high sensitivity analysis of plutonium isotopes in environmental samples using accelerator mass...
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TECHNICAL NOTE www.rsc.org/jaas | Journal of Analytical Atomic Spectrometry
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High sensitivity analysis of plutonium isotopes in environmental samples usingaccelerator mass spectrometry (AMS)
D. P. Child,* M. A. C. Hotchkis and M. L. Williams
Received 12th October 2007, Accepted 25th January 2008
First published as an Advance Article on the web 28th February 2008
DOI: 10.1039/b715788f
This article presents a methodology for the determination of the concentration and isotopic ratio of
plutonium occurring at femtogram levels in environmental matrices such as soils and sediments by
accelerator mass spectrometry (AMS). Results on analyses of a number of reference materials
(IAEA-375, IAEA-135, IAEA-300, IAEA-327, NIST 4350, NIST 4353b) are presented as validation of
the method in reproducibly measuring the plutonium isotopic ratio 240Pu : 239Pu in a variety of
environmental sample matrices.
Introduction
Mass spectrometry techniques such as sector field inductively
coupled plasma mass spectrometry (SF-ICP-MS) and thermal
ionisation mass spectrometry (TIMS) have enabled the sensi-
tivity of measurements of long lived actinides to be improved
at least three orders of magnitude compared to alpha count-
ing1–3 and in addition allow measurement of 239Pu : 240Pu : 241Pu
concentration ratios. The application of accelerator mass
spectrometry (AMS) to the analysis of actinides offers potential
further improvements to sensitivity through its ability to reduce
isobaric molecular interferences and spectral interferences
caused by abundant adjacent mass peaks,4–6 particularly in the
case of samples with complex matrices.
In the measurement of nuclear safeguards environmental
samples it has been necessary to conduct simultaneous extraction
and measurement of plutonium, uranium and iodine isotopes on
the one sample, necessitating a specialised sample preparation
methodology. Iodine is required because the fission product129I can be a useful signature of nuclear activities.7 In order to
validate this method and to ensure that disproportionation
between native and tracer plutonium was not occurring,
a number of standard reference materials with published
plutonium concentrations were prepared and analysed.
Analytical method
Materials used
The laboratory used for sample preparation is ventilated with
HEPA-filtered air at positive pressure. All chemical reagents
used are of high purity ARISTAR grade or equivalent unless
otherwise noted. All water used during sample preparation was
deinionised water (18.2 MU) from a Milli-Q water purification
system. All equipment is washed successively with an acid
wash (HNO3 or H3PO4), a neutralising agent plus deconta-
minating detergent (Decon 90�), and then rinsed with deionised
water.
Australian Nuclear Science and Technology Organisation (ANSTO),Private Mailbag 1, Menai, NSW 2234, Australia. E-mail: [email protected]; Fax: +61 2 9717 9265; Tel: +61 2 9717 3851
This journal is ª The Royal Society of Chemistry 2008
For AMS determination of plutonium concentration and
isotopic ratios (240Pu : 239Pu) the technique of isotope dilution
is used. NIST SRM 4334 G 242Pu is added to all samples as the
reference isotope. Additions of 1 pg 242Pu per sample were used
in the present work. An in-house standardised 238Pu tracer was
used as a yield monitor in tests of the extraction procedures
described below. The 238Pu was analysed by alpha spectrometry.
Matrix destruction
Prior to processing, soil and sediment samples are checked for
homogeneity, and if necessary coned and quartered to ensure
homogenous representation of the sample. A combustion
method was chosen to enable collection of volatile iodine from
the bulk sample matrix prior to liberation of the actinides. The
method shown in Fig. 1 was then used for the separation and
extraction of plutonium and uranium from sample matrices.
The combination of high temperature combustion with only
partial sample dissolution (acid leaching) poses a risk of
incomplete dissolution of native plutonium oxide and therefore
incomplete mixing of tracer plutonium (242Pu) and native
plutonium (239Pu and 240Pu).8 Plutonium of safeguards interest
is expected to be present as very fine micron sized oxide particles
condensed from the exhaust in reprocessing facilities or adsorbed
to the surface of aerosol particles, and therefore should be
susceptible to aqua regia leaching. This partial dissolution
method was therefore chosen to utilise the reduction in potential
ingress of matrix elements into the sample (particularly silicon
and uranium), reduction in chemical manipulation and therefore
lower blanks, and a simplified, more rapid sample preparation
process for plutonium analysis. To minimise the potential for
disproportionation between fallout plutonium and tracer
plutonium the temperature of combustion was kept below
900 �C and the duration of the high temperature combustion
was kept to �30 min.9
Plutonium purification
Environmental samples are expected to contain uranium at
much higher concentrations than plutonium. As the presence
of uranium may interfere with the detection of plutonium
J. Anal. At. Spectrom., 2008, 23, 765–768 | 765
Fig. 1 Schematic of sample processing.
