Purification of americium from assorted analytical wastein hydrochloric acid medium

A. Sengupta • S. K. Thulasidas • V. C. Adya •

P. K. Mohapatra • S. V. Godbole • V. K. Manchanda

Received: 8 November 2011 / Published online: 23 November 2011

� Akademiai Kiado, Budapest, Hungary 2011

Abstract During the simultaneous extraction of plutonium

and uranium using anion exchange chromatographic technique

from analytical waste in hydrochloric acid medium, 241Am

which is invariably present in the plutonium bearing fuel

samples remains in the effluent. A two step separation scheme

was developed for the recovery and purification of Am from the

assorted waste to facilitate the disposal of large volume of

aqueous waste and the purified Am solution was utilized for

spectroscopic investigation. The separation scheme involved

solvent extraction using 0.1 M TODGA ? 0.5 M DHOA for

separation of americium from Fe, Pb, Ni and Na followed by

extraction chromatographic technique using CMPO on inert

support as stationary phase for separation of Ca from Am. A

systematic study on the extraction behavior of Am from

hydrochloric acid medium revealed that out of four extraction

systems well known for actinide partitioning namely 0.1 M

TODGA ? 0.5 M DHOA, 1 M DMDBTDMA, 0.2 M

CMPO ? 1.2 M TBP and 30% TRPO, only 0.1 M TOD-

GA ? 0.5 M DHOA extracts americium from 7.5 M HCl feed

acidity. A comparative study involving CMPO solvent

extraction and column chromatographic technique revealed

that elution of Am from column is satisfactory as compared to

inefficient stripping of Am from organic phase in solvent

extraction technique using 0.1 M HNO3. The purity of the final

solution was checked for 17 elements of interest and was found

to be 98% pure, while the overall recovery of this two step

separation scheme was found to be 95%.

Keywords Americium � TODGA � DHOA � CMPO �DMDBTDMA � TRPO � Analytical waste

Introduction

Due to high specific activity of 241Am, which is invariably

present in plutonium bearing fuel samples, the large volume of

effluent waste generated during the simultaneous extraction of

Pu and U on anion exchange column from analytical waste in

hydrochloric acid medium, could not be disposed off. Am

which is rich in emission spectra was found to interfere during

the analysis of trace constituents in plutonium based fuel

samples by ICP-AES based method involving separation of

Pu using 30% TBP-CCl4 followed by the analysis of raffinate

for trace constituents. 241Am also has wide applications as a

low energy gamma source because of its cost, convenience,

spectral purity and half-life [1, 2]. The major use of 241Am

is in smoke detector alarms and as radiography source [1, 3].

It is also used as a target material for the production of244Cm, 252Cf and higher transuranic elements and is

particularly useful for a wide range of industrial gauging

applications and as source of alpha radiation. 241Am-Be and a

large number of such sources are worldwide used in oil-well

logging operations [1, 3]. Therefore an attempt was made for

the recovery and purification of americium from the assorted

analytical waste to facilitate the disposal of waste and to use

purified americium for spectroscopic and other applications.

In aged Pu samples, the growth of 241Am activity is due to

the decay of 241Pu. Typically about 50 mg of 241Am is gen-

erated from about 1 g of 241Pu per year whose content in Pu

sample depends on the burn-up of the fuel and its storage time.

A. Sengupta (&) � S. K. Thulasidas � V. C. Adya �P. K. Mohapatra � S. V. Godbole

Radiochemistry Division, Bhabha Atomic Research Centre,

Trombay, India

e-mail: arijita@barc.gov.in

V. K. Manchanda

Department of Energy Science, Sungkyunkwan University,

Suwon 440-746, Republic of Korea

123

J Radioanal Nucl Chem (2012) 292:1017–1023

DOI 10.1007/s10967-011-1554-4

Attempts were made for recovery and purification of ameri-

cium from different kinds of waste generated either during

reprocessing of spent fuels or analytical waste generated

during quality control programme [4–6]. Separation of

americium from waste, soil, sediments and bio assay samples

using different extractants involving solvent extraction and

extraction chromatographic techniques followed by its esti-

mation have been reported in literature [7–15]. An overview

on great number of analytical methods for the determination

of 241Am isotope in environmental and nuclear samples

involving alpha and gamma spectrometry; liquid scintillation

technique and mass spectrometry was reported by Vajda et al.

