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Our Portfolio: Monitoring Projects
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Measurement of Radionuclides Using Ion
Chromatography and Flow-Cell Scintillation Counting
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Information Resources
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Tech ID: 310 Project Overview
Problem: Radiological characterization and monitoring is an important
component of environmental management activities throughout the Department
of Energy (DOE) complex. Radionuclides which cannot easily be detected by
gamma-ray spectroscopy, such as pure beta emitters and transuranics, pose
special problems because their quantification generally requires labor-intensive
radiochemical separations procedures that are time-consuming and not practical
for field applications.
Solution: A technology that can measure transuranics and pure beta emitters
relatively quickly and has the potential of being field-deployable. This
technology combines high-performance liquid chromatography and on-line
scintillation counting with alpha/beta pulse shape discrimination. The ability
to measure pure beta emitters such as 90Sr, 99Tc, and
63Ni and actinides/ transuranics such as 232Th,
233U, 237Np, 239Pu, 241Am, and
244Cm has been demonstrated. Up to this point, work has been
primarily limited to aqueous samples of relatively high purity and to
radionuclide concentrations that are representative of many waste applications,
but are higher than those typically encountered in environmental cleanup
applications. For the technique to be useful in applications involving
complex matrices such as sludge and soil, research is needed in sample
preparation and processing to remove chemical and radiological interferences.
For the technique to be useful at typical environmental levels, research is
needed to lower detection limits. This project addresses these research needs.
Benefits:
- Analysis of alpha emitters and pure beta emitters in environmental
samples or waste samples
- Radionuclide-specific measurements in a relatively short period of
time (< 4 hours)
- Elemental and some isotopic selectivity
- On-line minimum detectable concentrations on the order of 0.4 to
4 kBq/m3 (10 to 100 pCi/g)
- Potentially field deployable
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Technology Description
The project has three main components: one to lower the radiation detection
limits, another to identify chemical and radiological interferences, and the
last to determine sample processing protocols. The components are focused on
sample types and radionuclides that are relevant in DOE applications. Although
efforts will be initially directed toward development of the technique as a
screening tool, it has the potential to be able to measure many radioactive
elements at regulatory levels.
The research effort is centered around the analysis technique, which combines
high-performance liquid chromatography and on-line scintillation counting.
Radionuclides in ionic form in an aqueous solution are concentrated on an
ion-exchange column and subsequently removed to a separation column with
chemical elements. Through the selection and sequencing of the elements,
chromatographic separation of the constituents is achieved. A chromatogram
of radioactive constituents is then produced by an on-line scintillation
counter. For very low-level applications, fractions containing selected
radioelements can be collected and counted off-line.
The basic instrumentation for this analysis technique is available under the
trade name ANABET (ANalysis of Alpha, Beta, and Electron capture Technology)
through Bradtec-GB, Inc. The effort to lower detection limits will focus on
background reduction. This will be accomplished through a combination of
coincidence counting, anti-coincidence shielding, and pulse shape
discrimination to distinguish between alpha pulses and beta/gamma pulses.
Sample preparation procedures and processing will be developed based on
quantified chemical and radiological interferences. A simple matrix
(groundwater) and two complex matrices (a soil and a waste-tank supernatant).
For each sample, the potential chemical and radiological interferences were
identified and the concentrations at which they interfere with either the
chromatographic separation or with radiation detection were determined.
These concentration limits are the target criteria for the development of
sample-preparation techniques.
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