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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 />

IV.C.4. Glass-ceramic Waste Form <strong>for</strong> the High-level Waste<br />

from Pyrometallurgical Reprocessing of Nuclear Fuels<br />

The high-level radioactive<br />

waste (HLW) generated from<br />

pyrometallurgical reprocessing<br />

of irradiated nuclear fuels in<br />

molten LiCl-KCl media cannot<br />

be immobilized in the<br />

conventional borosilicate glass,<br />

as chlorides have very poor<br />

solubility in glass.<br />

Immobilization of the chloride<br />

waste in a glass-ceramic such<br />

as glass-bonded sodalite, has<br />

emerged as a promising option.<br />

Sodalite is a naturally occurring<br />

mineral, and the glass-ceramic<br />

waste <strong>for</strong>m based on it is<br />

considered suitable <strong>for</strong> disposal<br />

in geological repositories. The<br />

waste <strong>for</strong>m fabrication involves<br />

the occlusion and/or ion<br />

exchange of the radioactive<br />

waste on to a zeolite, tailoring<br />

with a glass binder, and<br />

subsequent conversion to the<br />

glass-ceramic. The preparation<br />

and characterization of such a<br />

waste <strong>for</strong>m using a simulated<br />

waste composition have been<br />

investigated.<br />

Dehydrated Zeolite 4A was<br />

homogenized with simulated<br />

chloride HLW of a<br />

representative reference<br />

composition (2 wt% CsCl, 2<br />

wt% BaCl 2 , 9 wt% NdCl 3 and<br />

the rest LiCl - KCl eutectic) in<br />

an inert atmosphere glove box,<br />

and the mixture was<br />

equilibrated at 848 K <strong>for</strong> 100h<br />

in static argon. The salt-loaded<br />

zeolite (SLZ) was washed with<br />

water, and the eluate analyzed<br />

by atomic absorption<br />

spectrometry in order to<br />

ascertain the extent of salt<br />

uptake in the zeolite matrix. The<br />

SLZ was then converted to<br />

glass-bonded sodalite<br />

[Na 8 (AlSiO 4 )6Cl 2 ] by blending<br />

it with 25wt % of a specially<br />

prepared boroaluminosilicate<br />

glass, pelletizing and heating at<br />

1188 K <strong>for</strong> 15h in flowing<br />

argon. By this procedure,<br />

several batches were prepared<br />

by varying experimental<br />

S<br />

N<br />

N<br />

S<br />

N<br />

N<br />

S<br />

N<br />

parameters such as the zeoliteto-salt<br />

ratio. X-ray<br />

diffractograms of the final<br />

waste <strong>for</strong>m showed sodalite as<br />

the major phase and nepheline<br />

as a minor phase (Fig.1). SEM<br />

micrograph of the product<br />

showed a uni<strong>for</strong>m<br />

microstructure (Fig. 2).<br />

Thermophysical properties<br />

like thermal expansion and<br />

glass transition temperature of<br />

the glass-ceramic were studied<br />

by high-temperature XRD and<br />

differential<br />

scanning<br />

calorimetry, respectively. The<br />

variation of the lattice<br />

parameter with temperature<br />

was found to be similar to that<br />

S<br />

2Theta Cu K α<br />

S : Sodalite<br />

N : Nepheline<br />

Fig.1 Powder XRD pattern of the glass-bonded sodalite<br />

N<br />

FUEL CYCLE 109

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