[16]. Earlier we have reported a methodology for separation

and purification of americium from nitric acid medium and its

characterization by instrumental neutron activation analysis

[4, 17]. The present work involved development of an ana-

lytical methodology for purification of 22 mg of americium

from analytical waste in hydrochloric acid medium containing

130 mg of Ca, 32 mg of Pb, 24 mg of Ni, 33 mg of Fe and

133 mg of Na as major constituents. It was observed that to

extract americium from hydrochloric acid medium, 0.1 M

TODGA ? 0.5 M DHOA is effective from 7.5 M feed

acidity. Systematic study revealed that Pb, Ni, Fe and Na can

be separated from americium in hydrochloric acid feed using

solvent extraction with 0.1 M TODGA ? 0.5 M DHOA as

organic phase while Ca can be separated using column chro-

matographic technique with CMPO as stationary phase. The

purity of final americium solution was found to be *98%

while the overall recovery of the two step separation scheme

involving solvent extraction and extraction chromatography

was found to be 95%.

Experimental

Reagents

TODGA and DHOA were synthesized by previously reported

methods and their purities were determined by 1H MR, ele-

mental analysis and distribution coefficient measurements of

Am3? and UO22? respectively [18, 19]. Octylphenyl-N,

N-diisobutyl carbamoylmethyl phosphine oxide (CMPO)

and N,N0-dimethyl-N,N0-dibutyltetradecylmalonamide

(DMDBTDMA) were synthesized by reported method and

their purity was checked by their distribution behaviour

towards Am3? [20–22]. The CMPO loaded resin was pre-

pared by a method reported earlier [22]. Suprapure grade

nitric acid (Merck, Germany) was used throughout this work

and spec pure chemicals were used for making the elemental

standard solutions for ICP-AES analysis. n-dodecane was

procured from Koch-Light Laboratories, USA and Lancas-

ter, UK, respectively. The TBP solution (30% in n-dodecane)

was washed with 5% Na2CO3 to remove acidic impurities.

Methods

Extraction behavior of Am(III) using TODGA, CMPO,

DMDBTDMA and TRPO from hydrochloric acid medium

Since there was no literature available to the best of our

knowledge, to compare the extraction behavior of Am from

hydrochloric acid feed using extractants well known for

actinide partitioning, a systematic study of DAm values

versus the acidity (HCl(M)) of the aqueous feed was car-

ried out using 241Am tracer to optimize the extraction of

americium from hydrochloric acid using four extractants

namely 0.1 M TODGA ? 0.5 M DHOA, 1 M

DMDBTDMA, 0.2 M CMPO ? 1.2 M TBP and 30%

TRPO.

Extraction behavior of Fe(III), Ca(II), Pb(II), Ni(II),

Na(I) from hydrochloric acid medium using TODGA

ICP-AES analysis revealed that Fe, Ca, Pb. Ni and Na are

the major constituents of the waste along with americium.

With the aim of separation of americium from these ele-

ments by means of the extraction of americium in organic

phase leaving the impurities in the raffinate, studies were

carried out to understand the extraction behavior of these

elements from hydrochloric acid medium using 0.1 M

TODGA ? 0.5 M DHOA in dodecane as organic phase

which was found to be the best for extraction of americium

from hydrochloric acid feed. 1mg/mL concentration of

each element was allowed to equilibrate with the organic

phase for 2 h and the raffinate was analyzed for the ele-

ments mentioned above by ICP-AES.

Comparative study of CMPO solvent extraction

and CMPO column extraction

Above study revealed that americium cannot be separated

from calcium using TODGA from hydrochloric acid medium.

To get optimum condition a comparative study between sol-

vent extraction using CMPO as organic phase and column

chromatography using CMPO as stationary phase was carried

out. A feed containing 6.235 mg of Am in 150 mL having

3.5 M HNO3 acidity was equilibrated with equal volume of

organic phase (0.2 M CMPO ? 1.2 M TBP) for 1 h. After

complete phase separation, both the phases were analyzed

radiometrically,

The feed solution containing 6.097 mg of Am, at an acidity

of *3.5 M HNO3 in 115 mL was used for CMPO column

chromatographic extraction experiment. The feed solution

was loaded on the column with a rate of 2–3 drops per minute

after preconditioning with 50 mL of 3.5 M HNO3. The loaded

column was then washed thoroughly using 50 mL of 3.5 M

HNO3, so that the loosely bound or trapped ions were washed

1018 A. Sengupta et al.

123

out leaving Am?3 loaded on the column. Subsequently after

washing, Am3? held on the column was eluted using 0.01 M

HNO3 solution with a flow rate of 2–3 drops per minutes with

50 mL batches and was analyzed radiometrically.

