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Evolution of Solution Chemistry through Interactions with Waste Package Internal Structural Components

Published online by Cambridge University Press:  21 March 2011

Y.-M. Pan ,
C.S. Brossia ,
G.A. Cragnolino ,
D.S. Dunn ,
V. Jain  and
N. Sridhar
Y.-M. Pan
Affiliation:
Center for Nuclear Waste Regulatory Analyses (CNWRA)Southwest Research Institute 6220 Culebra Road, San Antonio, TX 78238-5166, USA
C.S. Brossia
Affiliation:
Center for Nuclear Waste Regulatory Analyses (CNWRA)Southwest Research Institute 6220 Culebra Road, San Antonio, TX 78238-5166, USA
G.A. Cragnolino
Affiliation:
Center for Nuclear Waste Regulatory Analyses (CNWRA)Southwest Research Institute 6220 Culebra Road, San Antonio, TX 78238-5166, USA
D.S. Dunn
Affiliation:
Center for Nuclear Waste Regulatory Analyses (CNWRA)Southwest Research Institute 6220 Culebra Road, San Antonio, TX 78238-5166, USA
V. Jain
Affiliation:
Center for Nuclear Waste Regulatory Analyses (CNWRA)Southwest Research Institute 6220 Culebra Road, San Antonio, TX 78238-5166, USA
N. Sridhar
Affiliation:
Center for Nuclear Waste Regulatory Analyses (CNWRA)Southwest Research Institute 6220 Culebra Road, San Antonio, TX 78238-5166, USA
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Abstract

The chemistry of the aqueous environment inside any breached waste packages is critical to the release of radionuclides from the waste packages for high-level waste disposal. A corrosion test cell that simulates some aspects of the internal geometry of the waste packages has been designed to investigate changes in the in-package solution chemistry. A series of tests was conducted to evaluate solution chemistry variations as a function of applied potential and temperature using a specimen of Type 316L stainless steel with a predrilled hole as a simulated pit. A micro-syringe was used to extract solutions from inside and outside the pit. The solutions were analyzed for cation concentrations using capillary electrophoresis, and the pH was measured using a micro-electrode. Preliminary measurements showed substantially high cation concentrations inside the pit due to anodic dissolution of Type 316L stainless steel. The solution pH became considerably acidic, reaching a value of 2.6. These results suggest that interactions of waste package internal structural components with incoming water may have significant influence on the evolution of water chemistry and the subsequent corrosion of waste forms such as spent nuclear fuel.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 713: Symposium JJ – Scientific Basis for Nuclear Waste Management XXV , 2002 , JJ1.10
Copyright
Copyright © Materials Research Society 2002

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References

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