| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 7966855 | Journal of Nuclear Materials | 2015 | 5 Pages |
Abstract
Alloy 690(TT) is widely used for steam generator tubes in pressurized water reactor (PWR), where it is susceptible to corrosion fatigue. In this study, the corrosion fatigue behavior of Alloy 690(TT) in simulated PWR environments was investigated. The microstructure of the plastic zone near the crack tip was investigated and labyrinth structures were observed. The relationship between the crack tip plastic zone and fatigue crack growth rates and the environment factor Fen was illuminated.
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Physical Sciences and Engineering
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Nuclear Energy and Engineering
Authors
J. Xiao, S.Y. Qiu, Y. Chen, Z.H. Fu, Z.X. Lin, Q. Xu,