Behavior of Ca(II) through CMPO column

The uptake and extraction behavior of Ca(II) was needed to

be investigated using CMPO column to confirm the com-

plete removal of Ca from the solution of our interest. Using

different concentrations of Ca (184–1,840 lg/mL) with a

feed acidity 3.5 M HNO3, the chromatographic extraction

studies were carried out using CMPO column precondi-

tioned with 25 mL of 3.5 M HNO3. The concentration

range for Ca(II) was chosen such that the concentration of

Ca(II) in the solution of our interest (Ca—867 lg/mL) was

within that range. Effluent, washing solution and eluant

were analyzed for Ca using ICP-AES technique.

Separation of Fe(III), Pb(II), Ni(II)

and Na(I) from americium

Based on the above studies, the waste solution containing

130 mg of Ca, 32 mg of Pb, 24 mg of Ni, 33 mg of Fe and

133 mg of Na as major constituents along with 22 mg of Am

was subjected to solvent extraction using 0.1 M TOD-

GA ? 0.5 M DHOA as organic phase for separation of Fe,

Pb, Ni and Na from Am. Two contacts of organic phase with

a:o =1:1 were used for complete extraction of Am leaving Fe,

Pb, Ni and Na in the raffinate. Subsequently the loaded organic

phase was stripped back using three contacts of pH-2 (0.01 M

HNO3). Mass distribution of americium in different fractions

generated was determined radiometrically while the impurity

analysis was carried out using ICP-AES.

Separation of Ca(II) from americium

CMPO column chromatographic technique using 5 g of TRU-

Spec CMPO resin material with a column (10 9 1 cm) of

10 mL bed volume was used for removal of Ca(II). The

specifications of CMPO column are given in Table 1. The

strip solutions from the TODGA step were mixed together and

the acidity was adjusted to 3 M HNO3 by adding suitable

amounts of supra pure HNO3 acid solution. To avoid break-

through of the column, the feed was divided into two equal

volumes and was passed through the column (which was

preconditioned with 3.5 M HNO3) with a rate of 4–5 drops per

minute. After loading, the column was washed with 5 bed

volumes of 3.5 M HNO3 and subsequently Am was eluted

using 0.01 M of HNO3 solution. Mass distribution of ameri-

cium was determined using radiometry while ICP-AES was

used for determination of impurities in the different fractions

obtained during the step.

Instruments

Radiometric estimation was used for determination of

americium in different fractions using 300 9 300 NaI (Tl)

well type scintillator detector. A suitable aliquot of each

sample was counted for sufficient time to get around

10,000 counts to restrict statistical counting error.

Impurity analyses were carried out using JY-Ultima

high resolution ICP-AES having practical resolution of

\0.005nm and has a continuous coverage of spectral range

200–800 nm. The specifications and working conditions of

the spectrometer are summarized in Table 2.

Results and discussions

Extraction behavior of Am(III) using TODGA, CMPO,

DMDBTDMA and TRPO from hydrochloric acid

medium

Figure 1 represents the extraction profiles of americium using

four promising extractants known for actinide partitioning

Table 1 Specification of CMPO extraction chromatography column

Parameters Specifications

Stationary phase 0.2 M CMPO ? 1.2 M TBP

Supported materials Chromosorb W

Mesh size (micron) 100–150

Amounts of resin in the column 5 g

Column length 10 cm

Bed volume 10 mL

Table 2 Specifications and operating conditions of JY-ULTIMA-

HR-ICP-AES

Optical design 1 M Czerny Turner

Grating Holographic, ion etched optical grating

Groove density 2,400 grooves/mm

Grating size 110 9 110 mm

Wave length range 120–800 nm

Band pass 0.0023 nm from 120–340 nm

0.0046 nm from 340–800 nm

Thermal regulation Controlled to 30±1 �C

RF generator

Frequency 40.68 MHz

Oscillator 27.12 MHz

Pump Dual channel (12 roller)

