About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
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| Symposium
|
Characterization of Minerals, Metals and Materials 2026 - In-Situ Characterization Techniques
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| Presentation Title |
Evaluating Additively-Manufactured Tungsten Alloys’
Performance for Fusion Plasma-Facing Components
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| Author(s) |
Charles A. Hirst, Dylan Kohler, Nicholas Crnkovich, Barret Elward, Behzad Rankouhi, Dan Thoma, Robert Kolasinski, Jonathan Coburn, Florian Effenberg, Zana Popovic, Dmitry Rudakov, Charlie Lasnier, Roberto Maurizio, Tony Leonard, Gilson Ronchi, Dinh Truong, Cedric Tsui, Marcos Navarro Gonzalez, Mykola Ialovega |
| On-Site Speaker (Planned) |
Charles A. Hirst |
| Abstract Scope |
Fusion Pilot Plants (FPPs) are proposed to be deployed within 10 years; however, to achieve this timeline, key materials challenges must be overcome. Plasma-facing components (PFCs) will be subject to extreme combinations of elevated temperature, ion bombardment, and neutron irradiation. To investigate the performance of candidate materials, additively manufactured tungsten (W) alloys were exposed using the Divertor Material Evaluation System (DiMES) in the lower divertor of DIII-D tokamak. Specimens were characterized with SEM, EDS, laser confocal microscopy, XRD, and XPS before and after exposure to deuterium plasmas with Te ~40-50 eV, densities of ~3×1019 m-3, and incident heat fluxes of 2.2-2.4 MW/m2. The results were compared to reference pure W irradiated under the same conditions. Deuterium retention will be determined through thermal desorption spectroscopy (TDS), using a custom-built facility being developed at UW-Madison. This study will inform the development of W-based PFCs and thus deployment of future FPPs. This work was supported by US DOE under DE-NA0003525, DE-AC02-09CH11466, DE-FC02-04ER54698, DE-AC05-00OR22725, DE-AC52-07NA27344. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, High-Temperature Materials, Environmental Effects |