Application Note: Gross Alpha Measurements in Aqueous Samples Using Extraction Chromatography and Liquid Scintillation Counting

a p p l i c at i o n N o t e

Liquid Scintillation Counting

Gross Alpha Measurements
Author
in Aqueous Samples Using Anil Thakkar, Michael Fern, Thomas Kupka,

Extraction Chromatography and James Harvey
Eichrom Industries Inc. and Charles J. Passo Jr.
and Liquid Scintillation and James Thomson
Packard Instrument Company
Counting

Abstract to reach a detection limit of 100 mBq/ L. Samples containing
extremely high levels of dissolved solids may require even longer
A new approach to the measurement of gross alphas in liquid
counting times to achieve the desired detection limit since an
samples, which combines Eichrom’s extraction technology with
even smaller sample size must be used. Alpha LSC has been
PerkinElmer’s liquid scintillation analysis technology, is presented.
proposed as an alternate to GPC for gross alpha measurements.
Difficulties with sample preparation and detection efficiency have
The inherent counting efficiency for alpha particles by LSC is
always been problematic with the traditional method of gas flow
in excess of 90%. Since it does not suffer from self absorption
proportional counting (GPC). The use of Eichrom’s extraction
problems, LSC can handle higher levels of dissolved solids.
resins and alpha liquid scintillation counting (LCS) has resolved the
However, the sample size is limited by what can be put into an
sample preparation problems, associated with drying the sample
LSC vial, and so for samples larger than 10 mL, some form of
on a planchet. With its superior detection efficiency over GPC,
sample concentration must be performed. As shown in Figures 1
this combination provides a better counting platform. Thus, many
and 2, Eichrom Industries actinide resin shows excellent uptake
of the inherent limitations associated with the traditional GPC
for all the actinides and for radium under neutral to slightly acidic
method are overcome by using this new approach and results
conditions,1,2 and is therefore a good candidate to preconcentrate
demonstrate faster sample preparation, lower detection limits
samples prior to alpha LSC. The actinide resin (using the Dipex®
and shorter counting times.
extractant3) is an extraction chromatographic resin in which the
functional group on the extractant molecule is a diphosphonate
Introduction moiety. The structure of this molecule is shown in Figure 3.
The traditional method of gross alpha measurements for liquid
samples using GPC suffers from a number of limitations. In order A method has been developed which combines this resin and
to minimize the problem of self absorption, the volume of sample alpha LSC to measure total alpha activity in water samples.
which can be analyzed is limited by the amount of dissolved The method is fast and simple. As many as 20 samples can be
solids found in the aqueous samples (typically environmental and processed in 24 hours, requiring only one to two hours of
process waters). Counting efficiency of alpha particles by GPC hands-on time. Using 100 mL samples, a detection limit of 2 pCi/L
is 35% to 40% at best (0 mg residue) and declines to less than (75 mBq/L) can be reached with only 60 minutes counting time.
10% when 100 mg of solids are left on the counting planchet.
Counting times in excess of 1000 minutes are typically required

