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Gary S. Was

Researcher at University of Michigan

Publications -  487
Citations -  17725

Gary S. Was is an academic researcher from University of Michigan. The author has contributed to research in topics: Grain boundary & Stress corrosion cracking. The author has an hindex of 56, co-authored 474 publications receiving 14795 citations. Previous affiliations of Gary S. Was include Massachusetts Institute of Technology.

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Application of the inverse Kirkendall model of radiation-induced segregation to ferritic–martensitic alloys

TL;DR: In this paper, the inverse Kirkendall (IK) model was applied to the binary Fe-Cr b.c. system, to determine whether observations of Cr in ferritic-martensitic (F-M) alloys can be explained by the IK mechanism.
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Quantitative analysis of radiation-induced grain-boundary segregation measurements

TL;DR: In this paper, a combination of STEM and AES data was used to determine the width of the segregated layer in an ultrahigh-purity alloy doped with P. The results showed that the latter is essentially contained in a single monolayer.
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Void swelling in ferritic-martensitic steels under high dose ion irradiation: Exploring possible contributions to swelling resistance

TL;DR: In this paper, the authors explored the contribution of helium effects and possible contributions to swelling resistance in ferritic-martensitic steels based on the results of transmission electron microscopy analysis and found that radiation induced high density precipitates (Fe,Cr)2C were found to account for the superior swelling resistance of CNS II.
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The effect of grain boundary structure on the intergranular degradation behavior of solution annealed alloy 690 in high temperature, hydrogenated water

TL;DR: In this paper, the environmental degradation of four different types of grain boundaries were investigated on alloy 690 following slow strain rate tensile tests in 360°C hydrogenated water, and it was shown that the grain boundary structure dependence of SCC resistance should be understood from its effects on solute diffusivity, structure of intergranular oxide and the local stress-strain state.
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The oxidation of alloy 690 in simulated pressurized water reactor primary water

TL;DR: In this paper, the oxide film formed on alloy 690 in simulated pressurized water reactor primary water is decorated with NiFe 2 O 4 particles which remain epitaxial with matrix.