Advancing Fusion Materials via Public and Private Sector Experiments in DIII-D
POSTER
Abstract
A suite of advanced plasma-facing material candidates, including tungsten (W) alloys, additively manufactured and doped W, high-entropy alloys (RHEAs), ultra-high temperature ceramics (UHTCs), SiC-based ceramics, and boron-based materials, was tested in reactor-relevant scenarios in the DIII-D tokamak to guide material selection for future fusion pilot plants. Incident target heat fluxes reached ~2.2–2.4 MW/m² inter-ELM and ~6 MW/m² during ELMs in H-mode on material samples developed by public and private partners. Angled targets saw fluxes up to 11 MW/m² with surface temperatures >800 °C. W-based materials, including cold-sprayed and laser-powder bed AM W-Ta, doped W (K, Re), W-Ti-Cr, Ta-Ti-V-W, and ITER-grade or neutron-irradiated references, showed varied thermal stability; some alloys exhibited improved crack resistance and reduced impurity release. RHEAs revealed constituent-selective erosion and modest impurity release. UHTCs (NbC, ZrC, (Nb,Ta)C) remained intact under transient heat loads. SiCf/SiC samples showed stable thermal behavior and distinct surface changes. B and Si-based ceramics, including pure boron aggregates, underwent measurable physical and chemical sputtering.
The data collected in DIII-D will support material choices for reactor-relevant environments.
The data collected in DIII-D will support material choices for reactor-relevant environments.
*Work supported by US DOE under DE-AC02-09CH11466, DE-NA0003525, DE-AC05-00OR22725, DE-FC02-04ER54698, DE-FG02-07ER54917, DE-SC0023378, DE-AC52-07NA27344.
Publication: J.D. Coburn, F. Effenberg et al 2025 Nucl. Mater. Energy, submitted
Presenters
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Florian Effenberg
- Princeton Plasma Physics Laboratory
- Princeton Plasma Physics Laboratory (PPPL)