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Characterization of Highly Waste Loaded Glass for HLW

Published online by Cambridge University Press:  15 February 2011

Kazuhiro Kawamura  and
Jin Ohuchi
Kazuhiro Kawamura
Affiliation:
Power Reactor and Nuclear Fuel Development Corporation (PNC), Tokai-works, 4–33 Muramatsu, Tokai-mura, Naka-gun, Ibaraki-ken, 319–11, JAPAN
Jin Ohuchi
Affiliation:
Power Reactor and Nuclear Fuel Development Corporation (PNC), Tokai-works, 4–33 Muramatsu, Tokai-mura, Naka-gun, Ibaraki-ken, 319–11, JAPAN
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Abstract

Possibility of highly waste loaded borosilicate glasses up to 65wt% were investigated for HLW. In the case the waste was loaded at a content higher than 45wt%, apatite crystal was identified in the glasses. Adding above 2.5wt% of M0O3, yellow phase was observed in the 45wt% waste glass. In the case the composition of actual waste was simulated, waste(25–45wt%) glasses were characterized. Chemical durability of 45wt% waste glass was equivalent to that of 25wt% waste glass under the condition of Na20 content lower than 12wt%. Rheological behavior of 45wt% waste glass was equivalent to that of 25wt% waste glass in the range of melting temperature. Electrical resistivity of 45wt% waste glass were a little lower than that of 25wt% waste glass and it depended on the noble metal content. The Time-Temperature-Transformation (T-T-T) diagram and the leach rate of heat treated glass indicated a good thermal stability of highly waste loaded glass below the glass transition temperature. Possibility of high waste loading up to 45wt% was elucidated.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 353: Symposium – Scientific Basis for Nuclear Waste Management XVIII , 1994 , 87
Copyright
Copyright © Materials Research Society 1995

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References

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