Journal
WEAR
Volume 368, Issue -, Pages 344-349Publisher
ELSEVIER SCIENCE SA
DOI: 10.1016/j.wear.2016.10.009
Keywords
Alloy 690; Oxidization; Fretting wear
Funding
- Human Resource Development Program of the Korea Institute of Energy Technology Evaluation and Planning (KETEP) Grant - Korean government Ministry of Trade, Industry and Energy [20134030200360]
- National Research Foundation of Korea (NRF) Grant - Korea government (MSIP)
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Effect of formation of oxidation film on the wear behavior of Alloy 690 steam generator (SG) tubes for nuclear power plants was investigated. Alloy 690 SG tubes are normally oxidized during operation due to the high temperature of the pressurized water. Based on the previous tribology research for metallic materials, we reasoned that the oxidation film can have an important effect on the wear behavior of the Alloy 690 SG tubes. Therefore, in this study, Alloy 690, oxidized in an autoclave under secondary water conditions, was used for wear test. The result of the wear test showed that as the oxidation treatment time increased, the thickness of oxidation film increased and the wear resistance of Alloy 690 increased. (C) 2016 Elsevier B.V. All rights reserved.
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