Rapid determination of 90Sr/90Y in water samples by liquidscintillation and Cherenkov counting
Jennifer M. Olfert • Xiongxin Dai •
Sheila Kramer-Tremblay
Received: 30 August 2013
� Atomic Energy of Canada Limited 2014
Abstract Strontium-90 (90Sr) is a ubiquitous contaminant
at nuclear facilities, found at high concentrations in spent
nuclear fuel and radioactive waste. Due to its long half-life
and ability to be transported in groundwater, an accurate
method for measuring 90Sr in water samples is critical to
the monitoring program of any nuclear facility. To address
this need, a rapid procedure for sequential separation of Sr/
Y was developed and tested in groundwater samples col-
lected from an area of riverbed affected by a 90Sr
groundwater plume. Sixteen samples, plus spike and water
blanks, were analyzed. Five different measurements were
performed to determine the 90Sr and yttrium-90 (90Y)
activities in the samples: direct triple-to-double-coin-
cidence ratio (TDCR) Cherenkov counting of 90Y, liquid
scintillation (LS) counting for 90Sr following radiochemi-
cal separation, LS counting for 90Y following radiochem-
ical separation, Cherenkov counting for 90Y following
radiochemical separation and LS counting of the Sr sam-
ples for 90Y in-growth. The counting was done using a low-
level Hidex 300SL TDCR counter. Each measurement
method was compared for accuracy, sensitivity and effi-
ciency. The results following Cherenkov counting and
radiochemical separation were in very good agreement
with one another.
Keywords Radiostrontium � Liquid scintillation
counting � Cherenkov counting � Water � Monitoring
Introduction
Strontium-90 (90Sr) is a ubiquitous contaminant at nuclear
sites, resulting from nuclear fission of plutonium and ura-
nium. As a result, it is found in high concentrations in spent
nuclear fuel and radioactive waste. World-wide nuclear
weapons testing in the 1950s and 1960s also resulted in
widespread distribution of 90Sr [1]. With its long half-life
of 28.79 years, 90Sr persists in the environment and if
released into soil, can form subsurface groundwater plumes
that could eventually discharge to surface waters [2, 3].90Sr is mobile in groundwater, with studies at Atomic
Energy of Canada Limited (AECL)’s Chalk River Labo-
ratories (CRL) showing that it moves at about 10 % of the
groundwater speed [4]. It is biochemically similar to cal-
cium and can therefore be accumulated in the bones if
taken up, potentially leading to cancers of the bone marrow
and the soft tissues surrounding the bone [5]. Thus, it is
important that effective monitoring techniques exist for90Sr in water samples, both as part of the regular moni-
toring program at nuclear sites and in the case of a radio-
logical emergency.
Although numerous radioanalytical procedures for 90Sr
in environmental water samples have been reported [6–11],
many of them require a large sample volume and are time-
consuming. Therefore, a more rapid method for measuring90Sr in environmental water samples would be beneficial.
To address this, rapid procedures for radiochemical sepa-
ration of 90Sr/90Y were developed and tested in ground-
water samples collected from an area of riverbed at the
CRL site affected by a 90Sr groundwater plume. The
measurements obtained from these procedures were also
compared to the measurements obtained from direct triple-
to-double-coincidence ratio (TDCR) Cherenkov counting.
The use of direct Cherenkov screening has increased [12];
J. M. Olfert (&) � X. Dai � S. Kramer-Tremblay
Chalk River Laboratories, Atomic Energy of Canada Limited,
Chalk River, ON K0J 1J0, Canada
e-mail: [email protected]
123
J Radioanal Nucl Chem
DOI 10.1007/s10967-013-2913-0
however, questions remain about how potential interfer-
ences (e.g., 40K, 210Pb/210Bi and other high energy beta-
emitting radionuclides) may affect the accuracy of its
measurements. Details of all the methods tested are
described and compared for accuracy, efficiency and
sensitivity.
Experimental
Reagents and standards
All of the reagents used in the procedures were analytical
grade or better. Hydrochloric and nitric acids were pur-
chased from Fisher Scientific Canada (Ottawa, ON, Can-
ada). Deionized water was obtained from a Millipore
Direct-Q5 Ultrapure water system.
Sr and DGA-N resins (50–100 lm) in 2 ml pre-packed
cartridges were obtained from Eichrom Technologies Inc.
