Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
7963563 | Journal of Nuclear Materials | 2018 | 9 Pages |
Abstract
The tangential fretting wear of three kinds of zirconium alloys tube mated with 304 stainless steel (SS) plate was investigated. The tests were conducted in an autoclave containing 300 °C pressurized B-Li water for tube-on-plate contact configuration. The worn surfaces were examined with scanning electron microscopy (SEM), energy dispersive spectroscopy (EDS) and 3D microscopy. The cross-section of wear scar was examined with transmission electron microscope (TEM). The results indicated that the dominant wear mechanism of zirconium alloys in this test condition was delamination and oxidation. The oxide layer on the fretted area consists of outer oxide layer composed of iron oxide and zirconium oxide and inner oxide layer composed of zirconium oxide.
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Authors
Lefu Zhang, Ping Lai, Qingdong Liu, Qifeng Zeng, Junqiang Lu, Xianglong Guo,