Figure 1. Figure 2.
Figure 1. Acid dependency of the the uptake of several actinide species
Acid dependency of uptake of several actinide species Figure 2. Acid dependency of the uptake of of several non-actinide species
Acid dependency of the uptake several non-actinide species
by the Dipex resin. Figure 1. resin.
by the Dipex by the Dipex resin. Figure 2. resin.
by the Dipex
Acid dependency of the uptake of several actinide species Acid dependency of the uptake of several non-actinide species
by the Dipex resin. by the Dipex resin.
Experiment
Experiment
the same manner as the blanks except that the appropriate spike
mL Ultima Gold LLT were added to a glass scintillation
was also added directly to the scintillation vial. The simulated
Experiment (0.5 g) was , and to one liter of a spiked mL vial.blanks except were prepared with two stockwas also the
Actinide resin (0.5 g) was added to one liter of a spiked water
sample acidified to pH 2 with HNO addedstirred on a magnetic
Actinide resin
Ultima Gold LLT were prepared in the same manner as
the
Direct spikes
ground water matrix was added to a glass scintillation
that the appropriate spike solutions;
vial. Direct spikes were in Table 1.in the same manner as
composition is shown prepared
stir plate. After the (0.5 g) was addedtime, the HNO3, and stirred the added directly that the appropriatevial. The simulated
water sample acidified to pH 2 with resin a spiked
blanks except to the scintillation spike was also
3
Actinide resin indicated contact to one liter of was collected
wateronsample acidified to pH 2 with indicated contact time,
a magnetic stir plate. After the HNO , and stirred ground water matrix was prepared with two stock solu-
using a vacuum filtration apparatus and a 0.45 micron Gelman added directly to the scintillation vial. The simulated
on athe resin was collected using a vacuum filtrationthe filter ground liter of compositionprepared with two stock solu- purity
appara- One the each stock solution was prepared with high
tions;water matrix was is shown in Table 1.
3
filter. The resin a 0.45 micron Gelman indicated contact time,
magnetic stir plate. After the
tus and was rinsed with deionized (DI) water and rinsed
filter. The resin was
the resin was collected using atransferred to a watch glass
vacuum filtration appara-
containing the collected (DI) water and the filter containing the tions; theTwenty-five mL of each stock solution was added to 900
water. composition is shown in Table 1.
with deionized resin was
tus and a 0.45 micron Gelman filter. The resin was rinsed One liter of each stock solution was prepared with high
and placed under a heat was transferred to a watch glass and
collected resin lamp (approximately 75 cm above) for
Onepurityof eachTwenty-five was prepared with high NaOH,
mL of high purity water and mL of each pH of solution was
liter water. stock solution
mixed. The stock the resulting
with deionized (DI) water and the filter containing the
placedresin was transferred to a resin. The dried resin
under a heat lamp (approximately 75 cmand
approximately 15 minutes to gently dry the watch glass
collected above) solution to 900 mL ofto 9.8 using 0.1M HCl and 0.1M The
added was adjusted high purity water and mixed.
purity water. Twenty-five mL of each stock solution was
carefully transferred into minutes to gently dry the resin. added to 900 mL of high puritythen diluted mixed. The
for approximately 15 glass scintillation vial and the filter as necessary.resulting solution was adjusted tofinal volume of
