| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 5477953 | Nuclear Engineering and Technology | 2017 | 8 Pages |
Abstract
The fatigue crack growth behavior of Type 347 (S347) and Type 347N (S347N) stainless steel was evaluated under the operating conditions of a pressurized water reactor (PWR). These two materials showed different fatigue crack growth rates (FCGRs) according to the changes in dissolved oxygen content and frequency. Under the simulated PWR conditions for normal operation, the FCGR of S347N was lower than that of S347 and insensitive to the changes in PWR water conditions. The higher yield strength and better corrosion resistance of the nitrogen-alloyed Type 347 stainless steel might be a main cause of slower FCGR and more stable properties against changes in environmental conditions.
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Authors
Ki-Deuk Min, Seokmin Hong, Dae-Whan Kim, Bong-Sang Lee, Seon-Jin Kim,