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isotopes in mass spectrometry analysis by way of peak overlap,
it is necessary to separate plutonium from uranium. This is
achieved in our facility by ion exchange chromatography as
detailed in Fig. 1. The method developed at ANSTO is based
upon those given in ref. 10 and 11.
All samples are processed by the method described in Fig. 1
with the following exceptions. If samples contain large quanitites
of aluminium, the coprecipitate formed after digestion is washed
with 6 M NaOH to dissolve bulk aluminium before addition of
the samples to ion exchange columns. If samples are suspected
of having high phosphate content, the solutions are made up
to 1 M Al(NO3)3 to reduce the possibility of phosphate
complexed actinides prematurely eluting from the columns.
For introduction into the AMS ion source, the element of
interest must be purified and concentrated into a small pellet
of material of no more than a few milligrams. For measurement
of small quantities of actinides (<1 mg), the most suitable form
for AMS has been found to be as a co-precipitate with
�1.5 mg of iron oxide.12,13 Therefore approximately 1 mg of
iron(III) nitrate (Choice Analytical, 1000 ppm ferric nitrate) is
added and the Fe/Pu co-precipitated with NH4OH. This precipi-
tate is collected, washed with deionised water, dried and calcined
for loading into AMS sample holders.
Yields on samples processed using the methodology outlined
in this paper varied between 60–80% (determined by alpha
spectroscopy measurements of reference samples spiked with238Pu) and were deemed acceptable for the sensitivity require-
ments of this technique. Higher and more reproducible yields
are desirable for the future however, so further investigation
will be conducted to determine where the remainder of the
plutonium is being lost.
766 | J. Anal. At. Spectrom., 2008, 23, 765–768
AMS instrumentation and analysis method
Samples are measured by AMS on the ANTARES FN tandem
accelerator at ANSTO, using the ‘actinides beamline’ previously
described for analysis of 236U/238U isotopic ratios.13 For the
measurement of Pu isotopes on this system, ions of PuO� are
injected, a terminal voltage of 4 MV is used, and ions of Pu5+
are extracted giving a beam energy of 23.75 MeV. However,
the method for obtaining isotopic ratios of Pu differs to that
previously published.
With AMS, the ion beam is mass-analysed twice using sector-
field magnets: first as negative ions before acceleration, and then
as positive atomic ions after acceleration. To obtain isotopic
ratios for uranium on ANTARES, the rare isotope 236U5+ is
counted in a gas ionisation detector and the 238U5+ is measured
in an off-axis position using either a Faraday cup or a secondary
electron multiplier in current-amplifying mode. Thus the
uranium isotopes are measured at separate points on the focal
plane of the analysing magnet without changing magnetic field
or terminal voltage. The ions injected into the accelerator are
rapidly switched between 236UO� and 238UO� by modulating
the beam energy in the negative ion analyser (‘fast-cycling’). In
contrast, to measure Pu isotopic ratios, it is necessary to count
each Pu isotope sequentially in the same gas ionisation detector,
as all Pu isotopes are at low levels. This requires changing the
magnetic field of the positive ion analyser between each measure-
ment for the ANTARES instrument. This process is relatively
slow (‘slow-cycling’) as the magnet was not designed for rapid
switching. The configuration of the ANTARES system necessi-
tates this mode of operation, in contrast to the configuration
described in ref. 12, where isotopes can be switched by
modulating the terminal voltage.
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Test results and discussion
Determination of ability to discriminate plutonium in the
presence of uranium
A group of samples containing from 0 to 200 ng total uranium as
natural uranium (NIST 4321c), were analysed. A fixed amount
of 242Pu tracer was added to each sample. This experiment
allowed the impact of uranium concentration on plutonium
sensitivity to be determined; in particular 239Pu, which is the
isotope most likely to be affected by interferences from uranium.
The samples were analysed to derive the apparent amount of239Pu present in each sample. The results are shown in Fig. 2.
Fig. 2 Interference of uranium with mass 239 sensitivity. The dotted line
represents a simulated result assuming a 239 : 238 abundance sensitivity
of 9 � 10 �7 and an ‘offset’ of 3.5 fg (see text).
