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Sliding wear of a self-mated thermally sprayed chromium oxide coating in a simulated PWR water environment (2019)
Journal Article

Bearing surfaces in the primary circuit of pressurized water reactors (PWR) are prone to damage due to aggressive chemical and tribological conditions under which they operate, and a wide range of materials have been examined in this regard. One of t... Read More about Sliding wear of a self-mated thermally sprayed chromium oxide coating in a simulated PWR water environment.

Comparison of the sliding wear behaviour of self-mated HIPed Stellite 3 and Stellite 6 in a simulated PWR water environment (2019)
Journal Article

Cobalt-based alloys such as Stellite 3 and Stellite 6 are widely used to protect stainless steel surfaces in primary circuit nuclear reactor applications where high resistance to wear and corrosion are required. In this study, selfmated sliding wear... Read More about Comparison of the sliding wear behaviour of self-mated HIPed Stellite 3 and Stellite 6 in a simulated PWR water environment.