Review of Recent Progress in Plasma-Facing Material Joints and Composites in the FRONTIER U.S.-Japan Collaboration

L. M. Garrison*, Y. Katoh, T. Hinoki, N. Hashimoto, J. R. Echols, J. W. Geringer, N. C. Reid, J. P. Allain, B. Cheng, D. Dorow-Gerspach, V. Ganesh, H. Gietl, S. A. Humphry-Baker, E. Lang, I. McCue, J. Riesch, L. L. Snead, G. D.W. Smith, J. R. Trelewicz, Y. YangS. J. Zinkle

*Corresponding author for this work

Research output: Contribution to journalArticlepeer-review

Abstract

The plasma-facing components (PFCs) of future fusion reactors will have intricate structures and require multiple materials because no one material can simultaneously satisfy all the requirements of the component. The dissimilar material joints in PFCs must withstand extreme thermal and stress gradients under neutron irradiation. The Fusion Research Oriented to Neutron Irradiation and Tritium Behavior at Material Interfaces (FRONTIER) U.S.-Japan collaboration seeks to explore and explain the behavior of internal solid interfaces in PFCs under neutron irradiation. The first step of the collaboration was to identify the leading PFCs that should be studied further and prepare them for the next step, which will include neutron irradiation. Different strategies for material development are being pursued worldwide to produce robust PFCs. Here, an overview is presented of some of the most promising materials in the areas of copper alloys, tungsten-copper composites, tungsten-steel composites, additively manufactured tungsten, particle-reinforced tungsten, and tungsten and SiC fiber composites. Each material’s fabrication and benefits are described, and some discussion of remaining questions is given.

Original languageEnglish (US)
Pages (from-to)662-670
Number of pages9
JournalFusion Science and Technology
Volume79
Issue number6
DOIs
StatePublished - 2023

Funding

This paper has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the U.S. Department of Energy (DOE). The U.S. government retains and the publisher, by accepting this paper for publication, acknowledges that the U.S. government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this paper, or allow others to do so, for U.S. government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan ( http://energy.gov/downloads/doe-public-access-plan ). This work is part of the U.S.-Japan FRONTIER Collaboration supported by the DOE, Office of Fusion Energy Sciences, and the Ministry of Education, Culture, Sports, Science and Technology, Japan. Research is sponsored by the DOE, Office of Fusion Energy Sciences, under contract DE-AC05-00OR22725 with UT-Battelle, LLC. J. R. Trelewicz acknowledges support from the DOE, Office of Fusion Energy Sciences, under contract DE-SC0017899. This paper has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the U.S. Department of Energy (DOE). The U.S. government retains and the publisher, by accepting this paper for publication, acknowledges that the U.S. government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this paper, or allow others to do so, for U.S. government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan).

Keywords

  • Plasma-facing materials
  • fusion materials, review
  • plasma-facing components

ASJC Scopus subject areas

  • Civil and Structural Engineering
  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering
  • General Materials Science
  • Mechanical Engineering

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