About this Abstract |
Meeting |
2023 TMS Annual Meeting & Exhibition
|
Symposium
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Transmutation Effects in Fusion Reactor Materials: Critical Challenges & Path Forward
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Presentation Title |
Analysis of Irradiation Damage Accumulation in Bi-phase Tungsten Heavy Alloy Microstructures |
Author(s) |
James V. Haag, Weilin Jiang, Matthew Olszta, Wahyu Setyawan |
On-Site Speaker (Planned) |
James V. Haag |
Abstract Scope |
Tungsten heavy alloys present a combination of highly desirable material properties and favorable initial results for consideration as plasma facing material components in nuclear fusion reactors. Yet in these promising probe studies, there exists a lack of information on irradiation damage accumulation in these multi-component systems and its subsequent bearing upon material properties and thereby service lifetimes. To provide this essential data for material adoption, this study observes the effects of the simulated fusion environment on two identical composition tungsten heavy alloy specimens both before and after thermomechanical processing to observe the effects of microstructure on damage accumulation. These irradiations simulate the five-year expected damage to divertor tiles by subjecting specimens to sequential high temperature Ni and He ion irradiations to mimic displacement damage and He production incurred during extended operation. This data will then be used to greatly improve predictive capacity in the extrapolation of material service lifetimes. |
Proceedings Inclusion? |
Planned: |