This report evaluates hydrogen-induced cracking (HIC) susceptibility of titanium alloys in environments anticipated in the Yucca Mountain nuclear waste repository with particular emphasis on the. effect of the oxide passive film on the hydrogen absorption process of titanium alloys being evaluated. The titanium alloys considered in this review include Ti 2, 5 , 7, 9, 11, 12, 16, 17, 18, 24 and 29. It is concluded that under the exposure conditions anticipated in the Yucca Mountain repository, the HIC of titanium drip shield will not occur because there will not be sufficient hydrogen in the metal even after 10,000 years of emplacement.

Citation: De, G., Mon, K., Gordon, G., Shoesmith, D., Hua, F.. United States. Yucca Mountain Project. An Evaluation of Hydrogen Induced Cracking Susceptibility of Titanium Alloys in US High-Level Nuclear Waste Repository Environments. Washington, D.C.: Department of Energy, 2006.

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