wasplaced under a heat lampa(approximately 75 cm above) pH of the The solution was water and to a 9.8 using
The1dried resin15HCl.carefullygentlyrinse was collected
was The 0.5Mtransferredthe resin.
into a glass 1000 mL. Aliquots of this solution were spikedThe solution the
rinsed with mL of 0.5M minutes to HCl dry
for approximately pH 0.1M HCl and 0.1M NaOH, as necessary.9.8 using in
of the resulting solution was adjusted to and used
scintillation vial and the filter rinsedLLT was mLglass
with 1 added 0.5M procedure as the simulated ground water matrix. Aliquots
of
in the scintillation vial. Tencarefully transferred into a
The dried resin was mL Ultima Gold 0.1M HCl and 0.1M NaOH, volume of 1000 mL.
was then diluted to a finalas necessary. The solution
scintillation vial andHCl filter rinsed with 1 mL the 0.5M
HCl. The 0.5M the rinse was collected in of scintilla-
and the alpha activity was counted on a PerkinElmer Tri-Carb wasof this solution were spiked and used inmL. procedure as
then diluted to a final volume of 1000 the Aliquots
HCl. The 0.5M HCl rinse wasGold LLT times added30 orthe of this solution were spiked and used in the procedure as
tion vial. Ten mL Ultima collected in the scintilla-
was and
®
the simulated ground water matrix.
2550TR/AB liquid scintillation counted Count Packard Tri-Carb ®
tionalpha Ten mL Ultima Gold LLT was added and the
vial. activity was
counter. on a were
60 minutes as indicated and the alpha region of interest was®set the simulated ground water matrix.
alpha activity was counted on a Packard Tri-Carbtimes
2550TR/AB liquid scintillation counter. Count
between 90 and or 60keV. The alpha/beta discriminator setting
2550TR/AB 500 minutes as indicated and Count times
were 30 liquid scintillation counter. the alpha region
(124) was30 or 60 minutes between procedure inalpha The alpha/
were determined following the 90 and 500 keV.instrument
of interest was set as indicated and the the region
instruction manual, set between 90(124)500 keV. The alpha/
beta discriminator setting and was determined follow-
of interest was using 210Po as the pure alpha source and
90 90
Y ing the procedure in the instrument instruction manual,
Sr/betaas the 210 beta source. Vialswas determined follow-
discriminator setting (124) used in the discriminator
pure
ing procedure had thethe instrument instructionSr/ Y as the
using Po as the pure alpha source and 90 manual, 90
setting the procedure in same composition as the actual
pure Po assource. Vials used in the discriminator the
210 beta
Y as setting
samplesprocedure the pure resin, 1source andHCl, and the mL
using (i.e., 0.5 g actinide alpha mL 0.5M Sr/as 10 actual
90 90
had theused in composition
pure Gold LLT). Blank
beta source. Vials same the discriminator setting
Ultimasamples (i.e., 0.5samples were prepared as follows: 0.5 g
procedure had the same compositionmL 0.5Mactual and
g actinide resin, 1 as the HCl,
actinide10 mL1 mL 0.5 M HCl, andBlank samples were prepared
resin, Ultima Gold LLT). 10
samples (i.e., 0.5 g actinide resin, mL Ultima Gold LLT were
1 mL 0.5M HCl, and Figure 3.
added to afollows:Gold LLT). Blank samples0.5 Mprepared in
10 mL Ultima 0.5 g actinideDirect spikes were prepared 10
as glass scintillation vial. resin, 1 mL were HCl, and Figure 3. Eichrom Dipex extractant.
Eichrom Dipex extractant.
as follows: 0.5 g actinide resin, 1 mL 0.5 M HCl, and 10 Figure 3.
Eichrom Dipex extractant.
Page 2 – Application Note
Page 2 – Application Note

