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Release of Neptunium, Plutonium, Uranium and Technetium from the Metallic Waste form from the Electrometallurgical Treatment Process

Published online by Cambridge University Press:  21 March 2011

S. G. Johnson ,
M. Noy ,
T. DiSanto  and
T. L. Barber
S. G. Johnson
Affiliation:
Argonne National Laboratory-West P.O. Box 2528 Idaho Falls, ID 83403
M. Noy
Affiliation:
Argonne National Laboratory-West P.O. Box 2528 Idaho Falls, ID 83403
T. DiSanto
Affiliation:
Argonne National Laboratory-West P.O. Box 2528 Idaho Falls, ID 83403
T. L. Barber
Affiliation:
Argonne National Laboratory-West P.O. Box 2528 Idaho Falls, ID 83403
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Abstract

This waste form is an alloy consisting of stainless steel with 15 wt% zirconium and acts as a host for the immobilization of radioelements that remain with the spent fuel cladding hulls following their treatment using an electrometallurgical treatment process. The results presented here are from 14, 34 and 90-day immersion tests conducted at 90 °C. These tests show that the release of uranium is considerably higher than that of all other major elements present (Fe, Cr, Ni, Zr), but that release of all constituents is comparable to or lower than that for borosilicate glass.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 713: Symposium JJ – Scientific Basis for Nuclear Waste Management XXV , 2002 , JJ11.73
Copyright
Copyright © Materials Research Society 2002

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References

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