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An Approach to Analysis of High Level waste Container Performance in an Unsaturated Repository Environment

Published online by Cambridge University Press:  25 February 2011

John C. Walton ,
Narasi Sridhar ,
Gustavo Cragnolino ,
Tony Torng  and
Prasad Nair
John C. Walton
Affiliation:
Department of Civil Engineering, University of Texas at El Paso, El Paso, Texas, 79968-0516
Narasi Sridhar
Affiliation:
Center for Nuclear Waste Regulatory Analyses, Southwest Research Institute, San Antonio, Texas, 78238-5166
Gustavo Cragnolino
Affiliation:
Center for Nuclear Waste Regulatory Analyses, Southwest Research Institute, San Antonio, Texas, 78238-5166
Tony Torng
Affiliation:
Center for Nuclear Waste Regulatory Analyses, Southwest Research Institute, San Antonio, Texas, 78238-5166
Prasad Nair
Affiliation:
Center for Nuclear Waste Regulatory Analyses, Southwest Research Institute, San Antonio, Texas, 78238-5166
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Abstract

One of the requirements for the performance of waste packages prescribed in 10CFR 60.113 is that the high level waste must be “substantially completely” contained for a minimum period of 300 to 1000 years. During this period, the radiation and thermal conditions in the engineered barrier system and the near-field environment are dominated by fission product decay. In the present U.S design of the engineered barrier system, the outer container plays a dominant role in maintaining radionuclide containment. A quantitative methodology for analyzing the performance of the container is described in this paper. This methodology enables prediction of the evolution of the waste package environment in terms of temperature fields, stability of liquid water on the container surface, and concentration of aggressive ions such as chloride. The initiation and propagation of localized corrosion is determined by the corrosion potential of the container material and critical potentials for localized corrosion. The coiTOsion potential is estimated from the kinetics of the anodic and cathodic reactions including oxygen diffusion through scale layers formed on the container surface. The methodology described is applicable to a wide range of metals, alloys and environmental conditions.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 333: Symposium V – Scientific Basis for Nuclear Waste Management XVII , 1993 , 863
Copyright
Copyright © Materials Research Society 1994

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References

REFERENCES

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