2

Table 1.
Ground water composition.
Table 1. Ground water composition.
Table 1.

Results and Discussion
Results and Discussion Table 1.
Percentageand Discussion
Results uptake of various spikes of alpha emitters of
Percentage uptake of various spikes of alpha emitters of interest
interest were measured using the procedure, previously
were measured using the procedure, previously described. 241Am,

Resultsof500Am ofof variouswith aprocedure, emitters time
Percentage241Am, 234/238U,used.spikes226Ra were used. The
described. uptake were 232ThThe uptake of Am and
Discussion the 30 alphaofcontact of
and of
and mL and 234/238U from 500minute previously
234/238
U, 232Th and 226Ra 241

uptake were measured using
interest 241
234/238
U from DI water mL DI water
is shownain Tables 2of234/238U, 232Th is shown in emitters2of
with 30 241Am, contact spikes of alpha Tables and
described.minuteand 3. time and 226Ra were used. The
Percentage uptake various
uptake of 241Am and 234/238 the procedure, of DI water
3.
interest were measured usingU from 500 mLpreviously
described. 241minute contact Th and 226Ra wereTables the
with a 30 Am, 234/238U, 232 time is shown in used. 2 and
Americium uptake was 234/238 excellent asexpected fromThe
uptake of behavior of 241Am on241 500 wasresin. The uranium
Americium uptake was U fromwas mL of DI water
3. expected from
excellent as
241
Am and
the theoretical contact time isAm on in Tables 2 and
theoretical
with a 30 minute behavior of the actinide actinide resin.
shown the
recoveries were uptake expected. Sinceas as expected. Since
The uranium recoveries were not was expected from
3. Americium not as was excellent thermodynamically, the
actinidetheoretical behavior actinideall of the uranium, resin.
thermodynamically, the of up resin should have
the resin should have taken241Am on the actinide taken Table 3. Uptake of 234/238U at 30 minute contact time.
we The uraniumuranium, wewere as was expected from to
Americium uptake was excellent notkinetic issuethere was
up all of the recoverieswas some as expected. Since
evaluated whether there evaluated whether related Table 3.
the theoretical issue related to uptake onto the have of
some kineticbehavior of 241Am resin actinide timeCor-
thermodynamically, the actinideon theshould resin.taken Uptake of 234/238U at 30 minute contact time.
uptake onto the resin. Correspondingly, the contact resin.
respondingly, the contact evaluated whether Since
up all of the uranium, we time of the sample with the
The uranium the actinide resin was extended. Inthere was Table 3.
the sample withrecoveries were not as expected. Table 4,
thermodynamically, related to uptakeshould contact times
some kinetic issue extended. resin onto4, have uranium
actinide resin was actinide In Table the resin. Cor-
the taken Uptake of 234/238U at 30 minute contact time.
the respondingly, the thevarious sample contact times are
up spike recoveries at we evaluated whether there wasthe
uranium spike recoveries at time of sample
contact various the sample with
all of the uranium, Table 3.
shown.
are actinide resin was extended. In Table 4, the uranium
shown.
some kinetic issue related to uptake onto the resin. Cor- Uptake of 234/238U at 30 minute contact time.
respondingly, the contact time samplesample with the
spike recoveries at various of the contact times are
shown.
actinide resin was extended. In Table 4, the uranium
spike recoveries at various sample contact times are
shown.

Table 4.
Effect of contact time on 234/238U spike recovery.
Table 4. Effect of contact time on 234/238U spike recovery.
Table 2. Table 4.
Uptake of 241Am (91.6% efficiency). Effect of contact time on 234/238U spike recovery.
Table 2. Table 4.
Uptake of 241Am (91.6% efficiency).
Application Note
Effect of contact time on 234/238U spike recovery. – Page 3
Table 2. Uptake of Am (91.6% efficiency).
241
Table 2.
Uptake of 241Am (91.6% efficiency). Application Note – Page 3

3 Application Note – Page 3

The data indicatesindicates a relationshipcontact time and time
The data a relationship between between contact
uranium spike recovery. At recovery. At four hours the
and uranium spike four hours contact time, contact time,
recovery is quantitative. quantitative. contact period represents
the recovery is The 18 hour The 18 hour contact period
overnight (unattended) contact of the resin with the sample. resin
represents overnight (unattended) contact of the
Unattended operations which can be carried out overnight can be
with the sample. Unattended operations which are
carried out overnight are attractive to routine production
attractive to routine production laboratories because of the
laboratories because of the effective use of space and
effective use of space and time. This contact time period was
time. This contact time period was chosen for all future
chosen experiments. experiments. Based in Table 4, it is expected
for all future Based on the data on the data in Table
4, it is expected that four hour contact time is also adequate. re-
that four hour contact time is also adequate. Spike
coveries of thorium and radium from DI water (18 hour
Spike recoveries of thorium and radium from DI water (18 hour
contactcontact time) were acceptable. See Table 5.
time) were acceptable. See Table 5.

