This report presents results of sensitivity studies aimed at elucidating which model parameters contribute most to the drip shield and waste package degradation characteristics. The model parameters identified included (a) general corrosion rate model parameters (temperature-dependence and uncertainty treatment), and (b) stress corrosion cracking (SCC) model parameters (uncertainty treatment of stress and stress intensity factor profiles in the Alloy 22 waste package outer barrier closure weld regions, the SCC initiation stress threshold, and the fraction of manufacturing flaws oriented favorably for through-wall penetration by SCC.

Citation: Mon, K.G., B.E. Bullard, D.E. Longsine, S. Mehta, J.H. Lee, A.M. Monib. United States. Sandia National Laboratories. Long-Term Waste Package Degradation Studies at the Yucca Mountain Potential High-Level Nuclear Waste Repository. Washington, D.C.: Department of Energy, Office of Civilian Radioactive Waste Management, 2002.

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