Behaviour of radioactive iodide and bromide ions from aqueous solution on ion exchange resins Amberlite IRA-400

doi:10.4236/ns.2009.13025

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Vol.1, No.3, 191-194 (2009)

doi:10.4236/ns.2009.13025

SciRes

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

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

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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