About this Abstract |
Meeting |
2025 TMS Annual Meeting & Exhibition
|
Symposium
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Meeting Materials Challenges for the Future of Fusion Energy
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Presentation Title |
Evolution of He Bubble Morphology During In Situ Heating of Plasma Exposed Tungsten and Tungsten Alloys |
Author(s) |
Dhriti Bhattacharyya, Bryan Teo, Matt Thompson, Maryna Bilokur, Cormac Corr |
On-Site Speaker (Planned) |
Dhriti Bhattacharyya |
Abstract Scope |
Tungsten is the prime candidate material for the plasma facing wall of the divertor in Tokamak based nuclear fusion reactors because of its excellent high temperature mechanical properties and refractory nature. However, as the divertor removes He from the plasma, the W monoblocks constituting the surface are bombarded by low energy He, leading to its absorption and the formation of a thin layer of bubbles which may result in a nanotendril structure called “fuzz”. We report on the study of the evolution of He bubbles formed in W/ W alloys exposed to He plasma in the MagPIE device at ANU, through in situ TEM observations made while the sample is annealed to temperatures up to 850°C. The shape and size distribution of the bubbles are analysed in order to obtain an understanding of the retention and release of He in W as a function of plasma exposure and annealing temperatures. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Characterization, High-Temperature Materials |