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IGCAR : Annual Report - Indira Gandhi Centre for Atomic Research

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IGC<br />

<strong>Annual</strong> <strong>Report</strong> 2007<br />

Fig.1 Variation of D Pu(IV) with nitric<br />

acid concentration.<br />

after washing the column, it<br />

was eluted with 0.5 M nitric<br />

acid. It is seen from Fig.2 that<br />

<strong>for</strong> 4% PVP resin, about 99.8%<br />

of the loaded plutonium could<br />

be eluted within 3 bed volumes,<br />

whereas <strong>for</strong> 8% PVP about 93%<br />

of plutonium could be eluted.<br />

The 12% resin shows a poor<br />

and incomplete elution pattern;<br />

only 86% of plutonium could<br />

be eluted within 5 bed volumes.<br />

Under similar conditions Dowex<br />

1X4 also exhibits poor and<br />

incomplete elution pattern.<br />

Even after 6 bed volumes only<br />

about 66% of the loaded Pu<br />

could be eluted.<br />

Fig.2 Elution profile of PVP resins<br />

and Dowex 1X4.<br />

Radiation degradation<br />

The resins were irradiated in a<br />

Co-60 gamma chamber in<br />

presence of 8 M nitric acid,<br />

after which the resins were<br />

analysed <strong>for</strong> capacity, moisture<br />

content and Pu distribution<br />

ratios. All the resins were<br />

irradiated up to 200 MRad of<br />

total absorbed dose. As<br />

expected, <strong>for</strong> all the resins the<br />

D Pu(IV) decreased with the<br />

increase in dose. The value of<br />

D Pu(IV)<br />

of 200 MRad irradiated<br />

8% PVP resin was nearly<br />

identical to that of 100 MRad<br />

irradiated Dowex 1X4. At 200<br />

MRad of total cumulative dose,<br />

PVP resin shows little damage<br />

in the <strong>for</strong>m of dimples over<br />

bead surface (Fig.3) but it takes<br />

up plutonium over a range of<br />

nitric acid concentration,<br />

whereas Dowex 1X4 was<br />

completely degraded. As the<br />

total absorbed dose increases,<br />

the strong-base capacity of the<br />

resin decreases, indicating the<br />

deterioration of functional<br />

group (i.e. methyl group) upon<br />

irradiation. The deterioration of<br />

the polymer matrix upon<br />

irradiation is also manifested in<br />

the increase in moisture content<br />

of the irradiated resin and<br />

increase in volume of resin.<br />

Palladium recovery<br />

Palladium is a precious metal<br />

with good catalytic, corrosion<br />

and oxidation resistant<br />

properties, which have resulted<br />

in its widespread use in<br />

different industries. The natural<br />

abundance of palladium is very<br />

low and thus, there is an<br />

incentive in recovering<br />

palladium from the high level<br />

Fig.3 SEM images of unirradiated and<br />

200 MRad irradiated 8% PVP resin.<br />

waste generated in Fast Reactor<br />

Fuel Reprocessing. At <strong>IGCAR</strong>,<br />

we have developed a method<br />

<strong>for</strong> the recovery of palladium<br />

from nitric acid medium. We<br />

have used 8% PVP resin <strong>for</strong> the<br />

recovery of palladium from 2 M<br />

and 4 M nitric acid medium. In<br />

a small column of 7.2 ml about<br />

1000 ml of solution containing<br />

210 ppm of palladium was<br />

passed and it was observed that<br />

even the last 200 ml of effluent<br />

contains less than 2 ppm of<br />

palladium. Similar results were<br />

obtained when 400 ml of<br />

solution containing 800 ppm of<br />

palladium was passed.<br />

Palladium was eluted with 0.5M<br />

thiourea in 0.1M HNO3 and<br />

95% of loaded palladium was<br />

eluted in four-bed volume of<br />

column. When the solution<br />

containing palladium,<br />

ruthenium and rhodium were<br />

passed through the column<br />

only palladium was loaded.<br />

The above studies indicate<br />

that 4-vinylpyridine resins can<br />

be used <strong>for</strong> recovery and<br />

purification of plutonium as<br />

well as <strong>for</strong> the recovery of<br />

palladium from radioactive<br />

waste solutions.<br />

84 FUEL CYCLE

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