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Initial Investigation Into the Vitrification of High Molybdenum Solids in Borosilicate Glass

Published online by Cambridge University Press:  15 February 2011

Barbara F. Dunnett ,
Nick R. Gribble ,
Andrew D. Riley  and
Carl J. Steele
Barbara F. Dunnett
Affiliation:
National Nuclear Laboratory, Sellafield, Seascale, Cumbria, CA20 1PG, U.K.
Nick R. Gribble
Affiliation:
National Nuclear Laboratory, Sellafield, Seascale, Cumbria, CA20 1PG, U.K.
Andrew D. Riley
Affiliation:
Sellafield Ltd., Seascale, Cumbria, CA20 1PG, U.K.
Carl J. Steele
Affiliation:
Sellafield Ltd., Seascale, Cumbria, CA20 1PG, U.K.
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Abstract

Sellafield Ltd operates a Waste Vitrification Plant (WVP) to immobilise the arisings from the reprocessing of spent nuclear fuel. Washout of solids from the base of waste storage tanks in preparation for decommissioning is likely to produce feeds enriched in molybdenum to the WVP. Vitrification of such feeds in the borosilicate glass formulation currently used by the WVP for vitrification of reprocessing waste has been investigated to determine the maximum achievable loading of MoO3.

The vitrification of molybdenum in the absence and presence of reprocessing waste was studied. A number of glasses were manufactured in the laboratory containing various waste loadings. The resultant glasses were examined both visually and under the scanning electron microscope for the presence of any phase separation. Additional aluminium was added to the glasses manufactured in the absence of reprocessing waste to improve the durability of the glass. In borosilicate glass containing 3.5 wt% Al2O3 the onset of a molybdenum phase separation was observed in glasses containing 2.6 wt% MoO3. In the presence of Magnox reprocessing waste, phase separation was observed when the product contained >3.8 wt% MoO3. Soxhlet durability testing of a selection of the glasses manufactured was carried out. The Soxhlet durability of glasses in the absence of phase separation was good.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 1193: Scientific Basis for Nuclear Waste Management XXXIII , 2009 , 291
Copyright
Copyright © Materials Research Society 2009

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