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Evaluation of Iron-Base Materials for Waste Package Containers in a Salt Repository

Published online by Cambridge University Press:  25 February 2011

R. E. Westerman ,
J. L. Nelson ,
S. G. Pitman ,
W. L. Kuhn ,
S. J. Basham  and
D. P. Moak
R. E. Westerman
Affiliation:
Pacific Northwest Laboratory, Battelle Boulevard, Richland, Washington, U.S.A.
J. L. Nelson
Affiliation:
Pacific Northwest Laboratory, Battelle Boulevard, Richland, Washington, U.S.A.
S. G. Pitman
Affiliation:
Pacific Northwest Laboratory, Battelle Boulevard, Richland, Washington, U.S.A.
W. L. Kuhn
Affiliation:
Pacific Northwest Laboratory, Battelle Boulevard, Richland, Washington, U.S.A.
S. J. Basham
Affiliation:
Office of Nuclear Waste Isolation, 505 King Street, Columbus, Ohio, U.S.A.
D. P. Moak
Affiliation:
Office of Nuclear Waste Isolation, 505 King Street, Columbus, Ohio, U.S.A.
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Abstract

Design studies for high-level nuclear waste packages for salt repositories have identified low-carbon steel as a candidate material for containers. Among the requirements are strength, corrosion resistance, and fabricability. The studies of the corrosion resistance and structural stability of iron-base materials (particularly lowcarbon steel) are treated in this paper. The materials have been exposed in brines that are characteristic of the potential sites for salt repositories. The effects of temperature, radiation level, oxygen level and other parameters are under investigation. The initial development of corrosion models for these environments is presented with discussion of the key mechanisms under consideration.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 26 , 1983 , 427
Copyright
Copyright © Materials Research Society 1984

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References

REFERENCES

1. Rule 10 CFR, Part 60, Disposal of High-Level Radioactive Wastes in Geologic Repositories, Federal Register, 48, 120, p. 28217, (1983).Google Scholar
2. Basham, S. J. Jr., and Carr, J. A., “Waste Package Designs for Disposal of High-Level Waste in Salt Formations,” IAEA-CN-43/222, IAEA Conference on Radioactive Waste Management, Seattle, Washington, May 1983.Google Scholar
3. Westerman, R. E., “Investigation of Metallic, Ceramic, and Polymeric Materials for Engineered Barrier Applications in Nuclear Waste Packages,” PNL 3484, Pacific Northwest Laboratory, Richland, Washington (1980).Google Scholar
4. Westerman, R. E., Pitman, S. G., and Nelson, J. L., “General Corrosion, Irradiation-Corrosion, and Environmental-Mechanical Evaluation of Nuclear Waste Package Structural Barrier Materials,” PNL-4364, Pacific Northwest Laboratory, Richland, Washington (1982).10.2172/6633179Google Scholar
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