Nebulizer Pneumatic concentric

Operating condition

Ar plasma flow 13 L/min

Integration time 10 s

Reflected power \10 W

Sample flow rate 1 mL/min

Purification of americium from assorted 1019

123

(TODGA, CMPO, DMDBTDMA and TRPO) at various

hydrochloric feed acidity. It was found that there was practi-

cally no extraction of americium from hydrochloric acid

medium using 30% TRPO in dodecane throughout the

observed acidity range. The similar observation was found to

be true in case of 1 M DMDBTDMA in dodecane system also

while a steady increase in DAm was found beyond 6 M HCl in

case of 0.2 M CMPO ? 1.2 M TBP system. In case of 0.1 M

TODGA ? 0.5 M DHOA in dodecane system it was

observed that there was a steady increase in DAm up to 7 M

feed acidity and subsequently it attained a maxima with

DAm = 23 (% extraction = 95 with A:O = 1:1) followed by

decrease in DAm value. It was found that for effective

extraction of americium from hydrochloric acid medium

0.1 M TODGA ? 0.5 M DHOA in dodecane as organic

phase and 7.5 M feed acidity is required.

Extraction behavior of Fe(III), Ca(II), Pb(II), Ni(II),

Na(I) from hydrochloric acid medium using TODGA

On the basis of above study TODGA was found to extract

americium from HCl medium. With the aim to extract amer-

icium leaving behind the impurities in the raffinate, a sys-

tematic study was carried out to understand the extraction

behavior of the major constituents of the waste using TODGA

at varying HCl feed acidity (Fig. 2). It was found that there

was practically no extraction of Na, Fe, Ni and Pb throughout

the acidity range while in case of Ca, there was a sharp

increase in DCa value up to 6 M HCl and subsequently after

obtaining a maxima, decrease in DCa value was observed. The

extraction profile of Ca suggested that at 7.5 M feed acidity

*70% Ca would be coextracted along with americium. The

study revealed that, though 0.1 M TODGA ? 0.5 M DHOA

in dodecane system was found to effective for separation of

americium from Na, Fe, Ni and Pb, additional separation step

was necessary for separation of Ca.

Comparative study of CMPO solvent extraction

and CMPO column extraction

With the aim of extraction of americium from Ca, a

comparative study involving solvent extraction and

extraction chromatographic technique using CMPO as

extractant was carried out which suggested that 91% of the

feed (*5.5 mg of Am) was extracted in the organic phase

after one contact. Subsequently the loaded organic phase

was back extracted using pH *2 solution with A:O = 2:1.

Radiometric determination revealed that after one contact,

only 28% of the loaded Am could be stripped back sug-

gesting pH *2 solution is not effective for back extraction

of loaded americium. However, 0.4 M formic

acid ? 0.4 M hydrazine hydrate ? 0.1 M citric acid mix-

ture was effective for quantitative back extraction of Am.

Since the tubing of ICP-AES instrument was made up of

organic polymer, stripping of Am using organic complex-

ing agents does not conform to ICP-AES analysis. Am

distribution in different fractions is summarized in Table 3.

In case of extraction chromatographic technique, major

amount of the loaded Am was eluted in the first fraction.

*57% of the feed Am i.e. 3.505 mg was eluted in first

50 mL fraction. In other three fractions the amounts of Am

eluted out were 18.5, 6, 4 lg respectively in each 50 mL

0 1 2 3 4 5 6 7 8 9 10

0

5

10

15

20

25

DA

m

HCl(M)

30% TRPO

0.1M TODGA+0.5M DHOA

0.2M CMPO+1.2M TBP

1M DMDBTDMA

Fig. 1 Extraction behavior of Am(III) using TODGA, CMPO,

DMDBTDMA and TRPO from hydrochloric acid medium

2 4 6 8 10

0.01

0.1

1

10

D

HCl (M)

Ca

Na

Ni

Fe

Pb

Fig. 2 Extraction behavior of Ca(III), Fe(II), Ni(II), Na(I), Pb(II)

using 0.1 M TODGA ? 0.5 M DHOA from hydrochloric acid

medium

1020 A. Sengupta et al.

123

(Table 4). The amount of Am present in the fourth fraction

indicated that almost all loaded Am was eluted out in four

fractions. From this comparative study it can be concluded

that CMPO column with proper capacity could be used for

Am3? uptake and quantitative elution by 0.01 M HNO3.