(Lisle, IL, USA). The TraceCERT� stable Sr standard
(1,000 mg/l) was obtained from Sigma-Aldrich Canada
(Oakville, ON, Canada). The stable Y standard (2,000 mg/l
in 1 M HCl) was made using yttrium(III) nitrate tetrahydrate
obtained from Sigma-Aldrich Canada. The stable standards
were used to monitor chemical recovery. The radioisotope
standard for 90Sr was obtained from the National Institute of
Standards and Technology (Gaithersburg, MD, USA).
Ultima Gold AB liquid scintillation (LS) cocktail is avail-
able from PerkinElmer Canada (Woodbridge, ON, Canada).
Sample collection
Sixteen groundwater seep samples were collected from the
discharge zone of a groundwater plume containing 90Sr.
The samples were filtered through a 0.45 lm filter and
acidified with concentrated nitric acid to a final concen-
tration of 1 %.
TDCR Cherenkov counting
Three spike samples were prepared by adding known
amounts of the 90Sr standard to 20 ml of 1 % nitric acid.
The sixteen water samples, three spike samples and a
deionized water blank were counted on a low-level Hidex
300SL liquid scintillation (LS) counter (Hidex Oy, Fin-
land) for 30 min per sample. The TDCR ratio was used for
the correction of the counting efficiency by the following
formula:
Corrected counting efficiency ¼ 0:9� TDCR0:75
Details of the TDCR Cherenkov method have been
described in [13, 14].
Gamma analysis
Gamma spectrometry analysis was performed on five
samples representing the concentration ranges observed in
TDCR Cherenkov counting (SS1, SS7, NS2, NS8, NS9) to
determine if there were any significant contributions from
high energy beta-emitters that might interfere with the
direct TDCR Cherenkov results. A 500-ml polypropylene
bottle containing approximately 125 ml of sample was
placed directly on the detector face of a high purity ger-
manium detector (Ortec, USA) for up to 4 h.
Radiochemical separation
After the TDCR Cherenkov counting, all the groundwater
seep samples, spike samples and a water blank sample were
processed for simultaneous separation of 90Sr and 90Y,
followed by Cherenkov and LS counting. A 20 ml aliquot
of the original sample was first acidified by adding 20 ml
of concentrated nitric acid for a final concentration of
approximately 8 M. To measure the chemical recovery,
1 mg of stable strontium and 1 mg of stable yttrium were
added to each sample.
In order to sequentially separate the Sr/Y from the water
and any interfering substances, the Sr resin and DGA-N
resin cartridges were stacked with the DGA-N cartridge on
top. A 12-hole vacuum box (available from Eichrom
Technologies Inc.) system was used to help draw the
samples through the cartridges. A 60-ml plastic syringe
was attached to the top of the Sr resin cartridge with a two-
way luer lock valve (available from Cole-Parmer) to use as
a sample reservoir. Prior to separation, the columns were
pre-conditioned with 10 ml of ultrapure water followed by
10 ml of 8 M HNO3, both at a flow rate of 3.0 ml/min. The
samples were then passed through the cartridges at a flow
rate of 1.0 ml/min to extract Y onto the DGA-N resin and
Sr onto the Sr resin. After rinsing with 10 ml of 8 M
HNO3, the two resin cartridges were split for elution. The
Y was eluted off the DGA-N cartridge with 6 ml of 0.05 M
HCl into a pre-weighed 20 ml plastic scintillation vial. The
eluate was immediately counted on the low-level Hidex
LSC using the TDCR Cherenkov counting protocol for
direct determination of 90Y. After the Cherenkov counting,
0.2 g of the Y eluate was transferred to a 50-ml pre-
weighed centrifuge tube and diluted with 50 ml of 0.1 M
HNO3 for analysis of stable Y by ICP-MS analysis to
determine the Y chemical recovery. The remainder of
eluate was then mixed with 14 ml of Ultima Gold AB LS
cocktail for LS counting.
The Sr extracted was eluted off the Sr resin cartridge
with 6 ml of ultrapure water into a pre-weighed 20 ml
plastic scintillation vial. About 0.2 g of the Sr eluate was
transferred to a 50-ml pre-weighed centrifuge tube and
J Radioanal Nucl Chem
123
diluted with 50 ml of 0.1 M HNO3 for analysis of stable Sr
by ICP-MS to determine the Sr chemical recovery. The rest
of the eluate was mixed with 14 ml of Ultima Gold AB LS
cocktail for LS counting.
