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Modeling the hydrogen-induced cracking of titanium alloys in nuclear waste repository environments

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Abstract

This article considers hydrogen-induced cracking of titanium grade 7 and other relevant titanium alloys in the current waste package design for the environmental conditions anticipated within the proposed Yucca Mountain nuclear waste repository in Nevada. In particular, corrosion processes possible in the aqueous environments expected within this site are considered, including key corrosion processes that could occur and the expected corrosion performance of these alloys. It can be concluded that, based on the conservative modeling approaches adopted, hydrogen-induced cracking of titanium alloys will not occur under nuclear waste repository conditions since there will not be sufficient hydrogen in the alloy even after 10,000 years of emplacement.

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Authors and Affiliations

  1. Waste Package Materials Testing with Bechtel SAIC Company, Las Vegas, Nevada

    Fred Hua (senior engineer) & Pasu Pasupathi (manager)

  2. Framatome ANP, Las Vegas, Nevada

    Kevin Mon (senior staff scientist) & Gerald Gordon (senior staff scientist)

  3. the University of Western Ontario, London, Ontario, Canada

    David Shoesmith (a professor of chemistry)

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  1. Fred Hua
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  2. Pasu Pasupathi
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  3. Kevin Mon
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  4. Gerald Gordon
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  5. David Shoesmith
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Additional information

For more information, contact Fred Hua, Bechtel SAIC Company, LLC, 1180 Town Center Drive, Las Vegas, NV 89144; e-mail Fred_Hua@ymp.gov.

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Hua, F., Pasupathi, P., Mon, K. et al. Modeling the hydrogen-induced cracking of titanium alloys in nuclear waste repository environments. JOM 57, 20–26 (2005). https://doi.org/10.1007/s11837-005-0059-4

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