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Sintered Glasses for High-Level Wastes

Published online by Cambridge University Press:  03 September 2012

D. O. Russo ,
N. B. Messi de Bernasconi ,
M. E. Sterba ,
A. D. Heredia ,
M. Sanfilippo ,
S. Prastalo  and
J. C. Sbriller
D. O. Russo
Affiliation:
CNEA, Centro Atòmico Bariloche, RN 8400, ARGENTINA
N. B. Messi de Bernasconi
Affiliation:
CNEA, Centro Atòmico Bariloche, RN 8400, ARGENTINA
M. E. Sterba
Affiliation:
CNEA, Centro Atòmico Bariloche, RN 8400, ARGENTINA
A. D. Heredia
Affiliation:
CNEA, Centro Atòmico Bariloche, RN 8400, ARGENTINA
M. Sanfilippo
Affiliation:
CNEA, Centro Atòmico Bariloche, RN 8400, ARGENTINA
S. Prastalo
Affiliation:
CNEA, Centro Atòmico Bariloche, RN 8400, ARGENTINA
J. C. Sbriller
Affiliation:
CNEA, Centro Atòmico Bariloche, RN 8400, ARGENTINA
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Abstract

The objective of the work was to evaluate the long-term capacity of sintered glass to retain high-level nuclear wastes (HLW) in near-repository conditions. We have studied the corrosion behavior of waste forms partially devitrified (43 vol.%) in different aqueous media. Devitrified samples were irradiated at doses (γ radiation from a Co 60 source) ranging from 1.4 × 106 Gy to 2.0 × 108 Gy, in order to study their aqueous corrosion resistance in simulated underground water. The results show little or no effect of irradiation on the density, microstructure and corrosion resistance. The global dissolution rate was almost constant around a value of 5×10−5 g. cm−2 d−1. Elemental dissolution rates were also unaffected by radiation.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 465: Symposium II – Scienfific Basis for Nuclear Waste Management XX , 1996 , 205
Copyright
Copyright © Materials Research Society 1997

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References

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