IGCAR : Annual Report - Indira Gandhi Centre for Atomic Research
IGCAR : Annual Report - Indira Gandhi Centre for Atomic Research
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