Behavior of Ca(II) through CMPO column

With the aim of loading americium on the CMPO column

leaving Ca in the effluent, behavior of Ca through CMPO

column was studied. These studies revealed that in the

above concentration range Ca(II) was not held on CMPO

column and the effluent was found to contain major amount

of Ca. There was some amount of Ca which was trapped in

the column bed but it could subsequently be washed out

using five bed volumes of 3.5 M HNO3 solution (Table 5).

These experiments suggested that CMPO column is

effective for separation of Ca from americium.

Purification of americium from the waste

On the basis of above preliminary studies, two contacts of

0.1 M TODGA ? 0.5 M DHOA in dodecane with

A:O = 1:1 were given to the waste solution whose feed

was adjusted to 7.5 M HCl for quantitative separation of

americium from Pb, Ni, Na and Fe. The organic phase

which was loaded with americium along with Ca was

subsequently stripped by three contacts of 0.01 M HNO3.

82% of americium was stripped in first contact while the

overall recovery of this separation step was found to be

more than 99%. The decontamination factors for Pb, Ni, Fe

and Na were found to be 640000, 480000, 660000 and

2660000 respectively while that of Ca was found to be 1.1.

All the strip solutions were mixed together and the acidity

was adjusted to 3.5 M HNO3 for making proper feed of

CMPO column chromatographic extraction. Mass distri-

bution of americium at various fractions generated in this

step is summarized in Table 6.

To avoid the breakthrough of the column, the separated

solution was divided into two equal volumes and loaded on

the CMPO column maintaining the flow rate mentioned

earlier. Americium was found to be quantitatively held on

the column as suggested by the radiometric estimation of

americium in the raffinate. The loaded column was sub-

sequently washed thoroughly with 50 mL of 3.5 M HNO3

followed by elution with 0.01 M HNO3 in three batches of

total 150 mL volume. The first fraction was found to

contain 99% of americium while quantitative elution was

confirmed by estimation of americium in the third fraction.

Similar process was followed for the second feed for

CMPO extraction after preconditioning the column with

3.5 M HNO3. Table 7 represents the mass distribution of

americium at different fractions generated in CMPO step.

The overall recovery of this step was found to be 98%

while the decontamination factor for Ca was 24,00,000.

ICP-AES was employed for determination of impurity in

the solutions generated after each separation step with 10%

RSD (Table 8). The purity of the final purified americium

solution was checked for the analytes of interest using the

interference free analytical channels identified in our previous

Table 3 Am distribution in different fractions generated during

CMPO solvent extraction

Fractions Amount of

Am (mg)

Volume

(mL)

%

Recovery

Feed for CMPO solvent

extraction (aqueous phase

acidity 3.5 M HNO3)

6.235 150 –

Aq. phase after extraction 0.565 150 9

Org. phase after stripping 3.812 150 61

Strip solution (pH 2) 1.610 300 26

Table 4 Extraction and elution behavior of Am(III) using

TRU-SPEC� CMPO column

Fractions Amount of

Am (mg)

Volume

(mL)

% Recovery

Feed for CMPO column 6.0972 115 –

Effluent 0.976 115 16

Washing solution 1.525 50 25

Eluant-1 3.505 50 58

Eluant-2 0.019 50 0.3

Eluant-3 0.006 50 0.1

Eluant-4 0.004 50 0.06

Table 5 Extraction behavior of Ca(II) using CMPO column

Fractions

(lg/mL)

Preconditioning

(lg/mL)

Effluent

(lg/mL)

Washing

solution

(lg/mL)

Eluant

(lg/mL)

184 BDL 170 11.90 BDL

368 BDL 341 24.90 BDL

920 BDL 846 59.25 BDL

1840 BDL 1727 142.50 BDL

Table 6 Mass distributions of Am(III) at different fractions gener-

ated during TODGA-DHOA extraction in HCl medium

Fractions Volume (mL) Am(mg) % Recovery

Am stock 150 22.7 ± 0.7 –

Loaded TODGA 300 22.6 ± 0.6 99.56

Depleted aqueous 150 0.04 ± 0.001 0.17

Strip 1 50 18.6 ± 0.2 81.94

Strip 2 50 3.2 ± 0.3 14.10

Strip 3 50 0.87 ± 0.09 3.80

Purification of americium from assorted 1021

123

study [23]. The final solution was found to be 98% pure as

mentioned in Table 9 while the overall recovery of this two

step separation scheme was found to be 95%.