LS counting
The samples were counted for 90Sr or 90Y on the Hidex
300SL TDCR LS counter. For both LS and Cherenkov
counting, samples were counted for 30 min each. To
measure 90Y in-growth, the samples containing the 90Sr
fraction were recounted 8 days later.
Results and discussion
Minimum detectable activity and concentration
The minimum detectable activity (MDA) for each sample,
spike and blank was calculated using the Currie equation
[15] as described by Dai et al. [16]. The average MDAs of
five blank samples were 0.12 ± 0.02 Bq for 90Sr and
0.18 ± 0.06 Bq for 90Y. Considering the sample volume of
20 ml, the minimum detectable concentrations (MDC)
were calculated to be 5.7 ± 0.9 Bq/l for 90Sr and
9.1 ± 2.8 Bq/l for 90Y.
Based on the ICP-MS analysis, the average chemical
recovery for 90Sr was found to be consistently high at
92 ± 5 %, while that of 90Y was lower at 52 ± 15 %. The
low chemical recovery for 90Y is due to eluting the column
with an insufficient volume of HCl. The procedure has
been modified so that elution would be done with 9 ml of
0.05 M HCl instead of only 6 ml, with an increased
recovery of [90 %.
Performance evaluation of spiked water samples
Three water samples were spiked with known amounts of90Sr (1, 3.5 and 10 Bq), resulting in concentrations of 51.7,
175 and 546 Bq/l. The results for the spiked water samples
are shown in Fig. 1 and Table 1. The measurements in
each of the methods tested agreed well with the expected
Fig. 1 A comparison of the expected concentration of the spike
samples versus the five measured concentrations. Error bars represent
combined errors. The solid line is the 1:1 reference line
Table 1 Results of the expected concentration of the spike samples compared to the actual concentration
Low spike
51.7 Bq/l
Medium spike
175 Bq/l
High spike
546 Bq/l
Measured (Bq/l) Variation (%) Measured (Bq/l) Variation (%) Measured (Bq/l) Variation (%)
90Y:TDCR Cherenkov 55 5.9 182 4.0 577 5.590Sr:LSC 53 2.5 205 16.8 550 0.690Sr:Y in-growth 61 18 160 -8.9 614 12.490Y:LSC 44 -15.9 198 12.8 556 1.690Y:Cherenkov 48 -7.2 192 9.4 600 9.8
Fig. 2 Diagram showing an overview of the methodology used to
determine 90Sr and 90Y in groundwater samples
J Radioanal Nucl Chem
123
value. The chemical recovery for 90Sr was very good,
ranging from 87 to 90 % and averaging 88.7 ± 1.5 %.
There was much more variability in the chemical recovery
of 90Y, which ranged from 36 to 71 % and averaged
47.7 ± 7.2 %. Again, this is a result of insufficient elution
volume.
Gamma spectrometry analysis
The primary high energy beta-emitters that would be
expected to interfere with Cherenkov counting are 40K,137Cs, 60Co and 210Bi. Gamma analysis of selected samples
revealed no appreciable contribution from 40K, 137Cs or60Co. Determining the concentration of 210Bi requires more
extensive analysis and has not been completed at this time.
However, as the daughter product of naturally-occurring
210Pb, 210Bi is not expected to be present in these water
samples at a level of [5 Bq/l and thus would not interfere
with Cherenkov counting of 90Y.
Comparison of five measurements
The complete methodology is shown in Fig. 2.
In total, five different measurements were conducted:
direct TDCR Cherenkov counting of 90Y, LS counting for90Sr following radiochemical separation, LS counting for90Y following radiochemical separation, Cherenkov
counting for 90Y following radiochemical separation and
LS counting for 90Y in-growth of the Sr samples. Each
measurement has its own advantages and drawbacks.
Direct TDCR Cherenkov counting is very rapid, as there is
no sample pre-treatment or radiochemical separation
a
b
Fig. 3 The concentration of90Sr as determined by the five
different measurements is
shown in a. Note that the scale
is logarithmic. The
concentration of 90Sr
determined by direct Cherenkov
counting compared to the
averaged concentration of the
other four measurements is
shown in b
J Radioanal Nucl Chem
123
required, and scintillation cocktail does not need to be
added. Another advantage is that it is independent of
chemical quenching. It provides a good screening method
to quickly determine if there are any high-energy beta-
emitters (including 89Sr) in the samples. However, Cher-
enkov counting is subject to interference from other high-
energy beta/gamma-emitters (i.e. 40K, 210Pb/210Bi, 60Co
and 137Cs). Although radiochemical separation requires
sample pre-treatment and overall takes longer than direct
Cherenkov counting, results are still achievable in 1 day.
