Vol.1, No.3, 191-194 (2009)
doi:10.4236/ns.2009.13025
SciRes
Copyright © 2009 Openly accessible at http://www.scirp.org/journal/NS/
Natural Science
Behaviour of radioactive iodide and bromide ions from
aqueous solution on ion exchange resins Amberlite
IRA-400
Pravin Singare1*, Ram Lokhande2
1Department of Chemistry, Bhavans College, Mumbai, India
2Department of Chemistry, University of Mumbai, Mumbai, India
Received 15 June 2009; revised 2 July 2009; accepted 5 July 2009.
ABSTRACT
The ion exchange resin Amberlite IRA-400 in
iodide and bromide form where equilibrated
separately with the respective labeled iodide
and bromide ion solution of different concen-
trations varying from 0.005M to 0.100M in the
temperature range of 32.0 ºC to 48.0 ºC. The dis-
tribution coefficient Kd values calculated for
iodide and bromide ion exchange increases
with rise in ionic concentration of the external
solution, however with rise in temperature the
Kd values calculated where found to decrease.
Also the Kd values calculated where higher for
iodide exchange than bromide exchange.
Among the different alternative techniques
available for obtaining the Kd values, the radio-
active tracer technique used in the present ex-
perimental work offers high detection sensitivity.
It is expected that the distribution coefficient
data obtained from such experimental work will
significant in environmental impact assessment
on the disposal of radioactive waste.
Keywords: Ion Exchange Resin; Amberlite
IRA-400; Distribution Coefficient; Temperature
Effect; Concentration Effect; 131 I; 82 Br; Radioactive
Tracer Isotope
1. INTRODUCTION
There are number of liquid processes and waste streams
at nuclear power plants, fuel reprocessing plants and
nuclear research centers that require treatment for re-
moval of radioactive contaminants. One of the most
common treatment methods for such aqueous streams is
the use of ion exchange, which is a well developed tech-
nique that has been employed for many years in nuclear
industries [1,2]. The ion exchange process is very effec-
tive at transferring the radioactive content of a large
volume of liquid into a small volume of solid. Efforts to
develop new ion exchangers for specific applications are
continuing. In spite of their advanced stage of develop-
ment, various aspects of ion exchange technologies have
been continuously studied to improve the efficiency and
economy of their application in radioactive waste man-
agement. The selection of an appropriate ion exchange
material for the liquid radioactive waste treatment is
possible on the basis of information provided by the
manufacturer. However since the selection of the appro-
priate ion exchange material depends on the needs of the
system, it is expected that the data obtained from the
actual experimental trials will prove to be more helpful.
Generally the selected ion exchange materials must be
compatible with the chemical nature of the radioactive
liquid waste such type and concentration of ionic species
present as well as the operating parameters notably tem-
perature. Also while designing an ion exchange process-
ing system it is desirable to have an adequate knowledge
of the distribution coefficient values of the ion exchange
resin towards different ions present in radioactive liquid
waste. These distribution coefficients are very important
parameter for environmental impact assessment on the
disposal of radioactive waste arising from research in-
stitutes [3].
Although there are different alternative methods
available to know the distribution coefficient values, but
radioactive isotopic technique is expected to be the most
appropriate method as it offer several advantages such as
high detection sensitivity, capability of in-situ detection,
and physico-chemical compatibility with the material
under study [4-8]. Attempts where made by the previous
researchers to study the concentration and temperature
effect on cation exchange systems for computing the
distribution coefficient values [9-15]. However very
little work was done to study the distribution coefficient
values in anion exchange systems [16]. Therefore, in the
present investigation, attempts where made to study the
effect of external ionic concentration and temperature on
P. Singare et al. / Natural Science 1 (2009) 191-194
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192
distribution coefficient, for which radioactive tracer
technique was used.
2. EXPERIMENTAL
Ion exchange resin Amberlite IRA-400 (by Rohm and
Haas Company, USA), was a strongly basic anion ex-
change resin in chloride form. The resins where con-
verted in iodide and bromide form by eluting with 10 %
KI and KBr solution in a conditioning column. The
1.000 g (m) of conditioned resins in iodide and bromide
form was equilibrated separately with labeled 250 mL (V)
of 0.005 M iodide and bromide ion solution respectively
under continuous and uniform mechanical stirring. The
solution was uniformly stirred using the mechanical
stirrer for 3h at a constant temperature of 32.0 0C so as
to attain equilibrium.
