical similarities between uranium(VI) and molybdenum(VI) create challenges for separation and quantitation of uranium isotopes from a mixed fission product sample. The purpose of this work was to demonstrate an improved chemical separation for the detection of 235 U using gamma spectroscopy. The...
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Published in | Journal of radioanalytical and nuclear chemistry Vol. 307; no. 3; pp. 1737 - 1742 |
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Main Authors | , , , |
Format | Journal Article |
Language | English |
Published |
Dordrecht
Springer Netherlands
01.03.2016
Springer |
Subjects | |
Online Access | Get full text |
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Summary: | Chemical similarities between uranium(VI) and molybdenum(VI) create challenges for separation and quantitation of uranium isotopes from a mixed fission product sample. The purpose of this work was to demonstrate an improved chemical separation for the detection of
235
U using gamma spectroscopy. The optimized method, which included extraction and anion exchange chromatography, demonstrated a consistent chemical yield of 74 ± 3 % for uranium. Using a fresh fission product sample the minimum detectable activity for
235
U,
237
U, and
238
U was reduced by a factor of two. The chemical isolation of uranium was achieved in less than 4 h, with a separation factor of 1.41 × 10
5
from molybdenum. |
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Bibliography: | PNNL-SA-109446 USDOE AC05-76RL01830 |
ISSN: | 0236-5731 1588-2780 |
DOI: | 10.1007/s10967-015-4617-0 |