Doing a radiochemical separation removes impurities or
interferences from the sample, thus giving results specific
to Sr or Y without the concern of interferences. The DGA
and Sr resin columns can be stacked during the separation,
allowing Sr and Y radionuclides in a sample to be simul-
taneously separated.
Figure 3a shows the 90Sr concentration determined by
each measurement on a logarithmic scale. The results from
each method agreed very well with one another above the
MDC. The concentration of 90Sr determined by direct
TDCR Cereknov counting was also plotted against the
average 90Sr concentration of the other four measurements
following radiochemical separation (Fig. 3b). As shown in
Figs. 3a and 3b, all five measurements agreed very well
with one another, demonstrating that results obtained by
TDCR Cherenkov counting are just as reliable as those
obtained following radiochemical separation.
Conclusions
A rapid procedure for sequential separation of Sr/Y was
developed and tested. The method involved sequential
separation of 90Sr and 90Y, followed by Cherenkov and LS
counting. Following radiochemical separation, the activity
of the 90Sr fraction was counted immediately on a Hidex
300SL TDCR counter. The samples were recounted 8 days
later to measure 90Y in-growth. The activity of the 90Y
fraction was measured immediately after radiochemical
separation by Cherenkov counting and then by LS count-
ing. The results of the four measurements following
radiochemical separation were compared to those obtained
from direct TDCR Cherenkov counting. A set of water
samples collected from the discharge zone of a ground-
water plume containing 90Sr were analyzed. The mea-
surements obtained from counts following TDCR
Cherenkov counting and radiochemical separation agreed
very well. This confirmed that direct TDCR Cherenkov
counting can serve as a rapid screening method with reli-
able results. However, the radiochemical separation
method may yield more accurate results in cases where
other interfering radionuclides are present in the samples.
Acknowledgments The authors acknowledge the financial support
from Atomic Energy of Canada Limited (AECL).
References
1. UNSCEAR (2000) Sources and effects of ionizing radiation.
Report to the General Assembly of the United Nations with
Scientific Annexes, United Nations sales publication E.00.IX.3,
United Nations
2. Amano H, Matsunaga T, Nagao S, Hanzawa Y, Watanabe M,
Ueno T, Onuma Y (1999) Org Geochem 30(6):437–442
3. Shevchenko A, Gudzenko V, Nasedkin I, Panasevitch E (2001)
Environ Geol 40:1177–1184
4. Audet M (2013) Annual Safety Report—CRL Groundwater
Monitoring Program Annual Report for 2011, Atomic Energy of
Canada Limited. CRL-509247-ASR-2011
5. United States Environmental Protection Agency (2012) Radiation
protection: strontium. http://www.epa.gov/radiation/radionuclides/
strontium.html. Accessed 10 Dec 2013
6. Vajda N, Kim CK (2010) Appl Radiat Isot 68(12):2306–2326
7. Vaney B, Friedli C, Geering JJ, Lerch P (1989) J Radioanal Nucl
Chem 134:87–95
8. Cobb J, Warwick P, Carpenter RC, Morrison RT (1994) Analyst
119:1759–1764
9. Shabana EI, Al-Hussan KA, Al-Jaseem QK (1996) J Radioanal
Nucl Chem 212:229–240
10. Grahek Z, Zecevic N, Lulic S (1999) Anal Chim Acta 399:
237–247
11. Popov L, Hou X, Nielsen SP, Yu Y, Djingova R, Kuleff I (2006) J
Radioanal Nucl Chem 269:161–173
12. Stamoulis KC, Ioannides KG, Karamanis DT, Patiris DC (2007) J
Environ Radioact 93:144–156
13. Tayeb K, Dai X, Corcoran EC, Kelly DG (2013) J Radioanal
Nucl Chem (Accepted)
14. Kossert K (2010) Appl Radiat Isot 68:1116–1120
15. Currie LA (1968) Anal Chem 40:586–593
16. Dai X, Cui Y, Kramer-Tremblay S (2013) J Radioanal Nucl
Chem 296:363–368
J Radioanal Nucl Chem
123