Conclusions

In conclusion it can be highlighted that a two step sepa-

ration scheme involving solvent extraction and extraction

chromatography was developed for purification of milli-

gram quantities of americium from the analytical waste in

hydrochloric acid medium containing Ca, Fe, Na, Ni, Pb as

major constituents (Fig. 3). TODGA was used for separa-

tion of americium from Pb, Ni, Fe and Na with decon-

tamination factors 640000, 480000, 660000 and 2660000

respectively while Ca can be separated using CMPO col-

umn chromatography with D.F. 2400000. The final solu-

tion was found to be 98% pure with respect to 17 analytes

of interest while the overall recovery of these two step

separation scheme was 95%. This work is optimization and

demonstration of the methodology for purification of mil-

ligram amounts of americium from assorted waste in

hydrochloric acid medium.

Table 7 Mass distribution of Am(III) in different fractions generated during CMPO step

Fractions Part-1 % Recovery Part-2 % Recovery

Am Volume (mL) Am Volume (mL)

Feed for CMPO 10.9 ± 0.7 100 – 11.0 ± 0.7 100 –

Effluent 0.08 ± 0.005 lg 100 0.73 0.03 ± 0.005 lg 100 0.27

Washing 0.04 ± 0.005 lg 50 0.37 0.03 ± 0.004 lg 50 0.27

Eluant-1 10.8 ± 0.4 mg 50 99.08 10.7 ± 0.6 mg 50 97.27

Eluant-2 8 ± 0.6 lg 50 0.07 5 ± 0.4 lg 50 0.04

Eluant-3 BDL 50 – BDL 50 –

Table 8 ICP-AES analysis of different fractions generated during

Am purification from HCl medium

Elements Am-stock

(mg)

TODGA strip

(mg)

CMPO eluant

(mg)

Ca 130 ± 5 120 ± 5 BDL

Pb 32 ± 3 BDL BDL

Ni 24 ± 2 BDL BDL

Fe 33 ± 3 BDL BDL

Na 133 ± 3 BDL BDL

Table 9 Determination of trace

elements in purified Am (Am—

100 lg/mL) by ICP-AES

Elements Conc in Am

matrix (lg/mL)

Eu \0.05

Dy \0.05

Gd 2

Sm \0.05

Fe \0.05

Ca \0.05

Na \0.05

Cr \0.05

Ag \0.05

Al \0.05

Co \0.05

Mn \0.05

Mg \0.05

Ni \0.05

Cd \0.05

Zn \0.05

Cu \0.05

Analytical waste (Am, Fe, Pb, Ni, Na, Ca)

7.5M HCl feed

Separation of Fe, Pb, Ni and Na from americium:

1. Extraction with 0.1M TODGA + 0.5M DHOA from 7.5M HCl 2. Stripping with 0.01M HNO3

Separation of Ca from americium:

1. Feed was adjusted to 3.5M HNO3 and loaded on CMPO column 2. After washing with 5 bed volumes of 3.5M HNO3, elution with

