Study on the Corrosion Behavior of 690TT Alloy Heat Transfer Tubes with Scratch Defects in a Simulated High-Temperature and High-Pressure Water Environment of the Pressurized Water Reactor Secondary Circuit
In order to evaluate the effect of scratch defects on the stress corrosion performance of 690TT alloy heat transfer tubes in a simulated high-temperature and high-pressure water environment of the secondary circuit， a nuclear power steam generator heat transfer tube was chosen as the research subjec...
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| Format: | Article |
| Language: | zho |
| Published: |
Editorial Department of Materials Protection
2025-03-01
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| Series: | Cailiao Baohu |
| Subjects: | |
| Online Access: | http://www.mat-pro.com/fileup/1001-1560/PDF/20250310.pdf |
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