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Alloy 690 is a high-chromium nickel-base alloy used in various primary coolant system components and for steam generator tubes in many nuclear power plants. A thermal treatment is typically applied for Alloy 690 components, giving the material a better resistance to stress corrosion cracking, compared to mill-annealed condition, due to fine grain boundary carbides of type M23C6. The effect of thermal aging at 400 ◦C was investigated in four different heats of Alloy 690. After 5000 h and 10 000 h of aging, one of the materials showed a significant increase in hardness, whereas the three other heats did not show a measurable effect of aging. Microstructural and hardness characterizations were performed, on both initial and aged material, by applying optical microscopy, scanning electron microscopy, energy-dispersive X-ray spectroscopy, microhardness and nanoindentation measurements, in order to study the microstructural features causing the observed increase in hardness.
|Title of host publication||19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors|
|Publisher||American Nuclear Society (ANS)|
|Number of pages||9|
|Publication status||Published - 2019|
|MoE publication type||A4 Article in a conference publication|
|Event||19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019 - Boston, United States|
Duration: 18 Aug 2019 → 22 Aug 2019
|Conference||19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019|
|Abbreviated title||ENVDEG 2019|
|Period||18/08/19 → 22/08/19|
FingerprintDive into the research topics of 'Effect of thermal aging on microstructure and hardness of industrial heats of Alloy 690'. Together they form a unique fingerprint.
- 1 Finished
Huotilainen, C., Que, Z. & Ehrnstén, U.
1/01/19 → 31/12/19