0.01M HNO3

Purified americium solution

Purity – 98%, Overall recovery – 95%

Fig. 3 Proposed flow sheet of purification of americium from

analytical waste in hydrochloric acid medium

1022 A. Sengupta et al.

123

References

1. Katzz JJ, Seaborg GT, Mross LR (1986) The chemistry of the

actinide elements, vol 2, 2nd edn. Chapman and Hall, New York,

pp 1188–1190

2. Knoll GF (2000) Radiation detection and measurements, 3rd edn.

John Wiley and Sons Inc, New York

3. http://www. Epa. Gov/radiation/source- management/final_sealed-

source- alts. Pdf

4. Sengupta A, Adya VC, Mohapatra PK, Godbole SV, Manchanda

VK (2010) Separation and purification of americium from ana-

lytical waste solutions. J Radioanal Nucl Chem 283:777–783

5. Mathur JN, Murali MS, Natarajan PR, Badheka LP, Banerji A,

Micheal KM, Kapoor SC, Dhuwad RK (1992) Tail end purifi-

cation of americium from plutonium loading effluents using a

mixture of octyl (phenyl)-N,N-diisobutyl carbamoyl phosphine

oxide and tri-N-butyl phosphate. J Radioanal Nucl Chem

165(4):219–227

6. Schulte LD, FitzPatrick JF, Salazar RR, Schake BS, Martinez BT

(1995) Clean-up of hydrochloric acid waste streams from actinide

processing using extraction chromatography. Sep Sci Technol

30(7–9):1833–1847

7. Micheal KM, Kapoor SC, Mathur JN, Iyer RH (1996) Purification

of americium from bulk quantities of plutonium loading effluent

using triauryl amine. J Radioanal Nucl Chem 213:431–439

8. Muscatello AC, Navratil JD (1988) Americium removal from

nitric acid waste streams. J. Radioanal. Nucl. Chem.lett.

128:449–462

9. Michel H, Barci-Funel G, Dalmasso J, Ardisson G (1999) One

step ion exchange process for radiochemical separation of

americium plutonium and neptunium in sediments. J Radioanal

Nucl Chem 240:467–470

10. Michel H, Levent D, Barci V, Barci-Funel G, Hurel C (2008) Soil

and sediment sample analysis for determination of natural and

anthropogenic radionuclides. Talanta 74:1527–1533

11. Tavcar P, Jakopic R, Benedik L (2005) Sequential determination

of 241Am, 237Np, Pu radioisotopes and 90Sr in soil and sediment

samples. Acta Chim solv 52:60–66

12. Moreno J, Vajda N, Danesi PR, Larosa JJ, Zeiller E, Sinojmery M

(1997) Combined procedure for the determination of 90Sr, 241Am

and Pu radionuclides in soil samples. J Radioanal Nucl Chem

226:279–284

13. Wang JJ, Chen IJ, Chiu JH (2004) Sequential isotopic determi-

nation of plutonium, thorium, americium, strontium and uranium

in environmental and bio assay samples. Appl Radiat Isotop

61:299–305

14. Lee YK, Bakhtiar SN, Akbarzadeh M, Lee JS (2000) Sequential

isotopic determination of strontium thorium, plutonium, pranium

and americium in bioassay samples. J Radioanal Nucl Chem

243:525–533

15. Adya VC, Sengupta A, Dhawale BA, Rajeswari B, Thulasida SK,

Godbole SV (2011) Recovery of americium from analytical solid

waste containing large amounts of uranium, plutonium and silver.

J Radioanal Nucl Chem 11:44. doi:10.1007/s10967-011-1360-z

16. Vajda N, Chang-Kyu Kim (2010) Determination of 241Am iso-

tope: a review of analytical methodology. J Radioanal Nucl Chem

284:341–366

17. Sengupta A, Adya V, Acharya R, Mohapatra P, Manchanda V

(2011) J Radioanal Nucl Chem 267:281–285. doi:10.1007/

s10967-010-0675-5

18. Ansari SN, Pathak PN, Husain M, Prasad AK, Parmar VS,

Manchanda VK (2005) N,N,N0,N0 tetraoctyl diglycolamide

(TODGA): a promising extractant for actinide partitioning from

high level waste (HLW). Solv Extr Ion Exch 23:463–479

19. Gupta KK, Manchanda VK, Subramanian MS, Singh RK (2000)

Solvent extraction studies on U (VI), Pu(IV) and fission products

using N,N dihexyl octanamide. Solv Extr Ion Exch 18:273–286

20. Schulz WW, Horwitz EP (1988) TRUEX process and manage-

ment of liquid TRU waste. Sep Sci Technol 23:1191–1210

21. Mahajan GR, Prabhu DR, Manchanda VK, Badheka LP (1998)

Substituted malonamides as extractants for partitioning of actin-

ides from nuclear waste solutions. Waste Manage 18:125–133

22. Nair GM, Prabhu DR, Mahajan GR, Shukla JP (1993) Tetra-butyl

and tetra-isobutyl malonamides as extractants for U(VI) and

Pu(IV). Solv Extr Ion Exch 11:831–847

23. Mathur JN, Murali MS, Natarajan PR, Badheka LP, Banerji A,

Ramanujam A, Dhami PS, Gopalakrishnan V, Dhumwad RK,

Rao MK (1993) Partitioning of actinides from high-level waste

streams of PUREX process using mixtures of CMPO and TBP in

dodecane. Waste Manage 13:317–325

Purification of americium from assorted 1023

123