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Leaching of Am-241 from a Radioactive Waste Glass Corroded in the Presence of Stainless Steel Corrosion Products and/or Bentonite

Published online by Cambridge University Press:  28 February 2011

Masaki Tsukamoto ,
Inga-Kari Björner ,
Hilbert Christensen ,
Hans-Peter Hermansson  and
Lars Werme
Masaki Tsukamoto
Affiliation:
Central Research Institute of Electric Power Industry, 11-1, Iwatokita 2-chome, Komae-shi, Tokyo 201, Japan
Inga-Kari Björner
Affiliation:
Studsvik Nuclear, S-611 82 Nyköping, Sweden
Hilbert Christensen
Affiliation:
Studsvik Nuclear, S-611 82 Nyköping, Sweden
Hans-Peter Hermansson
Affiliation:
Studsvik Nuclear, S-611 82 Nyköping, Sweden
Lars Werme
Affiliation:
Swedish Nuclear Fuel and Waste Management Co, P.O. Box 5864, S-102 48 Stockholm, Sweden
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Abstract

The release of Am-241 during corrosion of the radioactive waste glass, JSS-A, has been studied in the presence of corrosion products and/or uncom-pacted bentonite. The corrosion behaviour of Am-241 has been analyzed using gamma spectrometry. Adsorption of Am-241 on bentonite is observed in all cases. The contents of Am-241 in centrifuged leachates are in most cases less than 1/100 of total values. The normalized elemental mass loss of Am increases initially with corrosion time, and the values in the presence of bentonite and corrosion products are larger than those in the presence of bentonite alone. This tendency is in agreement with results previously found for other elements. The release of Am is low, only about 10–20 % of the corresponding total mass loss.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 112: Symposium P – Scientific Basis for Nuclear Waste Management XI , 1987 , 565
Copyright
Copyright © Materials Research Society 1988

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