Výsledky vyhledávání - "Ehrnstén, U."

Publikováno v: Huotilainen, C, Ehrnstén, U, Ahonen, M & Hänninen, H 2019, Effect of thermal aging on microstructure and hardness of industrial heats of Alloy 690 . in 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors . American Nuclear Society (ANS), pp. 156-164, 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, EnvDeg 2019, Boston, United States, 18/08/19 .
Scopus-Elsevier

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 bett

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Analytical examination of welds of surrogate and archive RPV materials

Autor: Ehrnstén, U., Autio, J.-M., Ivanchenko, M., Nevasmaa, P., Efsing, P.

Publikováno v: Ehrnstén, U, Autio, J-M, Ivanchenko, M, Nevasmaa, P & Efsing, P 2016, ' Analytical examination of welds of surrogate and archive RPV materials ', Paper presented at 19th Meeting of the International Group on Radiation Damage Mechanisms in Pressure Vessel Steel, IGRDM19, Asheville, United States, 10/04/16-15/04/16 .

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https://cris.vtt.fi/en/publications/e8f8d2de-5764-487a-a350-b6a0c0e8b2e7

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