Table 1 Plutonium content of a collection of reference materials comprising rin this work are based upon single measurements and errors represent 1s dreported in the cited publication
Referencematerial
Samplesize/g
239Pu activity/Bq kg�1
240Pu activityBq kg�1
IAEA-135 0.48–0.64a 126 � 19 86 � 17Irish Sea sediment
127 � 8 96 � 6
IAEA-375 2.06 0.113 � 0.010 0.124 � 0.02Russian soil 0.49 0.108 � 0.025 0.119 � 0.04
IAEA-300 1.08 2.41 � 0.09 1.51 � 0.11Baltic Sea sediment
IAEA-327 1.55 0.282 � 0.020 0.205 � 0.03Soil
NIST SRM-4353 0.93 4.74 � 0.24 1.14 � 0.14Rocky Flats soil
NIST SRM-4350b 1.47 0.364 � 0.024 0.117 � 0.02River sediment 1.41 0.342 � 0.022 0.152 � 0.02
a This range represents an average of results from 3 samples (11 measuremenaverages calculated from 2 reported results. Errors include only counting starepresents a mean of 3 measurements.
This journal is ª The Royal Society of Chemistry 2008
The data can be interpreted in terms of two components: (i) an
abundance sensitivity for 239Pu : 238U of 9 � 10 � 7 and (ii) an
‘offset’ of 3.5 fg. The abundance sensitivity is limited by the
interference of 238U, which may be caused by a combination of
the finite resolving power of the magnetic analysers, the injection
of 238U as molecular ions of same mass as 239Pu16O (e.g. 238U16OH
or 238U17O), and the occurrence of scattering and charge
changing collisions in the beam tubes. The ‘offset’ can be
explained as being due to a fixed level of contamination in the
samples, of either 238U at a level of around 3.9 ng, or 239Pu at
a level of around 3.5 fg. The contamination could be from the
reagents and materials used in the preparation of samples for
this test, or result from ion source memory effects from previous
analysis of uranium-bearing samples.
Analysis of standard reference materials
A number of reference materials certified for plutonium content
were analysed. These were prepared and analysed using the
method described above. Results of the analyses as specific
activities of 239Pu and 240Pu as well as 239 + 240Pu activity and
240 : 239 atom ratios are given in Table 1 where they are
compared to published values. Some of the ANTARES AMS
results in this table were published previously in ref. 14 and 15.
In most cases the measured activities are consistent with
previously reported values for the reference materials. In addi-
tion there was good agreement between replicate analyses of
IAEA-135, demonstrating good internal reproducibility. A plot
of replicate analyses of this reference material is shown in Fig. 3.
adionuclide bearing environmental materials. All measurements reportedeviations unless otherwise noted. Where no error is cited, no error was
/ 239 + 240Pu activity/Bq kg�1
240Pu : 239Puatom ratio Reference
212 � 25 0.186 � 0.022 This workrange 205–225b Certificate
223 � 5 0.207 � 0.006 Lee et al.18
245 � 1.4c 0.212 � 0.004 c McAninch et al.5
0 0.237 � 0.022 0.296 � 0.054 This work9 0.226 � 0.055 0.299 � 0.140 This work
range 0.26–0.34b Certificate0.240 � 0.040c McAninch et al.5
3.92 � 0.14 0.170 � 0.014 This workrange 3.09–3.90 b Certificate
3.70 � 0.08d 0.1779d Sturup et al.19
0.19 � 0.02e Kim et al.2
0 0.487 � 0.036 0.198 � 0.032 This workrange 0.56–0.60b Certificate
5.88 � 0.28 0.065 � 0.009 This work8.03 � 0.60 0.055 Certificate
4 0.481 � 0.034 0.087 � 0.019 This work6 0.494 � 0.034 0.121 � 0.022 This work
0.508 � 0.029 0.105 Certificate
ts) combined. b This range represents a 95% CL. c These values representtistics. d These values represent means of 3 measurements. e This value
J. Anal. At. Spectrom., 2008, 23, 765–768 | 767
Fig. 3 Replicate analysis of IAEA SRM 135.
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The small size of samples that were used in this work, 0.5–2 g,
increases the risk that the results are affected by sample inhomo-
geneity. This is especially the case for very low activity samples
where the activity may reside in only a few hot particles per
gram of sample. In the case of SRM 4350b, mention is made
in the certificate of the existence of hot particles. This may
explain the deviation seen between our result and the published
value. The good agreement in other cases suggests the samples
are reasonably homogeneous. In the case of IAEA-375, our
successful analysis of the 0.49 g of the soil represents just 23 fg
and 7 fg of 239Pu and 240Pu respectively in the sample.
