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Arthur T. Motta
Researcher at Pennsylvania State University
Publications - 189
Citations - 6287
Arthur T. Motta is an academic researcher from Pennsylvania State University. The author has contributed to research in topics: Zirconium alloy & Corrosion. The author has an hindex of 37, co-authored 184 publications receiving 5360 citations. Previous affiliations of Arthur T. Motta include Lawrence Berkeley National Laboratory & Chalk River Laboratories.
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Radiation effects in crystalline ceramics for the immobilization of high-level nuclear waste and plutonium
William J. Weber,Rodney C. Ewing,C. R. A. Catlow,T. Diaz de la Rubia,Linn W. Hobbs,C. Kinoshita,Hj. Matzke,Arthur T. Motta,Michael Nastasi,Ekhard K. H. Salje,Eric R. Vance,Steven J. Zinkle +11 more
TL;DR: A comprehensive review of the state-of-the-art of radiation effects in crystalline ceramics that may be used for the immobilization of high-level nuclear waste and plutonium is provided in this article.
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Corrosion of Zirconium Alloys Used for Nuclear Fuel Cladding
TL;DR: In this article, the mechanisms of corrosion and hydrogen pickup and the role of alloy selection in minimizing both phenomena are considered on the basis of two principal characteristics: the pretransition kinetics and the loss of oxide protectiveness at transition.
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Structure of zirconium alloy oxides formed in pure water studied with synchrotron radiation and optical microscopy: relation to corrosion rate
TL;DR: In this article, a detailed study of oxides formed in 360 °C water on four Zr-based alloys (Zircaloy-4, ZIRLO™,1 Zr−2.5%Nb and Zr•2.9%Cu) was undertaken to relate oxide structure to corrosion performance.
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Transmission electron microscopy examination of oxide layers formed on Zr alloys
TL;DR: In this paper, a transmission electron microscopy investigation was performed on oxides formed on three zirconium alloys (Zircaloy-4, ZIRLO and Zr-2.5Nb) in pure water and lithiated water environments.
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A thermal spike model of grain growth under irradiation
TL;DR: In this article, a model is proposed to describe grain growth under irradiation in the temperature-independent regime, based on the direct impact of the thermal spikes on grain boundaries, where grain-boundary migration occurs by atomic jumps, within the thermal spike, biased by the local grainboundary curvature driving.