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The localized corrosion resistance and mechanical properties of alloy 22 waste package outer containers

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  • High-Radiation Nuclear Waste Disposal
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Abstract

The proposed waste packages for the disposal of high-level radioactive waste at the potential repository at Yucca Mountain, Nevada, consist of an outer container and inner container. The outer container is made of alloy 22, a corrosion-resistant Ni-Cr-Mo-W alloy, while the inner container is made of type 316 nuclear-grade stainless steel. Fabrication processes such as welding and postweld heat treatments can induce changes to the microstructure of alloy 22. Such microstructural changes can reduce ductility and impact strength and promote localized corrosion. Environmental conditions within the emplacement drifts, such as composition of solutions contacting the waste packages, can also affect localized corrosion susceptibility. In this study, the effects of fabrication processes on impact strength, fracture toughness, and crevice-corrosion resistance of alloy 22 were investigated.

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Authors and Affiliations

  1. Southwest Research Institute, Center of Nuclear Waste Regulatory Analyses, San Antonio, Texas

    D. S. Dunn, Y. -M. Pan, K. T. Chiang, L. Yang, G. A. Cragnolino & X. He

Authors
  1. D. S. Dunn
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  2. Y. -M. Pan
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  3. K. T. Chiang
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  4. L. Yang
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  5. G. A. Cragnolino
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  6. X. He
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Additional information

For more information, contact D.S. Dunn, Southwest Research Institute, Center of Nuclear Waste Regulatory Analyses, 6220 Culebra Road, San Antonio, TX 78238-5166; (210) 522-6090; fax (210) 522-5184; e-mail ddunn@swri.org.

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Dunn, D.S., Pan, Y.M., Chiang, K.T. et al. The localized corrosion resistance and mechanical properties of alloy 22 waste package outer containers. JOM 57, 49–55 (2005). https://doi.org/10.1007/s11837-005-0064-7

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  • DOI: https://doi.org/10.1007/s11837-005-0064-7

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