Add time:07/29/2019         Source:sciencedirect.com

In this research, the cladding substrate, Zircaloy-4 was coated with a 3-μm zirconium silicide (ZrSi2). At 700 °C in air, the ZrSi2 coating prevented thermal oxidation and thereby protected the underlying Zicaloy-4 substrate. In contrast, uncoated Zircaloy-4 surface developed an oxide layer that was a few micrometers thick. To investigate the effects of the coating on boiling characteristics, a pool-boiling experiment with saturated water, and a Leidenfrost experiment at low Weber number were conducted under atmospheric pressure. Thermal oxidation of the ZrSi2-coated surface did not affect critical heat flux or Leidenfrost temperature, but thermal oxidation of the uncoated Zircaloy-4 substrate affected its boiling parameters. A thin ZrSi2 coating can be applied easily to a Zircaloy-4 substrate, and may be considered for use in nuclear reactors.

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