The one lowone low recovery forrepresented a sample in sample
The recovery for thorium thorium represented a
which there was non-quantitative transfer of the actinide resin ac-
in which there was non-quantitative transfer of the
from the filter resin from the filter paper to The next step in the
tinide paper to the scintillation vial. the scintillation vial.
The next step in the evaluation of this procedure was to
evaluation of this procedure was to test it on samples of the
test it on samples of the simulated ground water matrix. Table 5. Spike recoveries with 232Th and 226Ra.
Table 5.
See Tables 6 and 7.
simulated ground water matrix. See Tables 6 and 7.
Spike recoveries with 232Th and 226Ra.
The data indicates a relationship between contact time
All the actinides show good uptake from 500 mL samples.
All uranium spike recovery. At four hours contact time,
and the actinides show good uptake from 500 mL
Thorium recoveries, while not quantitative, werenot quantitative,
samples. indicates a relationship18 hour contact period
the data Thorium recoveries, between contact time
Therecovery is quantitative. Thewhile
equivalent
to the recoveries observed fromrecoveries Radium recoveries,resin
were equivalent to recovery. At four hours contact time,
and uranium spike the
DI water. observed from DI wa-
represents overnight (unattended) contact of the
however, were poor recoveries, however, were poor (seecan be
ter. recovery (see Table 7). As The 18be predicted period
withRadium is quantitative. might hour contact Table
the the sample. Unattended operations which
from the data in Table 7,predicted from thetoin the simulated the
7). As might be the calcium presentcontact Table 7,
carried out overnight are attractive data in of the resin
represents overnight (unattended) routine production
ground calcium present in the simulated ground which matrix,
with the sample. Unattended operations water canand
laboratories because of prevent (or possiblyof space be
water matrix, appears to the effective use block) the
uptake appearsout contact timepossiblywas to routine production
carried to prevent (or period block) the uptake future
of radium overnight are attractive chosen for all of ra-
time. Thison the actinide resin. Subsequent experiments
dium on the actinide resin. Subsequent experiments from
from 100 mL samplesBased on the data in Table 4, ofis expected
experiments. becausesimulated matrix showed much and
laboratories of the of the effective use it space
100 mL samples of thetime is wasmatrix showed much
time. This contact time simulated adequate. calcium
that four hour contact period also chosen for Spike re-
better uptake,uptake, probablythe lower overall level of all future
better probably due on the datathe lower overall(18 hour
experiments. Based anddue to from DI water expected level of
to
coveries of thorium radium
present. The results are equivalent to thein Table 4,5. isto the DI
it
calciumtime) were acceptable.are equivalent Spike re-
contact present. The results alsowater recoveries in
See Table
DI
that four hour contact time is adequate.
Table 5. See Table 8 for these results. See Table 8 for these re-
water recoveries in Table 5.
coveries of thorium and radium from DI water (18 hour
sults. time) recovery for thorium represented a sample
The one low were acceptable. See Table 5.
contact
in which there was non-quantitative transfer of the ac-
The final test of the method was to analyze actual Table 6.
environmentalresin from the method was to the scintillationenvi-
The finallow recoveryhad been previously characterized
The one test of the for paper to analyze actual vial.
tinide samples whichfilter thorium represented a sample U uptake from simulated ground water matrix.
234/238

