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Characterization of TiO2-Doped Yttria-Stabilized Zirconia (YSZ) for Supercritical Water-Cooled Reactor Insulator Application

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Abstract

In this study, TiO2-doped YSZ samples were tested in supercritical water (SCW) to evaluate their corrosion behavior. The doped samples were produced by mechanically alloying standard 7 wt.% Y2O3-ZrO2 with 5, 10, and 15 wt.% of TiO2 first. The bulk sample pieces were then obtained using plasma spraying of the alloyed powder materials followed by sintering. The results showed that the weight changes for 5TiYSZ and 10TiYSZ after 1000 h of exposure in SCW were negligible and the sample surfaces did not exhibit any indication of corrosion. In comparison to the reference materials (Al2O3 and 7YSZ) processed using the same method, the rate of weight change followed the order of Al2O3 > 7YSZ, 15TiYSZ > 10TiYSZ > 5TiYSZ. As several TiO2-doped 7SYZ compositions also display increased fracture toughness and reduced thermal conductivity, they may be considered as potential candidates for thermal insulation in a SCW-cooled nuclear reactor.

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Acknowledgment

Financial support for material and test equipment was provided by the NSERC/NRCAN/AECL under a NSERC CRD research grant.

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Authors and Affiliations

  1. Department of Mechanical and Aerospace Engineering, Carleton University, Ottawa, ON, Canada

    F. Barrett & X. Huang

  2. Atomic Energy Canada Laboratory, Chalk River, ON, Canada

    Dave Guzonas

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  1. F. Barrett
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  2. X. Huang
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  3. Dave Guzonas
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Correspondence to X. Huang.

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Barrett, F., Huang, X. & Guzonas, D. Characterization of TiO2-Doped Yttria-Stabilized Zirconia (YSZ) for Supercritical Water-Cooled Reactor Insulator Application. J Therm Spray Tech 22, 734–743 (2013). https://doi.org/10.1007/s11666-013-9911-1

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  • DOI: https://doi.org/10.1007/s11666-013-9911-1

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