For several samples, isotopic information for Pu is reported
here for the first time. The soil IAEA 327 was collected in 1990
near Moscow. The Pu isotopic ratio measured is consistent
with that expected for global fallout. The Rocky Flats soil
(SRM-4353) has a low 240Pu : 239Pu ratio, showing evidence, as
expected, of local contamination with weapons-grade pluto-
nium. The high 240 : 239 ratio for IAEA-375 measured (0.296)
reflects contamination from the Chernobyl accident, being
distinctly higher than that measured for the average global
tropospheric fallout (0.18).16 However, the ratio is lower than
that of the Chernobyl source material (0.43)17 suggesting that
768 | J. Anal. At. Spectrom., 2008, 23, 765–768
the soil contains a mixture of Chernobyl fuel particles with
global tropospheric fall-out.
References
1 T. Kenna, J. Anal. At. Spectrom., 2002, 17, 1471.2 C. K. Kim, C. S. Kim, B. U. Chang, S. W. Choi, C. S. Chung,G. H. Hong, K. Hirose and Y. Igarashi, Sci. Total Environ., 2004,318, 197.
3 C. S. Kim, C. K. Kim, P. Martin and U. Sansone, J. Anal. At.Spectrom., 2007, 22, 827.
4 L. K. Fifield, Nucl. Instrum. Methods Phys. Res., Sect. B, 2000, 172,134.
5 J. E. McAninch, T. F. Hamilton, T. A. Brown, T. A. Jokela,J. P. Knezovich, T. J. Ognibene, I. D. Proctor, M. L. Roberts,E. Sideras-Haddad, J. R. Southon and J. S. Vogel, Nucl. Instrum.Methods Phys. Res., Sect. B, 2000, 172, 711.
6 M. Hotchkis, D. Child and C. Tuniz, J. Nucl. Sci. Technol., 2003, 39,532.
7 C. Tuniz, M. A. C. Hotchkis, J. M. Ferris, D. Child, D. Fink andG. E. Jacobsen, Proceedings of the 42nd INMM Annual Meeting,15–19 July 2001, Indian Wells, USA.
8 C. Sill, Health Phys., 1975, 29, 619.9 J. D. Farr, R. K. Schulze, M. P. Neu and L. Morales, LANL ActinideResearch Quarterly, 2nd quarter, 2004, p. 26.
10 S. L. Maxwell, Radioact. Radiochem., 1997, 8(4), 36.11 Eichrom Technologies Inc., Analytical Procedure ACW13 VBS, Rev
1.2, 2003.12 L. K. Fifield, R. G. Creswell, M. L. di Tada, T. R. Ophel, J. P. Day,
A. P. Clacher, S. J. King and N. D. Priest, Nucl. Instrum. MethodsPhys. Res., Sect. B, 1996, 117, 295.
13 M. A. C. Hotchkis, D. Child, D. Fink, G. E. Jacobsen, P. J. Lee,N. Mino, A. M. Smith and C. Tuniz, Nucl. Instrum. Methods Phys.Res., Sect. B, 2000, 172, 659.
14 D. P. Child, M. A. C. Hotchkis and M. L. Williams, in RecentAdvances in Actinide Science, ed. R. Alvarez, N. D. Bryan andI. May, RSC, Cambridge, 2006, pp. 50–52.
15 D. P. Child, M. A. C. Hotchkis and M. L. Williams, Proceedings ofthe 46th INMM Annual Meeting, 10–14 July 2005, Phoenix, USA.
16 K. O. Buesseler, J. Environ. Radioact., 1997, 36(1), 69.17 J. A. Entwistle, A. G. Flowers, J. C. Greenwood, A. Mellor and
G. Nageldinger, Geochem.: Explor., Environ., Anal., 2005, 5, 11.18 S. H. Lee, J. Gastaud, J. J. La Rosa, L. Liong Wee Kwong,
P. P. Povinec, E. Wyse, L. K. Fifield, P. A. Hausladen, L. M. DiTada and G. M. Santos, J. Radioanal. Nucl. Chem., 2001, 248, 757.
19 S. Sturup, H. Dahlgaard and S. C. Nielsen, J. Anal. At. Spectrom.,1998, 13, 1321.
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