for gross alpha activityin thewhich had been previously charac-
ronmentalthere by theevaluation of this procedure the ac-
in which samples traditional evaporation/ GPC
The next step was non-quantitative transfer of was to
method. Twenty-four (24)the the simulated the traditional matrix.
terizedresingross alpha activity by ground water evapo-
tinide for from samples paper to the scintillation
test it on samples of filter were received from the vial.
Table 5.
ration/GPC 6 andSurveys National Watersamples Lab re-
The Tables method. Twenty-four (24) Quality were
See next step in 7.
United States Geological the evaluation of this procedure was to Spike recoveries with 232Th and 226Ra.
ceivedon samplesUnited States Geological Surveys Na-
from the of
(NWQL)testArvada, Colorado.the simulated ground water matrix.
in it
tional Water Quality Lab (NWQL) in Arvada, Colorado.
These samples represented Table 6. 234/238U uptake from simulated ground water matrix.
Table 5.
All Tables 6 and 7.show good uptake from 500 mL
the actinides
See samples from across the United States. Total
ground These samples represented ground water samples from
water
samples. Thorium recoveries, while not quantitative, Spike recoveries with 232Th and 226Ra.
dissolved solidsthe United States. been measured onfromof(TDS)
across (TDS) content had Total dissolved solids DI wa-
were equivalent to show good observed ten
All the actinides the recoveriesuptake from 500 mL
these samples, ranging asmeasured on ten of these samples,Table
content had been high as 1700 mg/L. Overall the results
samples. Thorium recoveries, while poor (see rang-
ter. Radium recoveries, however, werenot quantitative,
ing As high as 1700 mg/L.from the the results obtained
7). as might be to the recoveries observed method the
were equivalent predicted Overall data in Table 7,
obtained for the 24 samples using the proposed LSC from DI wa-
agreed for the 24 samplesthe simulated ground water method
extremely well with using the proposed LSC matrix,
calcium present in thosehowever, were poorusing Table
ter. Radium recoveries, previously obtained (see
agreed might be predicted in Table 9 previously obtained
appears to prevent (or with those data in Table
7). As extremely wellpossibly the are the results of ra-
the GPC method. The data shown from block) the uptake 7, the
using on the
dium thepresentmethod. The data shown intotal 9 are
calcium GPC in resin. Subsequent experiments from
Table
determined by each actinidethe simulated ground water matrix,
method along with the 2 sigma
the results determined by each method theshowed of ra-
100 mL to prevent (or possibly block) along with much
appears samples of the simulated matrix uptake the 2
propagated uncertainty (TPU). uncertainty (TPU).
sigmaon the propagated due to the lower overall level of
dium total actinide resin.
better uptake, probably Subsequent experiments from
calcium present. The results are matrix showed much
100 mL samples of the simulated equivalent to the DI
water uptake, probably due5. See lower overallthese re-
better recoveries in Table to the Table 8 for level of Table 7.
sults.
calcium present. The results are equivalent to the DI 232
Th and 226Ra uptake from simulated ground water matrix.
Table 7. 232Th and 226Ra uptake from simulated ground water matrix.
water recoveries in Table 5. See Table 8 for these re- Table 6.
The final test of the method was to analyze actual envi-
sults. 234/238
U uptake from simulated ground water matrix.
ronmental samples which had been previously charac-
Table 6.
terized for gross the method was to analyze actual envi-
The final test of alpha activity by the traditional evapo- 234/238
U uptake from simulated ground water matrix.
ration/GPCsamples which had been previouslywere re-
ronmental method. Twenty-four (24) samples charac-
ceived for gross United States Geological Surveys Na-
terized from the alpha activity by the traditional evapo-
tional Watermethod. Twenty-four (24) samples were re-
ration/GPC Quality Lab (NWQL) in Arvada, Colorado.
These samples represented ground water samples from
ceived from the United States Geological Surveys Na-
acrossWater Quality Lab (NWQL) in Arvada, Colorado.
tional the United States. Total dissolved solids (TDS)
content had been measured ground these samples from
These samples representedon ten of water samples, rang-
ing as4the Application Note dissolved solids (TDS)
across highUnited States. Total
Page – as 1700 mg/L. Overall the results obtained
for the had samples using on ten of these samples, rang-
content 24 been measured the proposed LSC method
agreed high as 1700 mg/L. Overall previously obtained
ing as extremely well with those the results obtained
using the GPC method. The data shown LSC method
for the 24 samples using the proposed in Table 9 are
4

the results determined by each method along with the 2

Table 8. 226R uptake from 100 mL simulated ground water matrix.
Table 8.
Table 8.
R uptake from 100 mL simulated ground water matrix.
226
R uptake from 100 mL simulated ground water matrix.
226

Table 9. Comparative results for NWQL water samples using GPC and LSC.
Table 9.
Table 9.
Comparative results for NWQL water samples using GPC and LSC.
Comparative results for NWQL water samples using GPC and LSC.

