Container Material Selection, Modeling and Testing

by W. L. Clarke, Lawrence Livermore Natl Lab, United States,
J. C. Farmer, Lawrence Livermore Natl Lab, United States,
W. G. Halsey, Lawrence Livermore Natl Lab, United States,
R. D. McCright, Lawrence Livermore Natl Lab, United States,

Document Type: Proceeding Paper

Part of: High Level Radioactive Waste Management 1990


Virtually all of the approximately 40,000 high-level nuclear wast containers to be emplaced at Yucca Mountain must remain intact for 1,000 years to satisfy Nuclear Regulatory Commission (NRC) regulation 10 CFR Part 60. The container material must, therefore, be extremely stable in the repository environment. Work to date has consisted of literature, analytical, and experimental studies to evaluate six candidate alloys for the container material, following a design configuration specified in the Site Characterization Plan. The final container material will be selected when the site characterization is sufficiently completed. In addition, efforts are being expended to identify and/or develop models for predicting long-term material performance, and to conduct testing to assist in the selection process and to confirm the models.

Subject Headings: Material tests | Materials characterization | Site investigation | Materials processing | Radioactive wastes | Radioactive materials | Hazardous materials | Federal government

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