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Glass/Ceramic Interactions in the Can-in-Canister Configuration for Disposal of Excess Weapons Plutonium

Published online by Cambridge University Press:  10 February 2011

B. P. Mcgrail ,
P. F. Martin ,
H. T. Schaef ,
C. W. Lindenmeier  and
A. T. Owen
B. P. Mcgrail
Affiliation:
Applied Geology and Geochemistry Department, Pacific Northwest National Laboratory, Richland, Washington 99352, pete.mcgrail@pnl.gov
P. F. Martin
Affiliation:
Applied Geology and Geochemistry Department, Pacific Northwest National Laboratory, Richland, Washington 99352
H. T. Schaef
Affiliation:
Applied Geology and Geochemistry Department, Pacific Northwest National Laboratory, Richland, Washington 99352
C. W. Lindenmeier
Affiliation:
Applied Geology and Geochemistry Department, Pacific Northwest National Laboratory, Richland, Washington 99352
A. T. Owen
Affiliation:
Applied Geology and Geochemistry Department, Pacific Northwest National Laboratory, Richland, Washington 99352
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Abstract

A can-in-canister waste package design has been proposed for disposal of pyrochlore rich ceramics containing excess weapons plutonium. The can-in-canister configuration consists of a high-level waste (HLW) canister fitted with a rack that holds minicanisters containing the ceramic. The HLW canister is then filled with glass. The pressurized unsaturated flow (PUF) technique was used to investigate waste form/waste form interactions that may occur when water penetrates the waste containers and contacts the waste forms. Volumetric water content was observed to increase steadily from accumulation of water mass as waters of hydration associated with alteration phases formed on the glass surface. Periodic excursions in effluent electrical conductivity and pH were monitored and correlated with secondary phases formed during the test. Plutonium exited the PUF system primarily as filterable particulates. However, effluent Pu and Gd concentrations were found to decrease with time and remained at near detection limits after approximately 250 days, except during transient pH excursions. These results indicate that both Pu and Gd will be retained in the can-in-canister waste package to a very high degree.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 608: Symposium QQ – Scientific Basis for Nuclear Waste Management XXIII , 1999 , 345
Copyright
Copyright © Materials Research Society 2000

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References

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