Application Note – Page 5

5

Figure 4. Comparison of paired results at varying TDS levels: LSC (left)Figure (right).
and GPC 4.
Comparison of paired results at varying TDS levels: LSC (left) and GPC (right).
TDS content are shown in Figure 4. In this figure, the gross (75 mBq/L)can be achieved with a 60 minute count time and a
alpha activity for each the ten which hadby the characterized for
The results for sample measured been two methods References
100mL sample. Process samples (non-environmental) in which
is plotted oncontent are shown in Figure 4. In this figure, the
TDS the y-axis versus the TDS content on the x-axis. the alpha activity is due only to the actinides and not to radium
gross alpha activity for each sample measured by the 1. Horwitz, E.P. et al. (1993). Separation and
Results by the two methods are plotted in pairs: the left-hand can bepreconcentration of actinidesusing 500 mL aliquots. ex-
analyzed by this procedure from acidic media by
two methods is plotted on the y-axis versus the TDS con-
data point in each x-axis. the LSC result; the right-hand dataplot-
tent on the pair is Results by the two methods are Detection limits chromatography. AnalyticaChimica lower, in
traction for these sample sizes would be much Acta.
point in each pairs: the left-hand data point in each pair2is the 281:361-372.
ted in pair is the GPC result. The error bars reflect the range of 15 mBq/L.
sigma total propagatedright-hand data point in each interval).
LSC result; the uncertainty (95% confidence pair is the 2. Burnett, W. and Cable, P. (1995). Determination of ra-
Note that in result.case, the agreement between the total propa-
GPC every The error bars reflect 2 sigma 95% dium-228 in natural waters using extraction chromato-
References resins. Radioactivity & Radiochemistry. Vol 6.
graphic
confidence intervals is excellent and appears interval). Note that
gated uncertainty (95% confidence to be unaffected
by the in everyof dissolvedagreement between the 95% confi-
amount case, the solids in the samples. Also the TPU 1. Horwitz,3:36-44.al. (1993). Separation and preconcentration
No. E.P. et
dence intervals is excellent and appears to be unaffected
of the LSC results is lower in all cases. 3. actinides from et al. (1997). Dipex: A newchromatography.
of Horwitz, E.P. acidic media by extraction extraction chro-
by the amount of dissolved solids in the samples. Also Analytica Chimica Acta. 281:361-372. separation and
matographic material for the
the TPU of the LSC results is lower in all cases. preconcentration of actinides from aqueous solution. Re-
2. Burnett, W. and Cable, Polymers. Determination of
active & Functional P. (1995).
Conclusion
Conclusion
In conclusion, the proposed method for measuring gross alpha
radium-228 in natural waters using extraction
chromatographic resins. Radioactivity & Radiochemistry.
activityIn conclusion,chromatography and liquidmeasuring gross Vol 6. No. 3:36-44.
by extraction the proposed method for scintillation
counting is quick and by extraction chromatography and liquid 3. Horwitz, E.P. et al. (1997). Dipex: A new extraction
alpha activity allows for lower detection limits with
shorterscintillation counting is quick andactinidesfor lower is
count times. The measurement of allows elements de- chromatographic material for the separation and
excellent using 500 mL sample aliquots.times. Themeasurement
tection limits with shorter count Accurate measurement
of actinides elements is excellent using 500 mL sample preconcentration of actinides from aqueous solution.
of alpha activity due to radium requires a sample aliquot of
aliquots. Accurate measurement of alpha activity due to Reactive & Functional Polymers.
100 mL if calcium content is high. A detection limit of 2 pCi/L
radium requires a sample aliquot of 100 mL if calcium
content is high. A detection limit of 2 pCi/L (75 mBq/L)
PerkinElmer, Inc.be achieved with a 60 minute count time and a 100
can
mL sample. Process samples (non-environmental) in
940 Winter Street
Waltham, MA 02451 USA
P: (800) 762-4000 or the alpha activity is due only to the actinides and
which
not to radium can be analyzed by this procedure using
(+1) 203-925-4602
www.perkinelmer.com
500 mL aliquots. Detection limits for these sample sizes
would be much lower, in the range of 15 mBq/L.
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– Application 2011
April
Note

Application Note: Gross Alpha Measurements in Aqueous Samples Using Extraction Chromatography and Liquid Scintillation Counting

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