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Corrosion of Radioactive, Crushed Waste Glass

Published online by Cambridge University Press:  26 February 2011

Inga-Kari Björner ,
H. Christensen ,
H. P. Hermansson ,
M Tsukamoto  and
L Werme
Inga-Kari Björner
Affiliation:
Studsvik Nuclear, S-611 82 Nyköping, Sweden
H. Christensen
Affiliation:
Studsvik Nuclear, S-611 82 Nyköping, Sweden
H. P. Hermansson
Affiliation:
Studsvik Nuclear, S-611 82 Nyköping, Sweden
M Tsukamoto
Affiliation:
Central Research Institute of Electric Power Industry, 11–1 Iwato Kita 2-chome, Koraae-shi, Tokyo 201, Japan
L Werme
Affiliation:
Swedish Nuclear Management Company. Box 5864 S-102 48 Stockholm, Sweden
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Abstract

The corrosion experiments of crushed, radioactive waste glass at Studsvik within phase V of the JSS Project are described. The experiments were performed with high S/V ratios (1100 and 4000 m−1) which resulted in silica saturation already after the shortest reaction time studied (91 d).Thee long term leach rate of the soluble elements is about 10−3 g.m d−1, both in the presence and absence of bentonite. In the presence of bentonite + magnetite the leach rate is higher, about 0.007 g.m1.d−2. The release rate to the solution of Cs is one order of magnitude lower and that of Pu-238 + Am-241 three orders of magnitude lower than the release rate of the soluble elements Mo and B. Most of the Pu-238 and Am-241 fraction, found in the solution, is present as colloids.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 127: Symposium BERLIN – Scientific Basis for Nuclear Waste Management XII , 1988 , 113
Copyright
Copyright © Materials Research Society 1989

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References

REFERENCES

1. “JSS-Project Phase I: A Summary of Work Performed at Studsvik Energiteknik AB and at Swiss Federal Institute for Reactor research (EIR)” JSS Technical Report 84–03Google Scholar
2. “JSS Project Phase V Final Report: Testing and Modeling of the Corrosion of Powders of Simulated Nuclear Waste Glass in Waste Package Environment” JSS Technical Report 88–02Google Scholar
3. “(MCC) Materials Characterization Center, Nuclear Materials Handbook, Vol 1, Test Methods” DOE-TOC-11400, Pacific Northwest Laboratory, Richland, WA (1981)Google Scholar
4. “JSS-Project Phase IV: Final Report of Work Performed at Studsvik Energiteknik AB and at Swiss Federal Institute for Reactor research (EIR)” JSS Technical Report 87–01, SKB (1987)Google Scholar
5. Tsukamoto, M et al “Leaching of Am-241 from Radioactive Waste Glass Corroded in the Presence of Stainless Steel Corrosion Products and-or Bentonite” in Scientific Basis for Nuclear Waste Management XI, edited by Apted, M.J. and Westermán, R.E. (Publishers Choice Book Mfg. Co PA 1988) pp 565–574. 1987Google Scholar