The Corrosion Behavior of Carbon Steel Materials Used at Nuclear Power Plants During Deactivation and Decommissioning Processes
Abstract
1. Introduction
2. Materials and Methods
3. Results and Discussion
3.1. Metallographs of Base Metals
3.2. Effect of Water Flow on Corrosion
3.3. Corrosion of Partially Immersed Samples
4. Conclusions
- When the autoclave was filled with stagnant water, the corrosion rates of carbon steel A106 B in stagnant water at 45 °C were 23 μm/year for the cold-drawn samples and 19 μm/year for the hot-rolled samples.
- When the autoclave was partially filled with water and the samples were fully immersed, the corrosion rate for the hot-rolled sample was 88 μm/year.
- When the autoclave was partially filled with water and the samples were half-submerged, the corrosion rate for the hot-rolled sample increased to 102 μm/year. In this case, significant corrosion was observed along the air–water interface.
- When the autoclave was filled with stagnant water that was renewed at intervals, the corrosion rate for the cold-drawn sample was 11 μm/year.
- All of the above observations are compatible with higher water conductivity measurements observed at longer water residence times inside the autoclave in combination with higher corrosion along the air–water interfaces.
- A sufficient oxygen concentration promotes the formation of FeOOH or Fe2O3, while an oxygen-deficient environment favors the formation of Fe3O4.
Author Contributions
Funding
Data Availability Statement
Conflicts of Interest
References
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Processes | Symbol | Class | Pipe Wall Thickness (mm) | Pipe Outside Diameter (mm) |
---|---|---|---|---|
Cold drawing | C | B | 2.77 | 21.3 |
Hot rolling | H | B | 5 | 32 |
Wt% | C | Si | Mn | P | S | Cr | Mo |
---|---|---|---|---|---|---|---|
Cold drawing | 0.19 | 0.22 | 0.43 | 0.016 | 0.002 | 0.002 | 0 |
Hot rolling | 0.21 | 0.22 | 0.44 | 0.013 | 0.014 | 0.015 | 0.02 |
Specification | Tensile Strength (Mpa) | Yield Strength (Mpa) |
---|---|---|
Minimum | 415 | 240 |
Maximum | 485 | 275 |
Test No. | Specimen No. | Test Condition | Specimen Inspection Interval | Testing Time (h) |
---|---|---|---|---|
Experiment (1) | C:15 H:15 | Still water (45 °C) | Extract one specimen per 60 days | 21,000 |
Experiment (2) | C:10 | Change water every 30 days (45 °C) | Extract 2 specimens per 60 days | 12,000 |
Experiment (3) | a:6 i:6 w:6 | Observation of interface corrosion behavior at still water (45 °C) | Extract one specimen per 90 days | 12,500 |
Heading | Corrosion Rate (µm/year) | Processes | Water Conductivity(µs/cm) | DissolvedOxygen(ppm) |
---|---|---|---|---|
Experiment (1) | 23 | Cold-drawn | 40.3 | 0.8 |
19 | Hot-rolled | |||
Experiment (2) | 11 | Cold-drawn | 0.4~22.3 | 6~1.72 |
The measurements were fluctuating due to periodic water changes. | ||||
Experiment (3) | 88 | Hot-rolled | 60.8 | 2.2 |
102 | Hot-rolled | |||
9 | Hot-rolled |
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Lu, W.-F.; Chen, T.-C.; Tsai, K.-C.; Yung, T.-Y. The Corrosion Behavior of Carbon Steel Materials Used at Nuclear Power Plants During Deactivation and Decommissioning Processes. Metals 2024, 14, 1444. https://doi.org/10.3390/met14121444
Lu W-F, Chen T-C, Tsai K-C, Yung T-Y. The Corrosion Behavior of Carbon Steel Materials Used at Nuclear Power Plants During Deactivation and Decommissioning Processes. Metals. 2024; 14(12):1444. https://doi.org/10.3390/met14121444
Chicago/Turabian StyleLu, Wen-Feng, Tai-Cheng Chen, Kun-Chao Tsai, and Tung-Yuan Yung. 2024. "The Corrosion Behavior of Carbon Steel Materials Used at Nuclear Power Plants During Deactivation and Decommissioning Processes" Metals 14, no. 12: 1444. https://doi.org/10.3390/met14121444
APA StyleLu, W.-F., Chen, T.-C., Tsai, K.-C., & Yung, T.-Y. (2024). The Corrosion Behavior of Carbon Steel Materials Used at Nuclear Power Plants During Deactivation and Decommissioning Processes. Metals, 14(12), 1444. https://doi.org/10.3390/met14121444