About this Abstract |
Meeting |
2023 TMS Annual Meeting & Exhibition
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Symposium
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Transmutation Effects in Fusion Reactor Materials: Critical Challenges & Path Forward
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Presentation Title |
Analytical TEM Examination of Re and Os Segregation in Neutron Irradiated Tungsten |
Author(s) |
Michael Klimenkov, Ute Jäntsch, Michael Dürrschnabel, Michael Rieth, Dmitry Terentyev, Wouter Van Renterghem |
On-Site Speaker (Planned) |
Michael Klimenkov |
Abstract Scope |
Tungsten is the prime candidate material for plasma-facing components in future fusion reactors due to its several advantageous properties such as a high melting point, high sputtering resistance and low coefficient of thermal expansion. The transmission electron microscopic examination tungsten irradiated in BR2 reactor at various temperatures and damage neutron irradiated tungsten is of high importance for assessing possible limits of operation conditions and life-time of plasma facing components.
This work focuses on the analysis of temperature- and dose-dependent rhenium (Re) and osmium (Os) segregation at voids, dislocation loops and grain boundaries. Segregation processes lead to a local Re and Os enrichment under certain conditions formation of σ-W(ReOs)2 and χ-W(ReOs)3 precipitates. The results contribute not only to the understanding of radiation hardening and embrittlement, which significantly limit the lifetime of W devices, but also to the verification and improvement of theoretical models for radiation-induced Re and Os diffusion in W. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, |