Discovering tungsten-based composites as plasma facing materials for future high-duty cycle nuclear fusion reactors
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Published:2024-06-15
Issue:1
Volume:14
Page:
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ISSN:2045-2322
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Container-title:Scientific Reports
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language:en
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Short-container-title:Sci Rep
Author:
Marchhart Trevor, Hargrove Chase, Marin Alexandru, Schamis Hanna, Saefan Ashrakat, Lang Eric, Wang XingORCID, Allain Jean Paul
Abstract
AbstractDespite of excellent thermal properties and high sputtering resistance, pure tungsten cannot fully satisfy the requirements for plasma facing materials in future high-duty cycle nuclear fusion reactions due to the coupled extreme environments, including the high thermal loads, plasma exposure, and radiation damage. Here, we demonstrated that tungsten-based composite materials fabricated using spark-plasma sintering (SPS) present promising solutions to these challenges. Through the examination of two model systems, i.e., tungsten-zirconium composite for producing porous tungsten near the surface and dispersoid-strengthened tungsten, we discussed both the strengths and limitations of the SPS-fabricated materials. Our findings point towards the need for future studies aimed at optimizing the SPS process to achieve desired microstructures and effective control of oxygen impurities in the tungsten-based composite materials.
Funder
U.S. Department of Energy
Publisher
Springer Science and Business Media LLC
Reference44 articles.
1. Miyahara, A. & Tanabe, T. Graphite as plasma facing material. J. Nucl. Mater. 155–157, 49–57. https://doi.org/10.1016/0022-3115(88)90226-7 (1988). 2. Yoshida, N. Review of recent works in development and evaluation of high-Z plasma facing materials. J. Nucl. Mater. 266–269, 197–206. https://doi.org/10.1016/S0022-3115(98)00817-4 (1999). 3. National Academies of Sciences, Engineering, and Medicine. Bringing Fusion to the U.S. Grid (National Academies Press, 2021). 4. Maingi, R., Lumsdaine, A., Barish, S., White, A., Allain, J. P., Greenfield, C., Chacon, L., Gourlay, S., Humphreys, D., Izzo, V., Rapp, J., Schmitz, O., Spadaccini, C., Wang, Z., Wirth, B., Hughes, J., McLean, H., Menard, J. & Merrill, B. Transformative enabling capabilities for efficient advance toward fusion energy (2018). 5. Skinner, C. H. et al. Recent advances on hydrogen retention in ITER’s plasma-facing materials: Beryllium, Carbon, and Tungsten. Fusion Sci. Technol. 54, 891–945. https://doi.org/10.13182/FST54-891 (2008).
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