The ion exchange reaction taking place can be repre-
sented as follows:
R-I + I*- (aq.) R-I* + I- (aq.) (1)
R-Br + Br*- (aq.) R-Br* + Br- (aq.) (2)
where I*- (aq.) and Br*- (aq.) represent aqueous solution of
iodide and bromide labeled with radioactive isotope 131 I
and 82 Br respectively.
The initial activity (Ai) and final activity (Af) in counts
per minutes (c.p.m.) of the labeled solutions was meas-
ured on γ-ray spectrometer having Na (I) Tl scintillation
detector. From the knowledge of Ai and Af, the Kd value
was calculated by the equation
Kd = [(Ai - Af) / Af ] x V / m (3)
The experimental sets where repeated in the same
manner by increasing the ionic concentrations up to
0.100 M and the temperature varying up to 48.0 0 C. The
Kd values for different sets where calculated by Eq.3.
The 82 Br isotope used was an aqueous solution of
ammonium bromide in dilute ammonium hydroxide hav-
ing activity 5mCi, γ- energy 0.55 MeV, and t1/2 36h. The
131 I isotope used was an aqueous solution of sodium
iodide in dilute sodium sulfite, having activity 5mCi, γ-
energy 0.36 MeV, and t1/2 8.04d [17].
3. RESULTS AND DISCUSSIONS
In the present research work the ion exchange resin in
iodide and bromide form where equilibrated for 3 h with
labeled iodide and bromide ion solution respectively of
known initial activity. From the results of previous work
[4-8,18-24]; it was observed that this time duration was
sufficient to attain equilibrium. Due to ion isotopic ex-
change reactions taking place the activity of the solution
decreases with time. The decrease in activity of the solu
Figure 1. Variation of distribution coefficient with ionic
concentration and temperature.
Table 1. Effect of ionic concentration on distribution coeffi-
cients. Temperature = 32.0 0C, amount of resin= 1.000 g, vol-
ume of solution = 250 mL.
Log Kd Concentration
(M)
Iodide ions Bromide ions
0.005 3.58 3.08
0.010 3.97 3.23
0.020 4.25 3.55
0.100 4.50 3.80
Table 2. Effect of temperature on distribution coefficients.
Concentration of labeled ionic solution = 0.005M, amount of
resin= 1.000 g, volume of solution = 250 mL.
tion was measured after 3h which represent the final
activity exchanged on the resin. From the knowledge of
initial and final activity, the Kd values where calculated
by Eq.3 to study the effect of temperature and concen-
tration. Heumann et al. [16] in the study of chloride dis-
tribution coefficient on strongly basic anion-exchange
resin observed that the selectivity coefficient between
halide ions increases at higher electrolyte concentrations.
Adachi et al. [9] observed that the swelling pressure of
Log Kd Temperature
0 C
Iodide ions Bromide ions
32.0 3.58 3.08
43.0 3.23 2.85
48.0 2.99 2.76
P. Singare et al. / Natural Science 1 (2009) 191-194
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193
the resin decreased at higher solute concentrations re-
sulting in larger distribution coefficient values. The tem-
perature dependence of the distribution coefficient on
cation exchange resin was studied by Shuji et al. [11],
they observed that the distribution coefficients increased
with decreasing temperature. The present experimental
results also indicates that the distribution coefficient Kd
values calculated for iodide and bromide ions increases
with increase in ionic concentration of the external solu-
tion (Table 1), however with rise in temperature the Kd
values calculated where found to decrease (Table 2).
Also the Kd values calculated where higher for iodide
ions as compared to that for bromide ions (Tables 1 and
2). The variation of Kd values for iodide and bromide
ions with temperature and concentration of external
ionic solution is graphically represented in Figure 1.
4. CONCLUSIONS
In heavy metal removal processes the rate of removal is
considered to be important factor from the practical as-
pect of reactor design and process optimization [25].
Earlier research was performed demonstrating the feasi-
bility of using the bioresin in a continuous system for
decontaminating pool water of 60 Co [26]. It is important
here to note that in all the above decontamination proc-
esses, distribution coefficient Kd values plays a very
prominent role in deciding about proper selection of
resins. The work carried out in the present experiment is
a demonstration showing application of radioactive ac-
tive tracer technique to study the parameters affecting
the distribution coefficient. The same technique can be
extended further to study the Kd values of different ion
exchange resins for various ions in liquid radioactive
waste. The data base so obtained on Kd value will serve
as a very important parameter for environmental impact
assessment on the disposal of radioactive waste [3].
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