About this Abstract |
Meeting |
2022 TMS Annual Meeting & Exhibition
|
Symposium
|
Materials Systems for the Future of Fusion Energy
|
Presentation Title |
Microstructural Examination of Radiation Damage in Tungsten |
Author(s) |
Michael Klimenkov, Ute Jäntsch, Ramil Gaisin, Steffen Antusch, Michael Rieth, Hans-Christian Schneider, 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 microscopic examination of neutron irradiated tungsten is of high importance for assessing possible limits of operation conditions and life-time of plasma facing components.
Transmission electron microscopy examinations of tungsten irradiated at various temperatures and damage doses identify four defect types that adversely affect the material properties: (1) interstitial and vacancy clusters, (2) dislocation loops and (3) voids. In addition, transmutation processes lead to an enrichment of the matrix with rhenium or osmium and their radiation-induced segregation on the structural defects. Under certain conditions, this segregation leads to the formation of σ-W(ReOs)2 and χ-W(ReOs)3 precipitates. The defects lead to swelling, radiation hardening and embrittlement, which can considerably limit the service life of tungsten components. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, High-Temperature Materials, |