Deuterium retention in self-ion irradiated tungsten: influence of irradiation 
temperature, damage dose, and alloying elements

Zibrov, M.; Schwarz-Selinger, T.

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Deuterium retention in self-ion irradiated tungsten: influence of irradiation temperature, damage dose, and alloying elements

Zibrov, M., & Schwarz-Selinger, T. (2024). Deuterium retention in self-ion irradiated tungsten: influence of irradiation temperature, damage dose, and alloying elements. Talk presented at The Decennial IAEA Technical Meeting on Atomic, Molecular and Plasma-Material Interaction Data for Fusion Science and Technology (AMPMI 2024). Helsinki. 2024-07-15 - 2024-07-19.

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Item Permalink: https://hdl.handle.net/21.11116/0000-000F-B2B7-9 Version Permalink: https://hdl.handle.net/21.11116/0000-000F-B2B8-8

Genre: Talk

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Creators:
Zibrov, M.¹, Author
Schwarz-Selinger, T.¹, Author

Affiliations:
1Plasma Edge and Wall (E2M), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856327

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Language(s): eng - English

Dates: Submitted: 2024

Publication Status: Submitted

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Title: The Decennial IAEA Technical Meeting on Atomic, Molecular and Plasma-Material Interaction Data for Fusion Science and Technology (AMPMI 2024)

Place of Event: Helsinki

Start-/End Date: 2024-07-15 - 2024-07-19

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